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Proiecte colaborative de cercetare aplicativă
Domeniul 8: Spaţiu şi securitate
Direcţia de cercetare 8.5. Sisteme şi infrastructura de securitate Tematica de cercetare 8.5.3. Sisteme pentru asigurarea unui management eficient al situaţiilor de criză şi al intervenţiilor în
cazul dezastrelor, sisteme de detecţie, prevenire şi alertă. Aprobat: Ordinul MEN nr. 298/23.06.2014
Contract Nr. 298
SISTEM DE ALERTARE TIMPURIE SI ASISTARE COMPUTERIZATA A DECIZIILOR, BAZAT PE EVALUAREA ANTICIPATIVA A DINAMICII RAPIDE
A VULNERABILITATILOR INDUSE IN TERITORIU DE OBIECTIVELE NUCLEARE
N-WATCHDOG Raport tehnic #1 Decembrie, 2014
Etapa 1 Proiectarea Demonstratorului funcţional de concept N-WATCHDOG
(PoC) Act 1.1 Documentarea cunostintelor de Fizica; a datelor si modelelor specifice,
adaptate proceselor PoC-executabile; si a bibliotecilor de date. Solutii de implementare IT.
Baza de cunoştinţe, modelele, cerinţele de date, soluţii de implementare IT
RAPORT TEHNIC #1
Dan V. Vamanu, Valentin T. Acasandrei Institutul National de Cercetare-Dezvoltare pentru Fizica si Inginerie Nucleara ‘Horia Hulubei',
IFIN-HH Bucuresti Departamentul de Fizica Vietii si Mediului
Cuprins Pro Memoria: Planul de realizare, Etapa 1 ........................................................................ 1 1. Introducere ...................................................................................................................... 2
1.1. Conceptul N-WATCHDOG ...................................................................................... 2 1.2. Motivatia ................................................................................................................. 3 1.3. Termeni de referinţă ................................................................................................ 4 1.4. Cerinţe şi aşteptări, din perspectiva utilizatorului ................................................... 11
2. Termenul sursă al emisiilor atmosferice radioactive.................................................. 13 2.1. Definiţia ................................................................................................................. 13 2.2. Soluţii de evaluare................................................................................................. 13 2.3. Iniţiatorul: accidentul de referinţă ........................................................................... 16 2.4. Modelul ................................................................................................................. 17 2.5. Soluţia de implementare: arborii de eveniment ...................................................... 25
3. Dispersia atmosferică ................................................................................................... 34 3.1. Definiţia ................................................................................................................. 34 3.2. Soluţii de evaluare................................................................................................. 35 3.3. Soluţii IT ................................................................................................................ 51
4. Evaluarea radiologică a unei emisii atmosferice radioactive..................................... 64 4.1. Definiţie ................................................................................................................. 64 4.2. Mărimile fizice de bază ale dozimetriei radiaţiilor ionizante .................................... 64 4.3. Dozimetria accidentelor nucleare .......................................................................... 67
5. Analiza de vulnerabilitate ............................................................................................. 73 5.1. Definiţie ................................................................................................................. 73
6. Datele în N-WATCHDOG: biblioteci şi gestiune .......................................................... 85 6.1. Relaţiile bibliotecilor de date cu modulele funcţionale ............................................ 85 6.2. Gestiunea librăriilor de date .................................................................................. 87
Referinţe ............................................................................................................................ 88 ANEXA 1 Datele radiologice .......................................................................................... A1.1 ANEXA 2 Datele meteorologice..................................................................................... A2.1 ANEXA 3 Datele geografice ........................................................................................... A3.1 ANEXA 4 Supliment bibliografic ................................................................................... A4.1
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Pro Memoria: Planul de realizare, Etapa 1
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1. Introducere
No problem can be solved
from the same level of consciousness that created it.
Albert Einstein
1.1. Conceptul N-WATCHDOG Proiectul N-WATCHDOG are ca obiectiv realizarea unui ansamblu multidisciplinar de soluţii practice, orientate spre nevoile utilizatorilor de monitorizare a vulnerabilităţilor induse de obiectivele nucleare în teritoriul înconjurător, starea populaţiei, mediu şi infrastructuri, având un pronunţat caracter preventiv bazat pe capacitate anticipativă şi de alertare timpurie. Ȋn esenţă, sistemul va prognoza non-stop, cu o frecvenţă reglabilă (orară etc.), pe intervale de timp anticipate de 8 sau mai multe ore, expunerea, impactul radiologic potenţial şi eventualele măsuri de reacţie necesare în zona apropiată de obiectiv (cca. 25 km) ca şi în zona depărtată (zeci sau sute kilometri), postulând emisii radioactive virtuale în atmosferă; apoi va agrega indicatorii obţinuţi în grade de expunere, impact si vulnerabilitate pe scale inteligibile pentru utilizatori si va oferi rapoartele de sinteza partilor interesate. Ȋn acest scop, vor fi articulate intr-o secventa logica de procese excutabile modele analitice de evaluare radiologica si modele conceptuale de analiza cantitativa a riscului si vulnerabilitatii, integrate cu resursele relevante de date fizice, geografice (GIS) si de documentie stiintifica. Sistemul se va alinia stadiului actual al solutiilor dezvoltate de consortii tehnice de referinta, propunand, totodata, abordari inovative în materie de (a) mentalitate: acceptarea sistematica a posibilitatii reale a unor accidente severe dincolo de ‘baza de proiect', de evaluarea probabilista a riscului si de registrele de securitate operationala; (b) ontologie: accent pe dinamica rapida a vulnerabilitatilor în sincronie cu meteorologia zonala si alte variabile; (c) acoperirea tematica: o masina radiologica acomodand diferite modele de dispersie în mediu a poluantilor; o masina geografica ce poate adresa ad-hoc orice locatie de pe Planeta; o masina meteorologica obtinand în timp real prognozele relevante din surse Internet publice; (d) o combinatie de moduri de operare 'standalone' si pe pagini-web ce confera sistemului siguranta operationala; si (e) o complexitate proiectata minimalist, cu observarea stricta a 'nivelului suficient de necesitate'. In deplina cunostinta de legile, reglementarile si misiunea institutiilor nationale creditate în domeniul pregatirii pentru situatii de urgenta si raspunsului la crize [1–4], sistemul propus va completa capacitatile curente cu noi abordari si solutii consonante cu termenii de referinta si bunele practici internationale, pe baze stiintifice valide asigurate de Fizica si Dinamica Fluidelor, Stiintele Mediului, Geografie, Stiintele Formale si Ingineria Informatica. Dedicat nevoilor si specificului tarii, sistemul va acorda, totodata, o deosebita atentie implicatiilor trans-frontiera ale proceselor analizate, cautand cai posibile de inter-operare cu platformele europene cu vocatie similara si urmarind consecvent consistenta cu politicile UE în materie (Directiva Consiliului, 96/29/EURATOM [5] cu deciziile si reglementarile ulterioare). In cadrul unui consortiu alcatuit dintr-un institut national de cercetare-dezvoltare, o importanta universitate politehnica si o proeminenta companie privata proiectul isi propune dezvoltarea unui model experimental software denumit N-WATCHDOG care, ulterior proiectului, poate evolua intr-un produs comercializabil capabil sa ofere unei varietati de utilizatori – entitati de guvernanta, ONG, foruri media - facilitati customizate interactive precum si/sau servicii analitice si de alertare timpurie. Prin calitatile educationale intrinseci, derivand din capacitatile sale avansate de simulare si vizualizare (‘serious gaming’), sistemul poate contribui si la cresterea nivelului de informare în materie al Societatii Civile, incurajand o viziune mai echilibrata asupra meritelor si riscurilor inerente ale Energiei Nucleare, în lumea de dupa Fukushima-2011.
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1.2. Motivatia Una din constatarile semnificative cu privire la asa-numitele 'evenimente nucleare anormale' (abnormal nuclear events), incluzand catastrofele, inregistrate în ultima jumatate de secol - de la Windscale (1957) la Three Mile Island (1979), la Cernobal (1986) si, recent, la Fukushima (2011) - semnaleaza insuficienta recurenta a starii de pregatire pentru managementul adecvat al situatiilor de urgenta, incapacitatea de raspuns prompt si, în special, lipsa unor abordari pro-active din partea actorilor implicati fata de evolutiile violente dincolo de 'accidentul baza de proiect', considerate 'inimaginabile' sau, cu o metafora curenta 'lebede negre' (black swans).
La originea acestei stari de lucruri se poate identifica o combinatie de factori motivanti, incluzand subevaluarea riscurilor de accident sever în consecinte în temeiul presupusei lor probabilitati neglijabile - o postura ancorata în mentalitatea academica instaurata în urma Raportului Rasmussen [6] din anii '70 - în pofida schimbarilor decurgand, intre timp, din imbatranirea fizica si morala a tehnologiilor si instalatiilor, fapt ce ar pretinde o atitudine mult mai precauta; la aceasta adaugandu-se foamea imperativa de energie a societatilor dezvoltate, energo-intensive, ca si exigentele puterilor economice emergente si ale regiunilor cu demografie scapata de sub control - fapt ce pune în ocultatie considerentele de risc si tinde sa mentina la nivel scazut cheltuielile de prevenire a consecintelor unor politici precare în materie de siguranta tehnica si securitate energetica.
Se apreciaza ca un factor subiacent al neajunsurilor mentionate ar putea fi o perceptie depasita a Riscului si atitudinea fata de dezastre ce decurge din aceasta (Figura 1). Este, intr-adevar, un fapt indubitabil ca, pe parcursul celor peste 6 decenii de existenta a industriei nucleare, managementul Securitatii Nucleare a cunoscut o alunecare graduala, tacita dar irezistibila de la o filosofie sedativa, intemeiata pe presupusa valoare de referinta a 'accidentului baza de proiect', inspre revelatia incomoda, dar sprijinita de fapte, ca 'accidentul de probabilitate scazuta dar severitate ridicata' domina de facto tot mai mult considerentele de risc nuclear si ar merita, în consecinta, o prioritate mai inalta în politicile si planificarea managementului urgentelor de profil.
Odata acceptata, aceasta constatare atrage o revizuire pe trei paliere a atitudinii formatorilor de politici si planificatorilor: (a) în mentalitate: de la aversiunea traditionala fata de eventualitatea 'dezastrelor', la acceptarea posibilitatii reale a acestora vazuta ca o mai austera dar necesara disciplina a mintii, ca stimulent si oportunitate de ridicare a nivelului de vigilenta si a capacitatii de raspuns la crize; (b) în metoda: de la solutii reactive la solutii pro-active, anticipative, de tipul 'CE anume s-ar intampla daca, INTR-ADEVAR, s-ar intampla?'; si (c) în alegerea tintei
Fig. 1. Pregatirea pentru dezastre –
o paradigma în evolutie
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preocuparilor: de la riscuri, la vulnerabilitati1. Analistii inclinati sa vada în acest demers o transgresiune ideologica de natura sa conduca la o 'cultura a fricii', care ar putea agrava perceptiile gresite asupra 'Nuclearului' punand si mai mult în chestiune viitorul acestuia sunt invitati sa ia nota de contextul mai larg al problemei, bine ilustrat de rezultatele anchetei academice independente solicitata de U.S. National Intelligence Council în pregatirea raportului 'Global Trends 2030: Alternative Worlds' [7]. Din toate documentele acestei serii de referinta, evaluatorii au recomandat atentie deosebita 'aprecierilor categorice privind o frecvenţă asteptata ridicata a unor socuri si discontinuitati' în deceniile ce urmeaza, propunand dezvoltarea si asumarea unui 'cadru metodologic superior pentru o intelegere autentica a raporturilor dintre tendinte, discontinuitati si crize', precum si 'mai multa intelegere pentru consecintele secundare si tertiare', în incercarea de 'a identifica dezechilibrele ce se profileaza, prin exercitii intensive de simulare si 'jocuri de razboi' (war games), pentru surprinderea dinamicii faptelor în momente indicative cruciale'. Pastrand proportiile, proiectul pe care il propunem profeseaza convingerea ca 'un cadru metodologic superior pentru o intelegere autentica a raporturilor dintre tendinte, discontinuitati si crize' în evolutia Nuclearului (i) va trebui sa adreseze în mod necesar si prioritar chestiunea Securitatii Nucleare ca factor cardinal în echilibrarea perceptiei sociale a domeniului; (ii) va trebui sa imbratiseze o atitudine anticipativa, realista si precautionara fata de eventualitatea evenimentelor grave; (iii) va trebui sa considere toate eventualitatile ca 'imaginabile', inainte de a le respinge din principiu sau prejudecata; si (iv) este potrivit sa initieze, în sensurile aratate, solutii concrete la nivelul nevoilor de baza, ca pasi mici dar semnificativi, în pregatirea unor eventuale evolutii reformatoare majore. Fata de acestea, Partenerii proiectului considera că relevanta practica a proiectului rezida în materializarea, la un nivel de utilitate convingator, a recomandarilor de actiune implicite în analizele evocate, ale surselor de recunoscuta autoritate în materie: pregatiti-va pentru iminenta 'inimaginabilului'; priviti inainte, incercand sa determinati în mod fundamentat 'CE anume s-ar intampla daca, INTR-ADEVAR, s-ar intampla'; concepeti instrumentele de asistare a deciziei ca resurse de lucru ante factum, mai mult decat post factum; asigurati-va ca rezultate inteligibile ajung la indemana agentilor politici si sociali responsabili cu protejarea oamenilor, proprietatii, infrastructurilor si a Societatii în ansamblu. In vederea acestor obiective, cadrul tematic al proiectului va articula intr-o secventa logica de procese excutabile modele analitice de evaluare radiologica si modele conceptuale de analiza cantitativa a riscului si vulnerabilitatii integrate cu resursele relevante de date fizice, geografice (GIS) si documentatie stiintifica de profil. In acest scop vor fi mobilizate intr-un efort convergent elemente de cunoastere si metoda din Fizica si Dinamica Fluidelor, Stiintele Mediului, Geografie, Stiintele Formale si Ingineria Informatica, ce vor asigura intregii initiative o baza stiintifica adecvata. 1.3. Termeni de referinţă Domeniul Asistarii analizei si deciziei în pregatirea pentru managementul urgentelor nucleare a aparut ca o extensie a unei ramuri formale a Fizicii – Radioprotectia si Securitatea Nucleara, constituita odata cu aplicatiile Fizicii Nucleare în anii consecutivi ultimului Razboi Mondial. Dezvoltarea domeniului a fost stimulata de o serie de incidente operationale la prima generatie de centrale nuclearo-electrice, culminand cu primul accident nuclear de larga notorietate, la Windscale (Marea Britanie), în 1957 – an în care s-a constituit si organizatia Atoms for Peace a Natiunilor Unite, cunoscuta ulterior ca Agentia Internationala pentru Energia Atomica (IAEA).
1 Vulnerability: characteristic of design, location, security posture, operation, or any combination thereof, that
renders an entity, asset, system, network or geographic area susceptible to disruption, destruction or exploitation. Vulnerability degree: qualitative or quantitative expression of the level to which an entity, asset, system, network or geographic is susceptible to harm when it experiences a hazard (DHS Risk Lexicon 2010 Edition, U.S. Dept. Of Homeland Security).
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Necesitatea unei activitati cu o identitate proprie dedicata situatiilor de urgenta s-a consolidat dupa accidentul nuclear de la Three Mile Island (SUA), în 1979 si a capatat dimensiuni dramatice dupa accidentul de la Cernobal (URSS/Ucraina), din 1986 – retinut drept cel mai sever din istoria energeticii nucleare în termenii consecintelor de mediu si sanitare. Seria evenimentelor improbabile dar de mare severitate a continuat cu accidentul de la centrala Fukushima-Daiichi (Japonia, 2011), ce tinde a fi notat drept cel mai sever prin urmarile sale asupra politicilor nucleare din intreaga lume – fara a ignora, desigur, tributul în victime, destructurari ale vietii oamenilor si pierderi de valori materiale.
N-WATCHDOG în contextul Emergency Preparedness (EP)
Initial, activitatea în domeniu s-a concentrat pe elaborarea de concepte disciplinare, metodologie si proceduri – ce au format substanta reglementarilor nationale si a recomandarilor si ghidurilor de conduita la nivel international (v. Nuclear Safety Series si seria documentelor tehnice – TECDOC ale IAEA). De importanta centrala în aceasta etapa a fost conceptul Emergency Preparedness – Pregatirea pentru situatii de urgenta. Urmatorul extras rezuma modul curent de formalizare conceptuala a acestuia.
Modern Emergency Management principles originate in the U.S. where, in 1979 the NGA came up with the Comprehensive Emergency Management document [8] as a first systematic attempt to formalize the concepts, components and processes of EM. The NGA document describes the EM as a four (overlapping) phase process. Despite various adaptations and even alternative approaches taken ever since, there seems to be, over the last 30 years, a consensus within the EM community regarding this aspect, the four-phases becoming somehow standard (see Figure 2). [9, 10].
In short, the four phases of EM are:
Phase 1: Mitigation – comprises the effort to reduce loss of life and property by lessening the impact of disasters. This phase implies (yet is not limited to) actions like identifying hazards and threats, analyzing risks, eliminating and/or reducing risk, identifying the residual risk.
Mitigation-oriented activities should be considered long before an emergency occurs.
Fig. 2. The Emergency Management cycle.
The standard, 'Four-Phase' approach [11].
Phase 2: Preparedness – following mitigation, preparedness basically implies getting ready to handle the residual risks. The practical expression consists of a variety of activities to minimize the consequences of a disrupting event on humans, property and environment. Emergency preparedness (EP) is one of the core components of the overall process of emergency management. In a nutshell, emergency preparedness is a continuous cycle of planning, managing, organizing, training, equipping, exercising, creating, monitoring, evaluating and improving activities (Figure 3) so as to guarantee effective coordination and enhanced capabilities to prevent, protect against, respond to, recover from, and mitigate the effects of any kind of disasters [11].
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As with the mitigation, preparedness-oriented activities should be performed long before the event
occurrence.
Fig. 3. Typical Emergency Preparedness activities cycle
Phase 3: Response – also called the ‘golden 72 hours’; this component consists in putting into practice and applying all the expertise and knowledge prepared in the two phases before. Response phase includes the mobilization and coordination of the necessary emergency services and first responders and the actual intervention. In view of assessing the EM efficiency, response is the crucial indicator. Acting coherently, promptly, responsible, safely, and professionally in front of an actual emergency is the paramount objective of the entire EM process. In close relationship with the event timing, response occurs during or immediately following an event. Phase 4: Recovery – is a systematic attempt to restore the affected area to its previous, or otherwise better, state. Recovery activities can be short-term or long-term. Actions selection and prioritization is also a result of preparedness. Recovery is a process that starts after the event is consummated (all the danger is gone and the situation is totally under control). Sursa: Vamanu B.I., Acasandrei V.T.(2014). Terms of Reference for Assessing Nuclear and Chemical Emergencies in view of preparedness and response. – An outlook. Romanian Journal of Physiscs, in print.
In raport cu acest cadru de referinta,
N-WATCHDOG addressess Preparedness...
By anticipating (forecasting) Exposure from, and Impact of virtual, possible
Events, in consideration of target (communities) Vulnerabilities – including
target Mitigative capability,...
That all drive Response...
And prefigure Recovery
N-WATCHDOG is a tool addressing Planning,
aiming however to asserting itself as a leading actor serving all the other
Preparedness cycle components.
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N-WATCHDOG în contextul Decision Support Dystems (DSS) Sub presiunea evenimentelor, etapa academica a fost rapid surclasata si, totodata, complicata inaintea unor clarificari definitive, de deplasarea rapida a interesului spre instrumente de evaluare computerizata, acomodate sub sintagma Decision Support Systems – Sisteme de Asistare a Deciziei – o miscare evident stimulata de progresul stiintei si tehnologiei informatice.
In prezent, puternice consortii de cercetare-dezvoltare ale puterilor nucleare majore si alte tari dezvoltate incluzand Statele Unite, Germania, Franta, Marea Britanie, tarile scandinave, Japonia si – mai discreta ca vizibilitate dar, fara indoiala, eficienta – Federatia Rusa dezvolta si promoveaza puternice pachete software ce stabilesc nivelul superior de referinta al domeniului. Tabelul 1 prezinta o selectie sumara de produse larg citate la nivel international, consonante cu contextul proiectului.
Ca rezultat tangibil al proiectului, N-WATCHDOG imparte cu sistemele IT de referinta o serie
de insusiri. Intre asemanari se recunosc:
Capacitatea de a fi utilizat atat ca instrument asistare a raspunsului la crize, cat si ca instrument de planificare în asigurarea starii de pregatire.
Capacitati diagnostice si prognostice.
Conformarea cu cea mai raspandita si recomandata disciplina metodologica în modelarea proceselor de mediu – modelele gaussiene.
Utilizarea dozelor echivalente de radiatie ca indicatori ai contramasurilor necesare si ai efectelor sanitare posibile ale expunerilor la radiatii ( nu a Nivelelor Derivate de Interventie)
Particularitatile N-WATCHDOG impun atentiei, pe de alta parte, cateva aspecte distinctive:
Profilul In contrast cu referintele citate si în incercarea de a contribui complementar, pe
aspecte mai putin, sau deloc acoperite de acestea în raport cu abordarea descrisa, N-WATCHDOG va oferi utilizatorilor:
O concentrare a misiunii pe monitorizarea anticipativa, practic continua (regim ‘24/7’) a efectelor potentiale ale unor emisii radioactive virtuale în atmosfera transporate în mediu conform prognozelor meteorologice actualizate orar, sau mai frecvent, pe intervale de 8 sau mai multe ore (de exemple, 72 ore).
O extensie a evaluarilor dozimetrice de impact conventionale (‘relatie doza-efect’) – practicate si de codurile de referinta – la evaluari bazate pe agregarea variabilelor dozimetrice cu datele GIS – demografie, infrastructuri, capacitati de productie si servicii, indicatori de relevanta sociala si strategica pentru comunitatile virtual expuse, în indicatori de vulnerabilitate inteligibili pentru utilizatorii profani în materie, incurajati a mentine o stare de vigilenta informata fata de situatii deosebite.
Tabelul 1. Coduri de referinţă
Origin Code acronym
ComplexityH-high
M-medium L-low
European consortium RODOS [12] H
European consortium COSYMA [13] M
Scandinavian consortium ARGOS [14] H
France CERES [15] H
U.S.A. ARAC/NARAC [16] H
U.S.A. RASCAL [17] M
U.S.A. HOTSPOT [18] L
U.S.A. GENII [19] M
U.S.A. MACCS [20] H
Japan SPEEDI [21] H
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Fig. 4. N-WATCHDOG – ontologia.
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Fig. 5. N-WATCHDOG – Fluxul procedural
O aplicare sistematica a principiului minimei complexitati necesare (‘the point of diminishing return’) [22] în modelarea emisiilor radioactive, migratiei lor în mediu si a consecintelor sanitare, ceea ce califica N-WATCHDOG drept o solutie practica minimalista.
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O adresabilitate a produsului dominata de un continut si un format ce tintesc direct spre managerii si operatorii raspunsului la urgente, în ceea ce se desemneaza drept ‘Faza timpurie’ (Early Phase) a unui eveniment nuclear anormal – ceea ce consolideaza calitatea N-WATCHDOG de sistem de detectare a amenintarilor si alertare timpurie, (‘watchdog ‘= caine de paza’) în ordinea de idei a Temei 8.5.3. a competitiei PN-II-PT-PCCA-2013-4.
Ontologia
‘Dincolo de stadiul actual’ – în opinia autorilor propunerii – se situeaza si o calitate speciala a N-WATCHDOG, constand în capacitatea sistemului de a opera: (a) în mod ‘evaluare completa’ (full-assessment), implicand postularea de termeni-sursa si amstecuri de radionuclizi determinate de cod conform modelelor de referinta utilizate; sau (b) independent de radionuclizi, utilizand în acest caz drept indicator al expunerii o metrica adecvata, aplicata Factorului de Dilutie (1/m2 sau s/m3, în functie de model) – un derivat de prima evidenta al dispersiei atmosferice a poluantilor ce nu necesita postularea unor termeni-sursa. Aceasta abordare, ce tine seama de traditionala susceptibilitate a operatorilor de centrale nucleare fata de aprecieri postulative privind radioactivitatea evacuata în mediu, venite din afara propriului sistem, mentinand, în acelasi timp, o capacitate credibila de a evalua expuneri si vulnerabilitati a fost remarcata cu interes de Centrul de incidente si urgente (Incident and Emergency Centre) al IAEA, cu prilejul unei recente reuniuni de consultanta privind solutii de imbunatatire a metodologiei curente [23]. O schema indicativa a ontologiei intentionate în dezvoltarea N-WATCHDOG se prezinta în Figura 4.
Fluxul procedural Se intentioneaza ca fluxul procedural al N-WATCHDOG sa reflecte ontologia propusa. Noutatea solutiei este insa accentuata de capacitatea codului de a functiona (a) în Mod automat, ciclând secventa de analiza în maniera ‘24/7’ fara asistenta utilizatorului (‘unattended sessions’) cu timpi de actualizare ajustabili (tipic – o ora), consistent cu ritmul adoptat de cele mai multe site-uri de date meteo public-disponibile; sau (b) în Mod analitic, în sesiuni asistate de utilizator, compartimentate de cereri de input si mesaje explicative. In timp ce Modul automat va fi, probabil, preferat de utilizatorii familiarizati cu sistemul, Modul analitic va servi mai cu seama fazele de initiere si antrenament si va oferi, totodata, dezvoltatorilor platforma de intretinere si upgrade a codului. O versiune simplificata a fluxului procedural al N-WATCHDOG se prezinta în Figura 5.
Arhitectura produsului final In versiune finala, N-WATCHDOG se intentioneaza a fi o platforma operationala ce va utiliza un model tip n-tier, web-enabled, cu un nucleu de modelare, simulare si vizualizare (MS&V) integrat cu librarii GIS de date fizice si de cunostinte specializate. Platforma N-WATCHDOG-beta avuta în vedere ca produs livrabil al proiectului va dispune de o functionalitate moderna, avand ca trasaturi esentiale:
Organizarea: implicand functiuni extinse de modelare; o masina versatila de simulare; si capacitati adecvate de achizitie, pre-procesare si actualizare a resurselor de date.
Capacitatea de vizualizare: generatoare de vizualizare analitica a datelor si reprezentari grafice pe desktop si exportabile-web.
Masina de interogare – adresand si datele spatiale.
Integrarea: acoperind date numerice si spatiale, precum si configuratii diagnostice.
Masina de analiza a datelor: o facilitate esentiala acomodand algoritmi si standarde de management al datelor.
Capacitate predictiva si interactivitate avansata – calitati ce evidentiaza elemente de originalitate în conjugarea de interogari punctuale cu raportari sinoptice.
Sistemul va fi interactiv cu utilizatorul pe parcursul tuturor secventelor de modelare. Utilizatorul va putea interveni la momente determinate, reluand procesul de modelare pe seturi de noi ipoteze, consistent cu disciplina de lucru de tip ‘what if’ scenarios. Sistemul va fi, de asemenea, capabil sa alerteze utilizatorul asupra unor erori, sau inadvertente în input.
11
Utilizatorul va putea modifica date fizice statice, sau chiar fisiere intregi de date-default de o anumita complexitate, astfel incat sistemul sa reflecte convingerile sale experte si preferintele fata de anumite date intr-o maniera amicala (‘friendly code behaviour’). Operand intensiv cu date spatiale, sistemul va prezenta o ergonomie de tip ‘on-click’ ori de cate ori posibil. 1.4. Cerinţe şi aşteptări, din perspectiva utilizatorului Faţă de cele de mai sus, s-a apreciat ca N-WATCHDOG trebuie sa satisfaca urmatoarele cerinte cu valoare identitara pentru statutul de solutie originala si inovativa în domeniul sau – managementul urgentelor nucleare:
Sa constitue o trusa de instrumente minimalista, capabila insa de o acoperire cuprinzatoare a nevoilor unei analize extinse dincolo de limitele conventionale ale Evaluarii radiologice (Radiological Assessment), la evaluarea anticipativa a vulnerabilitatilor induse în populatie, comunitati si valori materiale, sociale, strategice.
Sa prezinte o functionalitate orientata spre anticipare, oferind prognoze de 'situatie' în mod '24/7' pe diferite durate, în mod orar sau mai frecvent.
Sa articuleze intr-o singura structura coerenta termeni-sursa – amestecuri de nuclizi si parametri de emisie, cu modele de dispersie în 'Vecinatatea apropiata' ca si în 'Vecinatatea indepartata' (Near/Far-Field) a surselor de emisie radioactiva, utilizand modele adecvate (plumes, puff trails).
Sa poata adresa, practic, orice sursa fixa sau incidentala de emisie radioactiva de pe Glob, asigurand generarea expeditiva, ad-hoc de harti topografice din resurse digitale (DEM) asimilate si date GIS rezidente, eliminand nevoia stocarii masive si, inerent, incomplete, de harti ante-preparate.
Sa poata procura prompt, în mod off-line browsing, prognozele meteorologice necesare modelelor de advectie-difuzie atmosferica, de pe site-uri Internet publice de profil.
Sa poata lucra, alternativ, în mod independent de opinia/implicarea agentului poluant ('Polluter-unbiased mode'), fara necesitatea invocarii de termeni-sursa chestionabili de catre acesta, strict în temeiul factorilor de dilutie atmosferica; sau la intreaga capacitate, implicand termeni-sursa postulati, doze, contramasuri, efecte sanitare si interpretari ale impactului în relatie cu prescriptiile de reglementare ('Polluter-biased mode').
Sa poata acomoda scenarii de eveniment alternative ('what if' scenarios) pentru aceleasi prognoze meteorologice din rezerva stocata si de a trata emisii multiple din diverse surse, sau provenind din diferite episoade de emisie ale aceleiasi surse.
Sa prezinte un design al fluxului operational bazat pe rularea modelisticii si resurselor de vizualizare în mod standalone (pe desktop), urmata de comutarea sistemului în mod web-server si publicarea rezultatelor asamblate intr-un Raport de situatie ('SitRep'), incluzand un bilant Input/Output complet, hartile rezidente interactive si harti web sinoptice si cu interogare punctuala.
Sa asigure robustete operationala, realizata prin stocarea de prognoze meteo în perioade de disponibilitate Internet si efectuarea de evaluari chiar si atunci cand retelele sunt scoase din functiune – o eventualitate de luat în considerare în perioade de criza.
Interfata original-proiectata a codului, cu toate elementele de input secvential acumulate, permanent 'la vedere' si editabile în mod-text, amical pentru utilizator (user-friendly).
Sa dispuna de o consistenta baza de resurse rezidente, incluzand harti digitale de elevatie (DEM); date GIS; librariile de date fizice, date de reglemetare si cunostinte.
Sa sprijine utilizatorii printr-o 'Biblioteca virtuala', conceputa ca o selectie actualizabila de documentatie de insemnatate speciala în administrarea situatiilor de urgenta nucleara.
Sa exploateze la maximum multidisciplinaritatea inerenta a sarcinii asumate si expertiza corespunzatoare a Partenerilor de proiect (Figura 6).
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Fig. 6. Contributori disciplinari ai proiectului si articularea lor intr-o abordare multi-disciplinara.
Baza de cunostinte, modelele, cerintele de date si solutiile de implementare IT decurg în mod natural din cerintele mentionate. Restranse la minimul indispensabil proiectarii si dezvoltarii IT a produsului, aceste elemente se prezinta în breviarul ce urmeaza. Detalii suplimentare de continut se pot obtine din bibliografia atasata Raportului, cu asistenta permanent asigurata a CO – IFIN-HH.
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2. Termenul sursă al emisiilor atmosferice radioactive
'We frequently give too little attention to the derivation of the source term, and yet this step is where the greatest potential lies for losing scientific and
stakeholder credibility. This is also the component of radiological assessment
that typically requires the most resources relative to the other steps.' Till [24]
2.1. Definiţia
In domeniul Nuclear Emergency Preparedness, termenul sursa se defineste astfel:
Source term
The amount and isotopic composition of material released or the release rate, used in modelling releases of material to the environment.
(IAEA -TECDOC-955, 1997 [25])
In logica evaluarii unei situatii radiologice consecutive unei emisii atmosferice radioactive, evaluarea termenului sursa ocupa prima pozitie (Figura 7):
Fig.7. Termenul sursa în logica Radiological Assessment.
2.2. Soluţii de evaluare In sens academic, evaluarea unui termen sursa consta în construirea si solutionarea unei ecuatii de bilant adecvate, reflectand migrarea materialului radioactiv – presupus a penetra accidental 'barierele de aparare în adancime' (defence-in-depth barriers) ale sursei primare de radiatii – în cazul în speta, un reactor nuclear – prin 'volumele de control' (control volumes) ale sistemului: tecile elementelor combustibile; vasul de presiune al reactorului; anvelopa (containment structure); si, eventual, alte spatii circuland 'aburul nuclear' (nuclear steam) – sala turbinelor etc (Figura 8).
14
Fig. 8. 'Volume de control' si ecuatii de bilant – solutia academica [26].
Date fiind dificultatile de conceptie si executie ale solutiei academice, organisme de reglementare nucleara de referinta (v. U.S. NRC) au adoptat si recomandat în 'manualele de raspuns' la accident nuclear (Response Technical Manuals, RTM [27]) o solutie simplificata, practica si oferind grade de incredere suficiente în adoptarea deciziilor de raspuns la
15
'evenimente nucleare anormale' (abnormal nuclear events). Cunoscuta drept 'Regula celor patru factori' (The Four-Factors Rule, 4FRule), solutia este explicata în Figura 9.
Fig. 9. 'Regula celor patru factori' [26].
16
2.3. Iniţiatorul: accidentul de referinţă Data fiind vocatia sa declarata – evaluarea anticipativa a vulnerabilitatilor induse de prezenta si functionarea obiectivelor nucleare – N-WATCHDOG se va concentra pe 'evenimente nucleare anormale' de tipul cunoscut drept 'Accident prin pierdere de racire' (Loss-Of-Coolant-Accident, LOCA). Relevanta LOCA decurge din faptul ca orice diminuare necontrolata a debitului, sau alta alterare a parametrilor prescrisi ai agentului de racire a zonei active a reactorului (reactor core) poate declansa un lant de evenimente soldat cu emisie de materie radioactiva în afara 'barierelor de aparare în adancime' – în mediul inconjurator.
Fig. 10. 'Subcooling margin negative' – diagnoza starii de alarma a conditiei zonei active a reactorului – prodromul unui LOCA [26].
17
In spiritul aceleiasi conduite ce a animat adoptarea 'Regulii celor patru factori' – a 'minimei complexitati necesare' (observance of Point of Diminishing Return, POD), manualele de raspuns atribuie generic LOCA iesirii accidentale din regimul de saturatie a 'aburului nuclear', fapt ce poate surveni
i) prin pierdere de presiune (pressure drop), sau
ii) printr-o 'excursie de temperatura' (temperature excursion) în circuitul de racire primar
(primary coolant loop) al reactorului (Figura 10).
Ambele eventualitati descrise – pressure drop si temperature excursion conduc la aceeasi diagnoza:
IF, for a given coolant pressure, temperature is HIGHER than saturation temperature, then Subcooling Margin is NEGATIVE and LOCA is possible.
IF, for a given coolant temperature, pressure is LOWER than saturation pressure, then Subcooling Margin is NEGATIVE and LOCA is possible.
2.4. Modelul 2.4.1. Algoritmul de bază Din acest punct, evaluarea termenului sursa urmeaza urmatoarele etape: Factorul timp al crizei de racire, explicat în Figura 11:
Fig. 11. Factorul timp, în determinarea tipului si severitatii consecintelor unui LOCA [26].
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Factorul #1 al 4FR: Inventarul de radioactivitate al zonei active (FPRi – Fission Product Inventory, nuclide i in inventory mix)
Calculat, în practica, pe baza unui inventar unitar de referinta, mediat în mod conservativ pentru reactorii moderati si raciti cu apa usoara (Light Water Reactors, LWR) si publicat în literatura deschisa (Figura 12). Problematic în cazul reactorilor moderati si raciti cu apa grea (Heavy Water Reactors, HWR), pentru care literatura este considerabil mai putin transparenta. Exprimat în unitati de activitate per megawatt-electric putere instalata (Ci/MWe, MBq/MWe).
Fig. 12. Formulare tipica a unui inventar unitar de activitate al zonei active – reactori LWR [26].
Factorul #2 al 4FR: Factorii de pierdere a activitatii din zona activa (CRFi – Core Release Fraction, of nuclide i )
Postuleaza proportia transgresiei nuclizilor-produsi de fisiune din zona activa a
reactorului (core) în volumul de control al anvelopei (containment). Fractii subunitare tabelate si publicate în literatura LWR (v. Figura 13). Practic indisponibile în literatura HWR deschisa. Factorul #3 al 4FR: Factorii de reducere a activitatii in containment (RDFmec – Reduction Factors, of nuclide i )
Postuleaza proportia în care mecanisme fizice pasive si solutiile tehnice active
instalate în anvelopa reactorului (containment) diminueaza nivelele de radioactivitate prin retinerea de material inaintea evacuarii controlate/scaparii necontrolate din avelopa. Fractii considerate independente de nuclid – o ipoteza simplificatoare (Figura 14). Tabulate pentru LWR, în functie de mecanismele de reducere. Practic indisponibile în literatura HWR deschisa.
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Fig. 13. Tabel de corelare a CRFi cu nivelele de afectare a zonei active de catre LOCA – reactori LWR [26].
Fig. 14. Tabel de corelare a RDFmec cu mecanismele de reducere – reactori LWR [26].
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Factorul #4 al 4FR: Factorii de pierdere ai anvelopei reactorului (EFcnt – Escape Factors, of containment )
Postuleaza proportia în care anvelopa reactorului 'pierde' în mod inerent în mediul
inconjurator material radioactiv. Fractii dependente de tipul de anvelopa si, partial, de tipul de accident (Figura 15).
Fig. 15. Factori de pierdere ai anvelopei – reactori LWR [26].
2.4.2. Modelul de evaluare: căile de emisie Generica în algoritm – 'Regula celor patru factori' – metodologia de referinta, recomandata de IAEA Viena prin documentul tehnic TECDOC-955/1997 devine specifica în privinta 'căilor de emisie' (Release Pathways) ale celor 7 tipuri de reactori cu apa usoara ce domina industria nuclearo-electrica în lume. Seria figurilor 16, 1 – 7 [27, 28] ilustreaza schemele adoptate în aceasta privinta prin consensul international al expertilor – autori ai documentului, ca reprezentative si aplicabile în caz de urgente nucleare. In considerarea lipsei de transparenta a originatorilor filierei HWR în materie, documentul citat nu acopera si problematica acesteia. Propunand spre implementare metoda TECDOC/955 – sprijinita de o substantiala serie de studii publicate de institutii de cercetare si organisme de reglementare nationale, N-WATCHDOG adopta, în cazul reactorilor cu apa grea – de interes special pentru Romania, ce a optat pentru filiera CANDU-PHWR, de origine canadiana – solutia de a recurge la 4 termeni-sursa prefabricati, identificati în literatura fara suportul analitic implicat, dar acoperitori pentru un numar egal de trepte de severitate a consecintelor accidentelor respective. Termenii astfel postulati vor deveni scalabili la interfata-utilizator a codurilor asigurand astfel, pe calea judecatii experte (expert, best-guess judgment) o minima flexibilitate în evaluarile radiologice.
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16.1. (PWR), Large-Dry Containment 16.2. Pressurized Water Reactor (PWR), Ice Condenser Containment
22
16.3. Boiling Water Reactor (BWR), Mark 1 Containment 16.4. Boiling Water Reactor (BWR), Mark 2 Containment
23
16.5. Boiling Water Reactor (BWR), Mark 3 Containment HWR
PENDING PUBLICATION BY ORIGINATORS/OPERATORS...
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16.6. VVER-440/230 (Eastern Europe) 16.7. VVER-440/213 (Eastern Europe and Finland)
Fig.16. Cai de emisie, pentru diferite tipuri de reactori cu apa usoara (LWR).
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2.5. Soluţia de implementare: arborii de eveniment In rezumat, evaluarea termenului sursa este condusa, în sistemul adoptat de N-WATCHDOG, conform fluxului logic rezumat în Figura 17:
Fig.17. Diagrama logica a schemei 4FR (Four-Factor Rule) [26].
Cei patru factori ai schemei 4FR implica, în moduri diferite, tipul de accident si caile de emisie respective, comportari distincte ale nuclizilor evadati din barierele de aparare în adancime (Defense-in-Depth Barriers), starea zonei active a reactorului (core condition), functiile de retinere pasive si active ale anvelopei si calitatile izolante (etanseitatea) acesteia fata de mediu.
Integrarea acestor elemente a necesitat o tehnica implementabila (i) initial la nivel de 'foi de lucru' preformatate (Worksheets), si ulterior, odata cu dezvoltarea mijloacelor IT de asistare a deciziei – la nivel de masina de calcul. Metoda recomandata de documentul de referinta, adoptata pentru nevoile N-WATCHDOG este cea a 'Arborilor de eveniment' (Event Trees).
Implementarea IT a acestora permite parcurgerea verificabila a cailor de emisie, de la factorul initiator al scaparii de radioactivitate la evacuarea efectiva în mediu a acesteia. Figurile 18, 1-14 [27, 28] redau arborii de eveniment considerati de literatura consultata suficienti pentru determinarea termenului sursa al principalelor evenimente anormale (abnormal events) ce pot interveni, cu probabilitati semnificative, la reactorii nucleari.
26
18.1 18.2
27
18.3 18.4
28
18.5 18.6
29
18.7 18.8
30
18.9 18.10
31
18.11 18.12
32
18.13 18.14
Fig.18. Arborii de eveniment considerati în sistemul N-WATCHDOG.
33
Se considera ca modelul de evaluare a termenului sursa al emisiilor atmosferice radioactive descris în prezenta sectiune în contextul bazei de cunostinte necesare este acoperitor pentru tipurile de reactori industriali cu apa usoara (LWR) în functiune în Europa - inclusiv si în mod special în vecinatatea Romaniei - si dominand industria nuclearo-electrica mondiala. Limitate, în cazul reactorilor cu apa grea (HWR) la un numar restrans de cazuri semnificative postulate, scalabile, codurile N-WATCHDOG vor fi proiectate si dezvoltate astfel incat sa poata acomoda, cu minime adaptari si reactorii HWR – daca informatia tehnica relevanta va deveni disponibila.
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3. Dispersia atmosferică 'It is expected that releases to the atmosphere
will contribute more to the (nonnatural) dose received by people than will releases to other environmental media.'
(Little1984, quoted by Till, 2008).
3.1. Definiţia
Din literatura domeniului se retine, pentru uzul proiectului, urmatoarea definire descriptiva:
La dispersion atmosphérique caractérise le devenir dans le temps et dans l’espace d’un ensemble de particules (aérosols, gaz, poussières) rejetées dans l’atmosphère. L’émission d’un produit à l’atmosphère peut revêtir un caractère :
soit chronique, avec des émissions à l’atmosphère plus ou moins continues ou périodiques dans le temps. Les rejets sont les sous-produits indésirables de toute activité humaine, par exemple, les gaz d'échappement des voitures, les fumées d'usines, de chauffages urbains ou toute forme de pollution diffuse (émission de gaz issu d'une décharge...);
soit accidentel, avec des émissions à l’atmosphère ponctuelles dans le temps, non désirées comme la fuite d'une cuve ou un dégagement de fumées dû à un incendie.
INERIS-DRA-2002-25427 [29]
In secventa de fenomene ce conduc de la emisiile radioactive la expunerea radiologica a populatiei dispersia atmosferica ocupa prima pozitie (Figura 19).
Fig.19. Radioecologia impactului de mediu si sanitar al industriei nucleare [24].
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3.2. Soluţii de evaluare Dispersia atmosferica (Atmospheric Dispersion, AD; uneori – Atmospheric Transport) este un proces complex, caruia Fizica Atmosferei i-a putut conferi un cadru de intelegere – inca limitat în capacitate diagnostica si predictiva - doar printr-o energica tratare reductionista.
Esenta modelului academic al dispersiei o constituie conservarea marimilor fizice implicate: conservarea masei (kg); conservarea impulsului (kg.m/s); conservarea cantitatii de caldura (J); conservarea unei proprietati caracteristice – în cazul proiectului de fata, activitatea (Bq, Ci).
Data fiind particularitatea sistemului fizic vizat – atmosfera – de a nu prezenta conditii la limita univoce la extremitatea superioara (ea insasi o notiune prost definita în sens matematic), sistemul complet de ecuatii cu derivate partiale ce articuleaza marimile mentionate nu are o solutie unica, si nici analitica.
Pentru a-l face util, ca baza a prognozelor meteorologice speculative (ce nu vectorizeaza, pur si simplu observatia, terestra sau satelitara a fronturilor atmosferice, maselor noroase etc.), stiinta domeniului a recurs, în principal, la doua tipuri de operatii: linearizarea; si scalarea, ajutate de Analiza dimensionala. Aproximatiile astfel obtinute sunt solubile prin analiza numerica, pe sisteme IT de performanta ridicata.
Fig. 20. Fenomene dominante retinute în modelarea, din perspectiva NEP, a dispersiei atmosferice [13].
Definirea unui model de valoare practica pentru NEP (Nuclear Emergency Preparedness) necesita insa o degradare suplimentara a solutiei academice. Astfel, – Pe palierul teoretic - tratarea în izolare a unei legi de conservare unice: conservarea activitatii; – Pe palierul practic – identificarea si modelarea adecvata a unui set limitat de fenomene demonstrabile experimental ca dominante în conditionarea rezultatului cautat: distributia spatiala si evolutia în timp a concentratiilor de entitate dispersata, cu efecte de mediu si sanitare, inclusiv afectarile economice si sociale ce creaza costuri indirecte în aprecierea impactului alterarii cadrului natural prin interventia entitatilor respective – Figura 20.
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3.2.1. Palierul teoretic Pentru scopurile N-WATCHDOG, autorii au dezvoltat o solutie compacta a problemei [30] prin: (a) linearizarea ecuatiei de dispersie a activitatii derivata din legea de conservare; si (b) rezolvarea acesteia prin metoda functiilor Green, metoda avand calitatea de a leaga termenul sursa de efectul de mediu al acestuia – distributia spatiala a concentratiei de
activitate (kBq/m3 sau Ci/m3) în spiritul unei relatii 'semnal-raspuns', descrisa printr-o integrala corespunzatoare. O compilare a etapelor esentiale în conducerea procesului se prezinta în Figura 21.
Fig. 21. Legea de conservare a activitatii (primul cadru rosu); ecuatia de dispersie linearizata (cadrul
albastru);elemente de calcul al propagatorului Green 'semnal-raspuns'; si solutia analitica integrala a distributiei spatiale a concentratiei de activitate, în modelul N-
WATCHDOG (al doilea cadru rosu).
37
Fig. 22. Solutiile ecuatiei de dispersie pentru sursa indicata în partea superioara a figurii, suficienta în
majoritatea evaluarilor radiologice. Emisie în intervalul de timp [0, tR]. Dimensiunile surse (m): Lx, Ly, Lz. In partea dreapta a figurii – solutiile pentru o sursa punctuala, adoptate de N-WATCHDOG
ca adecvate unui program de veghe si alertare radiologica prompta. Solutia obtinuta prezinta o deosebita versatilitate în raport cu geometria si rata de emisie a sursei, putand fi adusa, prin operatii algebrice relativ simple, la forme convenabile nevoilor N-WATCHDOG, ca program de veghe si alertare radiologica prompta (Figura 22), si anume: (a) Evaluarea radiologica a impactului emisiilor atmosferice radioactive pe intreaga arie de influenta semnificativa a unui obiectiv nuclear; si (b) Evaluarea radiologica a impactului emisiilor atmosferice radioactive în zona de proximitate a sursei potentiale, cea mai vulnerabila în principiu. 3.2.2. Palierul practic Reductiile solutiei redate în Figura 22 în scopurile indicate conduce la doua modele, consacrate în literatura si direct adaptabile aplicatiilor IT avute în vedere: :
Dispersia în pulsuri gaussiene – Gaussian Puff Trails; si Dispersia în pana gaussiana – Gaussian Plume.
38
3.2.2.1. Modelul Gaussian Puff Trails Ecuatia constitutiva de baza a modelului este:
n n
DF0(x,y,z) = 1/ [ (2)3/2 x(q) y(q) z(q) ] (DF1) p=0 q=p
.{ exp[-(zc - H)2/(2z2
(q))] + exp[-(zc + H)2/(2z2(q))]
+ exp[-(2hinv - z - H)2]/(2z2(q))] + exp[-(2hinv + z - H)2/(2z
2(q))]}
.{exp[-(x – xc)2/(2x
2(q))] . exp[-(y – yc)
2/(2y2(q))]}
in care:
xc, yc, zc (m) - coordonatele carteziene ale centrului 'pufului'; x, y, z (m) - coordonatele carteziene ale punctului observat;
H (m) - inaltimea sursei de emisie, presupusa punctuala;
hinv (m) - inaltimea stratului de inversie termica, o functie de clasa de sabilitate atmosferica
x, y, z (m) - coeficientii de dispersie pe directia axelor respective; depinzand de sistemul adoptat, acestia
pot fi: functii de timp – 'varsta', qa pufului din momentul emisiei în secventa (trail) de pufuri; sau functii de distanta, pe orizontala, a centrului pufului fata de sursa, calculabila prin cumularea segmentelor de drum parcurs de puff cu vitezele corespunzatoare momentelor respective, livrate de prognoza meteo.
(s) - este pasul de timp al secventei de pufuri; daca se alege ca secventa sa contina n pufuri, durata totala de observare a dispersiei emisiei atmosferice
(timpul de monitorare) este nsecunde; daca se
prescriu un numar de pufuri, n si un timp de monitorare tmon, atunci pasul de timp al secventei se deduce a fi tmon/n.
DF0(x,y,z) este Factorul de Dilutie brut – necorectat prin considerarea proceselor asociate advectiei-difuziei (v. sectiunea 3.2.3) - în punctul observat. Dimensiunea acestuia, s/m3, este determinata (a) de primul factor din membrul drept al ecuatiei, cu dimensiunea 1/m3 (ceilalti factori si termeni fiind adimensionali); si (b) de cea de-a doua suma - de fapt, o digitizare a unei integrale de timp, care adauga un factor s (secunda):
n n
∫ dt ~
p q=p
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3.2.2.2. Modelul Gaussian Plume Ecuatia constitutiva de baza a modelului este:
N
DF0(x,y,z) = 1 / [ 2 y(d) z(d) v ] (DF2) s=0
.{ exp[-(z – H(s))2/(2z2
(d))] + exp[-(z + H(s))2/(2z2(d))]
+ exp[-(2hinv - z – H(s))2]/(2z2
(d))] + exp[-(2hinv + z – H(s))2/(2z2(d))]}
.{exp[-x2/(2x2(d))] . exp[-y 2/(2y
2(d))]}
in care:
x, y, z (m) - coordonatele carteziene ale punctului observat; H(s) (m) - inaltimea sursei de emisie indexata s, presupusa
punctuala; hinv (m) - inaltimea stratului de inversie termica, o functie de
clasa de sabilitate atmosferica v (m/s) - viteza medie a vantului pe durata de
observatie(timpul de monitorare);
x, y, z (m) - coeficientii de dispersie pe directia axelor respective; depinzand de sistemul adoptat, acestia pot fi: în mod tipic, functii de distanta, pe orizontala, a punctului de observatie fata de sursa; se pot folosi si functii de timp – coreland distanta parcursa cu viteza;
d (m) - distanta punctului de observatie fata de sursa.
Suma se extinde asupra tuturor celor N surse participante la evenimentul de emisie.
Cazul cel mai comun este cel al unei singure surse. DF0(x,y,z) este Factorul de Dilutie brut – necorectat prin considerarea proceselor asociate advectiei-difuziei - în punctul observat. Dimensiunea acestuia este determinata strict de primul factor din membrul drept al ecuatiei, cu dimensiunea s/m3, ceilalti factori si termeni fiind adimensionali. 3.2.3. Procesele asociate Dupa cum s-a aratat, ecuatiile constitutive de baza ale modelelor livreaza Factorul de Dilutie brut al dispersiei. Prin traditie ele reflecta, din ansamblul de fenomene luate în cosiderare de abordarea practica a procesului, advectia (transportul în masa determinat de viteza si directia vantului), difuzia (expandarea norului radioactiv ejectat, caracterizata de coeficientii de dispersie), reflexia la sol si pe stratul de inversie a maselor de aer contaminate. O abordare a dispersiei revelatoare pentru impactul dozimetric al acesteia necesita insa si luarea în calcul a unor procese asociate, si anume:
Depunerea 'uscata' pe sol (Dry Ground Deposition); Depunerea 'umeda' pe sol (Wet Ground Deposition); Dezintegrarea radioactiva (Radioactive Decay); 'Saracirea' norului radioactiv (Cloud/Plume Depletion), ca urmarea a acestor
procese;
40
si, influentand intregul proces de dispersie,
Suprainaltarea norului radioactiv (Cloud/Plume Rise); si Clivajul vertical al norului/penei de efluent.
3.2.3.1. Depunerea uscată In contextul dat, depunerea uscata este rezultatul integrat în timp al intersectiei cu solul a fluxului de difuzie al activitatii. In timp ce, la nivel academic, modelarea procesului ocupa o intreaga literatura (v.e.g. [24]), la nivelul EPM se iau în considerare numai în mod indirect parametri ai vectorilor activitatii (stare de agregare, diametre, vascozitati etc.) – gaze sau aerosoli, prin intermediul unei 'viteze de depunere uscata' (Dry Deposition Velocity), vdry, data ca o functie de nuclidul considerat sau de clase de nuclizi. De regula, isotopii gazelor nobile (Kripton, Xenon) ce apar ca produsi de fisiune se considera a avea viteza de depunere uscata nula, în timp ce altor produse gazoase (e.g. iodura de cesiu) si aerosolilor li se atribuie viteze specifice, depinzand, în unele abordari si de natura suprafetei de depunere (sol, apa, zapada, iarba, padure). Detalii concrete se vor prezenta în sectiunea consacrata nevoilor de date ale N-WATCHDOG. Efectul de prima consecinta al depunerii uscate il constituie 'saracirea' (spolierea, debilitarea) continutului de activitate al norului/penei de efluent. Efectul se apreciaza printr- un Factor de saracire uscata (Dry Depletion Factor), calculat astfel: Fdry = exp(-vdry fdry/v), cu vdry –viteza de depunere uscata si v – viteza vantului, (F1) unde x
fdry = (/2)1/2 ∫d exp[-H2/(2z2())]/z()
0
integrala calculandu-se prin cuadraturi, pe distanta dintre sursa si punctul x parcurs prin advectie pana la momentul de interes. 3.2.3.2. Depunerea umedă Este rezultatul antrenarii activitatii aeropurtate (airborne activity) – de fapt, a purtatorilor materiali ai acesteia – de catre precipitatii. Precipitatia de referinta este ploaia, ninsoarea fiind tratata în literatura în termeni de 'ploaie echivalenta' (rain-equivalent).
Se calculeaza, prin integrare pe verticala de la 0 metri la infinit, o viteza de depunere umeda, astfel:
vwet = (/2)1/2 z exp(H2/(2z2)),
unde = a.Ib este o marime de calcul ce normeaza intensitatea ploii, I (mm/h) în raport cu natura nuclizilor, prin constantele specifice a si b. Factorul de saracire umeda (Wet Depletion Factor) este:
Fwet = exp(-. train), (F2) unde train (ore) este durata, observata sau presupusa, a ploii.
41
3.2.3.3. Dezintegrarea radioactivă Factorul de saracire prin dezintegrare radioactiva a norului/penei pe durata dispersiei atmosferice (Decay Depletion Factor) se calculeaza dupa cunoscuta lege exponentiala:
Fdecay = exp(- t), (F3)
unde = ln(2)/T1/2 ~ 0.693/T1/2 este constanta de dezintegrare a nuclidului din amestecul de izotopi radioactivi specificat de termenul sursa, dedusa din Timpul de injumatatire T1/2 al nuclidului, iar t este timpul scurs de la ejectia nuclidului. De notat ca, pentru inlesnirea calculatiei, disciplina 'de manual' în materie integreaza efectele filiatiei (formarea în cascada de noi nuclizi din antecesori prin dezintegrare si dezintegrarea consecutiva a acestora – descrisa de ecuatiile Bateman) în Factorii de Conversie la Doze (Dose Conversion Factors), ce vor fi explicati în sectiunea de Dozimetrie a Raportului. Relevanta proceselor de saracire depinde în masura importanta de trei factori: (i) timpul de injumatatire al nuclizilor implicati; (ii) durata de monitorizare a evenimentului; si (iii) regimul precipitatiilor.
Astfel, efectul saracirii asupra rezultatelor este considerabil în cazul dominarii în termenul sursa a nuclizilor de viata scurta, la durate de monitorizare mari, si în prezenta precipitatiilor; si poate deveni neglijabil în cazul contrar. In mod conservativ, N-WATCHDOG va lua constant în calcul efectele saracirii. Rezultatul net al proceselor asociate descrise consta în corectarea Factorului de Dilutie brut – ecuatiile (DF1) si (DF2), astfel: DF(x,y,z) = DF0(x,y,z).Fdry.Fwet.Fdecay (DF3)
Factorul de Dilutie efectiv, DF, astfel obtinut este marimea de prima importanta în evaluarea consecintelor unei emisii atmosferice radioactive. Astfel,
DF intervine ca marime de intrare indispensabila (input) în calculele dozimetrice care conduc, în final, la diagnoza de eveniment nuclear si recomandarile de contramasuri.
Pe de alta parte, distributia spatiala a DF (s/m3) poate constitui în sine o masura a
expunerii în aria de influenta a obiectivului nuclear, independent de o descriere completa a termenului sursa – subiect prin traditie controversat intre operatorii de obiective nucleare, tentati sa comunice date subestimate în materie si operatorii de management al urgentelor nucleare, tentati de un conservatism uneori excesiv.
3.2.3.4. Supraînălţarea norului/penei de efluent
Materia purtatoare de radioactivitate este ejectata din sursa de doi factori motori:
(i) impulsul mecanic; si (ii) continutul caloric. Proportia influentei acestora asupra inaltimii stabilizate (o medie teoretica a unei marimi în fapt fluctuante) a norului/penei radioactive variaza în functie de jocul presiunilor si temperaturilor în volumele de control ale obiectivului
42
– anvelopa, sala turbinelor, alte spatii de pe traseul cailor de emisie (v. sectiunea dedicata termenului sursa). Importanta evidenta a acestei etape a emisiei radioactive a determinat unii autori la o extindere a conceptului de termen sursa, care sa inglobeze nu numai problemele amestecului de nuclizi, ci si problema suprainaltarii. O disertatie completa fiind exclusa în limitele acestui breviar, se redau în continuare conceptele de adresare a subiectului în sistemul N-WATCHDOG. Modelul a retinut trei cazuri de interes: emisia; focul deschis; si focul în spatiu inchis. 3.2.3.4.1. Emisia Continutul radioactiv – gaze, vapori, aerosoli este ejectat prin orificii ale sistemelor de de evacuare controlata – cosuri de fum, valve de siguranta, filtre, sau în mod neontrolat prin sparturi ale anvelopei sau ale altor structuri de confinare.
HOT MIX - INPUT
_______________
Change defaults if/as appropriate.
When ready, 'PROCEED' from menu.
_________________________________
Physical Constants
------------------
PI Number, pi: 3.1415926
Gravity Acceleration, g (m/s2): 9.812
Ideal Gas Constant, Ridg (J/(mol.K))): 8.314
Mechanical Equivalent of Calorie (J/cal): 4.186
Air Molar Mass (kg/mol): 0.0289
Air Specific Heat (cal/(g.K)): 0.24
Air Density (g/m3): 1290
Release Data
------------
Venting Height (m AG): 40
Venting Diameter, Dvent (m): 3.7
Venting Velocity, w0 (m/s): 8.33
Vent Gas Temperature, tG (C): 90
Vent Gas Molar Mass, miug (kg/mol):0.0289
Ambient Temperature (C): 20
Ambient Pressure, Pa (mmHg):760
Wind Speed, u (m/s at 10 mAG): 2
Pasquill Stability: D
Downdraft (1 - considered, 0 - ignored): 0
Height of Most Influencial Building, Hbld (mAG): 20
____________________________________________________________________
THE PLUME RISE
_______________
EFFECTIVE RELEASE HEIGHT - STATIC ADJUSTMENTS
_____________________________________________
STACK WAKE DOWNDRIFT
.--------------------
If release through stake then
. If w0 <= 1.5 u, with u - the average wind speed at release vent height H, then
. dHstack = 2(1.5 - w0/u)D
If no stack or w0 > 1.5 u then
. dHstack = 0.
43
Effective Release Height, Heff_stack (mAG)
. Heff_stack = H - dHstack
CASE: no stack
. dHstack (m) = 0.
. Heff.stack (m) = 40
NEAREST BUILDING WAKE DOWNDRIFT
-------------------------------
In general: Heff_nbld = Heff_stack - dHnbld
If Heff_stack > 2.5 Hbld then
. dHnbld = 0
If Heff_stack > Hbld and Heff_stack <=2.5 Hbld then
If u >= 5 then
dHnbld = 1.5 Hbld - 0.6 Heff_stack
If u < 5 then
dHnbld = 0
If Heff_stack <= Hbld then
dHnbld = 0
CASE: Heff_stack > Hbld and Heff_stack <= 2.5 Hbld and u < 5
. dHnbld (m) = 0
. Heff.nbld = 40
. Consequent Effective Release Height (mAG): 40
EFFECTIVE RELEASE HEIGHT - PLUME RISE
_____________________________________
The Thermal Plume Rise:
If x < 3.5 x0 then
dHrise_th(x) = 1.6 (F^(1/3)) (x^(2/3))/u
If x >= 3.5 x0 then
dHrise_th(x) = dHrise_th(x0)
where
the vertical shear-adjusted wind speed at release vent is:
u = u10 (H/10)^m, if H>10, or u10 otherwise,
with u10 (m/s) - the wind speed at 10 mAG;
The transition distance from source is:
x0 = 14 F^(5/8) if F < 55 m4/s3
x0 = 34 F^(2/5) if F >= 55 m4/s3
the thermal portant flux is:
F = ((Tgas/muGas - Tair/muAir)/(Tgas/muGas)) g w0 ((D/2)^2)
with Tair, muAir - ambient air absolute temperature and molar mass, respectively,
. Tgas - gas absolute temperature at vent and molar mass, respectively.)
and the other notations - above.
The Final Thermal Plume Rise:
. If Pasquill A, B, C, D then
. dHrise_th = 1.6 F^(1/3) ((3.5 x0)^(2/3))/u
. If Pasquill E, F, G then
. dHrise_th = 5.0 (F^(1/4))/(S^(3/8)), S>0
The Stability Parameter (Squared Vaisala Frequency, N), S is: S = (g/Ta) DthetaDz
with DthetaDz - the Potential Temperature Gradient of the local atmosphere.
Note that S is effective only in stable atmospheres, of class E or F.
44
The Momentum Plume Rise
In the transition zone:
dHrise_mm = 1.89 (((w0^2) D/(u (w0 + 3u)))^(2/3)) (x^(1/3))
The Final Momentum Plume Rise:
the lowest rise from the following:
dHrise_mm = 1.5 w0 Dvent/u
dHrise_mm = 4.0 ((Fm/S)^(1/4))
dHrise_mm = 1.5 ((Fm/u)^(1/3))/(S^(1/6))
where Fm (m4/s2) is the momentum-driven portant flux:
Fm = (rhoAir/rhoGas)(w0^2)((Dvent/2)^2)
See the other notations above.
If Thermal and Momentum Drives are comparable:
dHrise = (3^(1/3))((Fm x/(((1/3+u/w0)^2)(u^2)) + F (x^2)/(0.5 (u^3)))^(1/3))
Inversion Cutoff
With this code, one holds the conservative assumption that there is no penetration
of the inversion lid, so that the effective height of the plume axis can only be
lower than,
or at most equal to, the height of the inversion lid defaulted for the respective
stability class.
CHARACTERISTIC DATA
___________________
- The vertical shear-adjusted wind speed (m/s) at release vent, u (m/s): 3.20427951
- The air density, rhoAir (kg/m3), at T = 293 K: 1.18637013
- The released gas density, rhoGas (kg/m3), at T = 363 K: 0.95759352
Thermall rise:
- The thermal portant flux, F (m4/s3): 169.467834
- The transition distance, x0 (m) from source: 264.91944
- The Stability Parameter, S (1/s2): 0(Vaisala Frequency N = 0.0)
- The Final Thermal Plume Rise, dHrise_th (mAG), for a class-D atmosphere: 262.74831
Momentum rise:
- The momentum portant flux, Fm (m4/s2): 294.220185
- The Final Momentum Plume Rise, dHrise_mm (mAG), for a class-D atmosphere:
14.4280484
Final Plume Rise, selected as the dominant among dHrise_th and dHrise_mm, above:
262.74831
- The Effective Plume Height of the Briggs' Stake Release Model: 302.74831
- The Entrainment-Corrected Plume Height (open fires):
Heffective = (HBriggs^3+(pool_Radius/entrainment_coeff)^3)^(1/3)
- pool_Radius/entrainment_coeff
CONCLUSION: Final, Effective Release Height (mAG): 292.751947
45
3.2.3.4.2. Focul deschis Scenariul reprezentativ, a cărui evaluare este solicitată de organismele de reglementare [31] (v. si [32]) este considerat căderea unei aeronave peste o structură adăpostind material radioactiv – ca bazinul de calmare a combustibilului nuclear uzat ataşat reactorilor de putere, sau altă formă de depozit, ‘uscat’ sau ‘umed’ de combustibil uzat, comun în cazul reactorilor de cercetare – însoţită de decopertarea structurii şi urmată de aprinderea carburantului.
OPEN FIRE - INPUT _________________
Change defaults if/as appropriate.
When ready, 'PROCEED' from menu.
_________________________________
Physical Constants
------------------
PI Number, pi: 3.1415926
Gravity Acceleration, g (m/s2): 9.812
Ideal Gas Constant, Ridg (J/(mol.K))): 8.314
Mechanical Equivalent of Calorie (J/cal): 4.186
Air Molar Mass (kg/mol): 0.0289
Air Specific Heat (cal/(g.K)): 0.24
Air Density (g/m3): 1290
Fire Data
----------
Fuel Mass (kg): 5300
Fuel Density (kg/m3): 950
Fuel Heat Value (J/kg): 33000000
Equivalent Fuel Pool Radius (m): 6
Equivalent Fuel Pool Linear Burn Rate (mm/min): 0.175
Fire Radiance Fraction (% energy radiated): 0.3
Entrainment Coefficient (): 0.06
Release Data
------------
Venting Height (m AG): 40
Ambient Temperature (C): 20
Ambient Pressure, Pa (mmHg):760
Wind Speed, u (m/s at 10 mAG): 2
Pasquill Stability: D
____________________________________________________________________
Fuel Volume = (Fuel Mass)/(Fuel Density)
= 5.57894737 m3
= 5578947.37 cm3
= 1473.96232 gal
Pool Area = 3.1415926 x (Fuel Pool Radius)^2
= 113.097334 m2
Pool Height = (Fuel Volume)/(Pool Area)
= 0.49328726e-1 m
= 49.3287259 mm
_________________________________________________________________________________
Duration of Fuel Fire = (Pool Height)/(Pool Linear Burn Rate)
= 281.878434 min
= 16912.706 sec
= 4.69797389 hrs
Heat Emission Rate:
Q = 3785.V.d.H.(1-f)/t
where:
Q - heat emission rate (cal/s)
t = 16912.706 - duration of fuel fire (s)
3785 - volume conversion factor (cm3/gallon)
46
V = 1473.96232 - volume of fuel (gallons) burned in time, t (s)
d = 0.95 - fuel density (g/cm3)
H = 7883.42093 - heat of combustion (cal/g)
f = 0.3 - assumed fraction of the heat of combustion that is radiated.
The Buoyant Flux:
F = g.Q/(pi.C.r.T)
where:
Q - heat emission rate (cal/s)
g - the gravity acceleration (m/s2)
C - gas specific heat (cal/(kg.K))
r - air density (kg/m3)
T - ambient temperature
One obtains:
___________
Q = 1729320.64 cal/s
= 7238936.21 J/s
t = 16912.706 sec
= 4.69797389 hrs
THE PLUME RISE
_______________
EFFECTIVE RELEASE HEIGHT - PLUME RISE
_____________________________________
The Thermal Plume Rise:
If x < 3.5 x0 then
dHrise_th(x) = 1.6 (F^(1/3)) (x^(2/3))/u
If x >= 3.5 x0 then
dHrise_th(x) = dHrise_th(x0)
where
the vertical shear-adjusted wind speed at release vent is:
u = u10 (H/10)^m, if H>10, or u10 otherwise,
with u10 (m/s) - the wind speed at 10 mAG;
The transition distance from source is:
x0 = 14 F^(5/8) if F < 55 m4/s3
x0 = 34 F^(2/5) if F >= 55 m4/s3
The Final Thermal Plume Rise:
. If Pasquill A, B, C, D then
. dHrise_th = 1.6 F^(1/3) ((3.5 x0)^(2/3))/u
. If Pasquill E, F, G then
. dHrise_th = 5.0 (F^(1/4))/(S^(3/8)), S>0
The Stability Parameter (Squared Vaisala Frequency, N), S is: S = (g/Ta) DthetaDz
with DthetaDz - the Potential Temperature Gradient of the local atmosphere.
Note that S is effective only in stable atmospheres, of class E or F.
Inversion Cutoff
With this code, one holds the conservative assumption that there is no penetration
of the inversion lid, so that the effective height of the plume axis can only be lower
than,
or at most equal to, the height of the inversion lid defaulted for the respective stability
class.
CHARACTERISTIC DATA
___________________
- The vertical shear-adjusted wind speed (m/s) at release vent, u (m/s): 3.20427951
- The air density, rhoAir (kg/m3), at T = 293 K: 1.18637013
47
- The released gas density, rhoGas (kg/m3), at T = 363 K: 0.95759352
Thermall rise:
- The thermal portant flux, F (m4/s3): 59.5407948
- The transition distance, x0 (m) from source: 174.343102
- The Stability Parameter, S (1/s2): 0(Vaisala Frequency N = 0.0)
- The Final Thermal Plume Rise, dHrise_th (mAG), for a class-D atmosphere: 140.273728
Momentum rise:
- The momentum portant flux, Fm (m4/s2): 294.220185
- The Final Momentum Plume Rise, dHrise_mm (mAG), for a class-D atmosphere: 14.4280484
Final Plume Rise, selected as the dominant among dHrise_th and dHrise_mm, above: 140.273728
- The Effective Plume Height of the Briggs' Stake Release Model: 180.273728
- The Entrainment-Corrected Plume Height (open fires):
Heffective = (HBriggs^3+(pool_Radius/entrainment_coeff)^3)^(1/3)
- pool_Radius/entrainment_coeff
CONCLUSION: Final, Effective Release Height (mAG): 89.9967394
3.2.3.4.3. Focul în spaţiu închis Scenariul reprezentativ – de asemenea in atentia organismelor de reglementare [33] este considerat un incendiu in spatiul inchis al unei structuri strategice – ca anvelopa unui reactor sau un depozit de material radioactiv – frecvent intalnit in operatiile de dezafectare, insotit de evacuarea gazelor si cenusilor rezultate (fly-ashes) prin solutiile normale de continuitate cu mediul – sisteme de ventilare, cai de acces.
FIRE IN THE HALL - INPUT
________________________
Change defaults if/as appropriate.
When ready, 'PROCEED' from menu.
_________________________________
Physical Constants
------------------
PI Number, pi: 3.1415926
Gravity Acceleration, g (m/s2): 9.812
Ideal Gas Constant, Ridg (J/(mol.K))): 8.314
Mechanical Equivalent of Calorie (J/cal): 4.186
Air Molar Mass (kg/mol): 0.0289
Air Specific Heat (cal/(g.K)): 0.24
Air Density (g/m3): 1290
Fire Data
----------
Fuel Mass (kg): 5300
Fuel Density (kg/m3): 950
Fuel Heat Value (J/kg): 33000000
Equivalent Fuel Pool Radius (m): 6
Equivalent Fuel Pool Linear Burn Rate (mm/min): 0.175
Fire Radiance Fraction (% energy radiated): 0.3
Entrainment Coefficient (): 0.6
Sugawa Model Parameter a (K.kW^(3/2).m^(-3/5)): 20
Sugawa Model Parameter k (): 1
Release Data
------------
Venting Height (m AG): 40
Venting Diameter, Dvent (m): 3.7
Ambient Temperature (C): 20
Ambient Pressure, Pa (mmHg):760
Wind Speed, u (m/s at 10 mAG): 2
Pasquill Stability: D
48
____________________________________________________________________
Fuel Volume = (Fuel Mass)/(Fuel Density)
= 5.57894737 m3
= 5578947.37 cm3
= 1473.96232 gal
Pool Area = 3.1415926 x (Fuel Pool Radius)^2
= 113.097334 m2
Pool Height = (Fuel Volume)/(Pool Area)
= 0.49328726e-1 m
= 49.3287259 mm
_________________________________________________________________________________
Duration of Fuel Fire = (Pool Height)/(Pool Linear Burn Rate)
= 281.878434 min
= 16912.706 sec
= 4.69797389 hrs
Heat Emission Rate:
Q = 3785.V.d.H.(1-f)/t
where:
Q - heat emission rate (cal/s)
t = 16912.706 - duration of fuel fire (s)
3785 - volume conversion factor (cm3/gallon)
V = 1473.96232 - volume of fuel (gallons) burned in time, t (s)
d = 0.95 - fuel density (g/cm3)
H = 7883.42093 - heat of combustion (cal/g)
f = 0.3 - assumed fraction of the heat of combustion that is radiated.
One obtains:
___________
Q = 1729320.64 cal/s
= 7238936.21 J/s
t = 16912.706 sec
= 4.69797389 hrs
THE FIRE FLOW
_____________
According to Sugawa (see menu's Help),
the fire flow temperature, Tg (C) at a height H m from the fire base
and a radial distance r (m) from the fire vertical axis is:
Tg = aSu/(N^(5/3))
where N is the following function of the fire power, Q (kW):
N =(H + r)/(Q^(2/5))
and the empirical constant aSu in the range 20-22 kW^(3/2).m^(-3/5).
With the flow temperature, Tg, and the ambient air temperature, Ta known,
the ejection velocity is:
v = kSu.(H/(H + 2.r)).((dT/Ta).g.H)^(1/2)
kSu = 1.0
g = 9.81 m/s^2.
One thus obtains:
Height Flow-Temperature Flow-Velocity
(m above fire base) (C) (m/s)
_____________________________________________________
1 7484.21914 15.8313594
2 2357.38131 12.5653583
3 1199.34576 10.9768515
4 742.528584 9.97313146
5 511.913388 9.25823512
49
6 377.770242 8.71233281
7 292.179514 8.2759691
8 233.881848 7.91567968
9 192.195101 7.61092375
10 161.242613 7.34826608
11 137.559953 7.11848071
12 118.99017 6.91498314
13 104.12961 6.73292469
14 92.0307799 6.56864103
15 82.0340961 6.4193017
16 73.6681659 6.28267913
17 66.5883561 6.15699168
18 60.5376633 6.04079418
19 55.3210601 5.93289971
20 50.7882407 5.83232266
_____________________________________________________
One retains, at the ejection mouth level:
_________________________________________
Reference Gas Temperature (C): 50.7882407
Reference Gas Velocity (m/s): 5.83232266
THE PLUME RISE
_______________
EFFECTIVE RELEASE HEIGHT - PLUME RISE
_____________________________________
The Thermal Plume Rise:
If x < 3.5 x0 then
dHrise_th(x) = 1.6 (F^(1/3)) (x^(2/3))/u
If x >= 3.5 x0 then
dHrise_th(x) = dHrise_th(x0)
where
the vertical shear-adjusted wind speed at release vent is:
u = u10 (H/10)^m, if H>10, or u10 otherwise,
with u10 (m/s) - the wind speed at 10 mAG;
The transition distance from source is:
x0 = 14 F^(5/8) if F < 55 m4/s3
x0 = 34 F^(2/5) if F >= 55 m4/s3
the thermal portant flux is:
F = ((Tgas/muGas - Tair/muAir)/(Tgas/muGas)) g w0 ((D/2)^2)
with Tair, muAir - ambient air absolute temperature and molar mass, respectively,
. Tgas - gas absolute temperature at vent and molar mass, respectively.)
and the other notations - above.
The Final Thermal Plume Rise:
. If Pasquill A, B, C, D then
. dHrise_th = 1.6 F^(1/3) ((3.5 x0)^(2/3))/u
. If Pasquill E, F, G then
. dHrise_th = 5.0 (F^(1/4))/(S^(3/8)), S>0
The Stability Parameter (Squared Vaisala Frequency, N), S is: S = (g/Ta) DthetaDz
with DthetaDz - the Potential Temperature Gradient of the local atmosphere.
Note that S is effective only in stable atmospheres, of class E or F.
Inversion Cutoff
With this code, one holds the conservative assumption that there is no penetration
of the inversion lid, so that the effective height of the plume axis can only be lower
than,
or at most equal to, the height of the inversion lid defaulted for the respective stability
class.
50
CHARACTERISTIC DATA
___________________
- The vertical shear-adjusted wind speed (m/s) at release vent, u (m/s): 3.20427951
- The air density, rhoAir (kg/m3), at T = 293 K: 1.18637013
- The released gas density, rhoGas (kg/m3), at T = 323.788241 K: 1.07356106
Thermall rise:
- The thermal portant flux, F (m4/s3): 58.5081283
- The transition distance, x0 (m) from source: 173.127237
- The Stability Parameter, S (1/s2): 0(Vaisala Frequency N = 0.0)
- The Final Thermal Plume Rise, dHrise_th (mAG), for a class-D atmosphere: 138.808892
Momentum rise:
- The momentum portant flux, Fm (m4/s2): 128.653022
- The Final Momentum Plume Rise, dHrise_mm (mAG), for a class-D atmosphere: 10.1019248
Final Plume Rise, selected as the dominant among dHrise_th and dHrise_mm, above: 138.808892
- The Effective Plume Height of the Briggs' Stake Release Model: 178.808892
- The Entrainment-Corrected Plume Height (open fires):
Heffective = (HBriggs^3+(pool_Radius/entrainment_coeff)^3)^(1/3)
- pool_Radius/entrainment_coeff
CONCLUSION: Final, Effective Release Height (mAG): 168.819317
3.2.4. Alocarea modelelor de disprsie in N-WATCHDOG In aprecierea autorilor, modelul Puff Trails prezinta o relevanta superioara, putand acomoda scari spatiale si de timp extinse – pana la zeci de ore si sute de kilometri, tinand seama de variatiile rapide ale meteorologiei pe duratele de monitorizare, tipuri de emisie diverse in profil si durata, si putand acomoda o maniera analitica naturala de a considera efectele topografiei. Modelul Gaussian Plume, ce recurge la medierea efectelor pe directia transversala fata de cea a vantului mediu pe intreaga durata de monitorizare are o acuratete acceptabila, demonstrata experimental, doar pe distante relativ scurte fata de zona de emisie. Pe de alta parte insa, modelul dispune de unele avantaje: in sens tehnic, poate acomoda cu relativa usurinta mai multe surse de emisie simultan, impreuna cu efectele topografiei in zona apropiata sursei; iar in sens legal, are meritul considerabil de fi fost adoptat de Autoritatea nucleara nationala, CNCAN, drept model oficial recomandat, printr-un document de reglementare [2]. In proiectarea N-WATCHDOG s-a tinut seama de avantajele mentionate in privinta ambelor modele, astfel incat corelarea aplicatiilor efective cu versiuni ale modelelor de baza mentionate se prezinta astfel (Tabelul 2): Tabelul 2. Modele servind aplicatiile N-WATCHDOG.
APLICATIA MODELUL Versiunea
The Far-Field Watchdog Puff Trails Basic
The Far-Field Trainer Puff Trails Basic
The Near-Field Watchdog Plume Basic
The Near-Field Trainer Plume Basic
Explosive RD* Devices Puff Trails 5-Puff column
Incendiary RD* Devices Puff Trails Dense short sequence
* RD – Radioactive Dispersion (Devices)
51
Versiunile modelelor reflecta particularitati ale termenului sursa, tinand de durata emisiilor – arbitrara sau strict conditionata de dinamica procesului (evacuare din structuri, explozie sau incendiu provocat) si configuratia initiala a norului de ejectie. Adoptarea lor raspunde faptului demonstrat in realitate – conform caruia distributia spatiala a efectelor radiologice ale unei emisii depinde atat de meteorologia de mediu cat si de mecanismele de ejectie la sursa ce pot determina, in cazuri speciale, necesitatea imperativa a considerarii efectelor topografiei zonelor expuse ('terenul complex').
3.3. Soluţii IT Principalii algoritmi preconizati pentru implementarea modelelor descrise urmaresc, in esenta:
In cazul modelului Puff Trails:
Istoria fiecarui puff dintr-o secventa temporala de emisie, determinand, la fiecare pas de timp, efectele pasajului acestuia peste teritoriul expus in virtutea meteorologiei momentului respectiv. Pornind din centrul puff-ului, se calculeaza simultan valorile 'efectului', exprimat in concentratii de activitate (kBq/m3) in fiecare nod al retelei spatiale cu celule rectangulare georeferentiate, ce acopera aria de studiu. Folosita ca mediu de stocare, reteaua cumuleaza treptat efectele in 'Concentratia de activitate integrata in timp' (Time-Integrated Concentration, TIC), masurata in kBq/m3 (sau μCi/m3) – marime de nemijlocita relevanta in calculul dozelor de radiatie (mSv), de interes in diagnoza locala si sinoptica a 'Situatiei Radiologice' (Radiological Situation). Intr-o redare indicativa, algoritmul decurge in sensul indicat in caseta C1.
In cazul modelului Gaussian Plume:
Variatia cu distanta pe directia de actiune a vantului mediu (downwind-from-source velocity = viteza de origine + 180 grade) a Concentratiei de activitate integrate in timp, TIC. Pornind de la datele astfel obtinute pe axa penei de dispersie, se calculeaza apoi valorile 'efectului', exprimat in concentratii de activitate (kBq/m3) in fiecare nod al retelei spatiale cu celule rectangulare georeferentiate, ce acopera aria de studiu, pregatindu-se astfel stocul de date pentru calculul dozelor de radiatie (mSv), de interes in diagnoza locala si sinoptica a 'Situatiei Radiologice' (Radiological Situation). Intr-o redare indicativa, algoritmul decurge in sensul indicat in caseta C2. Dupa cum rezulta din schitele de conceptie prezentate in continuare, punerea in opera a algoritmilor principali necesita o serie de rutine de calcul reflectand nevoia unor algoritmi ancilari, indispensabili. Dintre acestia se evidentiaza, ne-exhaustiv:
Algoritmul de calcul al coeficientilor de dispersie dependenti de timp - sistemul Doury; si dependenti de distanta la sursa – sistemele Karlsruhe-Julich (COSYMA), Brookhaven, Klug, StLouis, Slade, Briggs – versiunea CNCAN si Briggs – versiunea HotSpot a Lawrence Livermore Laboratories (SUA). Alegerea sistemului este, in evaluarile radiologice, rezultatul unei judecati-experte din partea utilizatorilor de coduri, ce poate afecta sensibil rezultatele finale. In contrast cu alte sisteme DSS, N-WATCHDOG ofera la interfata posibilitati de optiune corespunzatoare. Folosit in ambele modele.
52
Algoritmul numit de dezvoltatori 'Puffs Control Tower' care, prin analogie cu strategia turnurilor de control al traficului aerian, detecteaza in runtime cea mai apropiata statie meteorologica furnizoare de prognoze, aplicand in calcule datele provenind de la aceasta. Folosit de modelul Puff Trails.
Algoritmul rapid de calcul al distributiei spatiale a Concentratiei de activitate integrate in timp (Time-Integrated Concentration, TIC), construit pe o emulare in memorie a unei stive (stack), utilizat in modelul Gaussian Plume.
Algoritmii dedicati recoltarii in timp real si mod offline-browsing a datelor de prognoza meteorologica de la site-uri publice – de la o singura statie, cea mai apropiata de sursa in cazul Gaussian Plume si de la toate statiile ('turnurile de control') detectate in raport cu vectorul local al dispersiei pe traiectoria impusa de meteorologia rapi-variabila, in cazul Puff Trails.
Algoritmii de generare direct in runtime, din resursele DEM rezidente ale codului, de harti de situatie ad-hoc, acoperind dispersia si efectele sale pe intervalul de monitorare, in orice zona a Globului cu exceptia unor vecinatati nesemnificative ale Polilor.
53
C1. Schiţa de concepţie a algoritmului Puff Trails (dialect: Liberty BASIC 4.03 – limbaj cvasi-algoritmic de nivel înalt)
'The puff trail sequence loop
For p = 1 to npuffsX 'For each and every puff in the trail of npuffsX puffs...
'The assessment of the individual puff 'history' begins here...
laA = laSrc: LoA = LoSrc 'Starting from source at laSrc latitude and LoSrc longitude (decimal degrees)...
da = 0
'The puff time loop
For t = (p-1)*tau to tSpan-(p-1)*tau step tau 'Follow puff history from its relase at time = (p-1)*tau,
'over the duration of release, tSpan(s), with tau(s)- the puffs sequencing time step
dispuff = 0
age = t-(p-1)*tau 'Determine puff age(s) in the loop
if age>0 then 'as long as puff has not completely dissipated (concentration still above a pre-set boundary limit)
imet = int(t/3600) 'get time-position in the meteo forecast
if imet<1 then imet = 1
if imet>tMon then imet = tMon 'In this context,
wo$ = met$(imet)
wspd0 = val(trim$(word$(wo$,2))) 'get respective barometric wind velocity (hourly average at 10m above ground)
wdr = val(trim$(word$(wo$,3))) 'get respective wind direction, in degrees from North by East.
class = asc(trim$(word$(wo$,5)))-64 'get the pre-determined atmospheric stability category (A through F)
iRain = val(trim$(word$(wo$,6))) 'get respective precipitation rate(mm/h)
prel = prel(class) 'get vertical wind shear exponent
hInv = hInv(class) 'get inversion lid
wsp = wspd0*(hRel/10)^prel 'get wind velocity on the puff trajectory centerline
dispuff = dispuff+wsp*tau 'get puff horizontal distance to source
if dispuff<10*hRise then 'get effective puff height, hEff, knowing release height, hRel, pre-determined puff rise, and dispuff(m)
h = hRel+hRise*(dispuff/(10*hRise))^(2/3)
hEff = h
else
h = hRel+hRise
hEff = h
end if
if hEff>hInv then hEff = hInv 'cut (conservatively) puff height to the inversion lid level
'Compute dispersion coefficient sigmay (horizontal) and sigmaz (vertical)
'as functions of either puff age, or distance to source
gosub [sigmas]
'Compute puff radius considering ground, and inversion lid reflection
lnarg = tau*(1+lRGrd)*(Expo((-1)*hEff*hEff/(2*sigmaz*sigmaz))+
+lRInv*(Expo((-1)*(0-hEff-2*hInv)*(0-hEff-2*hInv)/(2*sigmaz*sigmaz))
+ Expo((-1)*(0+hEff-2*hInv)*(0+hEff-2*hInv)/(2*sigmaz*sigmaz))
54
+ Expo((-1)*(0-hEff+2*hInv)*(0-hEff+2*hInv)/(2*sigmaz*sigmaz))
+ Expo((-1)*(0+hEff+2*hInv)*(0+hEff+2*hInv)/(2*sigmaz*sigmaz)))/(kpi*sigmay*sigmay*sigmaz*Clim))
if lnarg> = 1 then
rPuff = sigmay*sqr(2*log(lnarg))
else
rPuff = 0
end if
'Compute Puff's depletion
if rPuff>0 then 'if puffs exists...
'The Dry Depletion
vDry0 = vDry(1) 'aerosols, Cs...
nT = 10
w = age/nT
Idry = 0
for ka = 1 to nT
x1 = (ka-1)*w: tageBIS = x1:gosub [sigmasBIS]:sigma1 = sigmazBIS: y1 = Expo((-1)*hEff*hEff/(2*sigma1*sigma1))/sigma1
x2 = ka*w: tageBIS = x2:gosub [sigmasBIS]:sigma2 = sigmazBIS: y2 = Expo((-1)*hEff*hEff/(2*sigma2*sigma2))/sigma2
Idry = Idry+w*(y1+y2)/2
next
Fdry0 = Expo((-1)*vDry0*Idry)
'The Radioactive Decay Depletion
HalflifeDCs = 1.01e4 'd
lambdaD0 = 0.69315/HalflifeDCs
Fdecay0 = Expo((-1)*tageD*lambdaD0)
'The Wet Depletion
tRain = 3600 's
aRain0 = aRain(1) '1/s
bRain0 = bRain(1)
Lrain0 = aRain0*(iRain^bRain0)
Fwet0 = Expo((-1)*Lrain0*tRain) 's, rain time
vWet0 = sqr(pi/2)*Lrain0*sigmaz*Expo(hEff*hEff/(2*sigmaz*sigmaz))
'Get total (dry + wet) ground deposition velocity
vTot = vDry0+vWet0
'Compute the effective Dilution Factor (s/m3)
DF = DF0*Fdecay0*Fwet0*Fdry0
'Compute Grid Knot Dilution Factors and Doses,
jc = int((LoA-NWLo)/pasLo)
ic = int((NWla-laA)/pasla)
'Compute puff contribution to the Time-Integrated Concentration (TIC)
'and apply Dosimetric Model(s) */ to the effect of determining the Radiological Situation-relevant doses
'over the entire grid
gosub [grid]
'The assessment of the individual puff 'history' ends here...
'Prepare the next step in the puff's time loop:
55
'Vectorize the Puff, by pushing it one-step-forward in space (wind velocity and direction known); then loop its history in time, till puff vanishes...
da = 1
laLoB$ = TrailC$(wsp*tau,laA,LoA,wdr+180)
laB = val(trim$(word$(laLoB$,1,","))) 'la
LoB = val(trim$(word$(laLoB$,2,","))) 'Lo
laA = laB: LoA = LoB
else
exit for
end if
end if
next
if da = 0 then exit for
scan
'Go to the next puff in the sequence and get its history and effects, similarly...
next
____________________________________________________________________________________________________________________________________________________________________
[grid] 'This routine belongs organically to the Dispersion Engine and is therefore included here...
for ii=ic to 0 step -1 'Scanning the knot lines from the puff knot line, to the North
la=laB+abs(ii-ic)*pasla
for jj=jc to 0 step -1 'Scanning the knots from the puff center knot, to the West
Lo=LoB-abs(jj-jc)*pasLo
gosub [Range] '[Range] here determines the distance of the targeted grid knot to the puff center knot
if dis<=rPuff then
j=jj
i=ii
if j>0 and j<jub and i>0 and i<iub then
d(j,i)=d(j,i)+DF*Expo((-1)*dis*dis/(2*sigmay*sigmay)) 'The exponential here adjusts the puff center value to the knot position value...
else
exit for
end if
else
exit for
end if
next
for jj=jc+1 to jub step 1 'Scanning the knots from the puff center knot, to the East
Lo=LoB+abs(jj-jc)*pasLo
gosub [Range]
if dis<=rPuff then
j=jj
i=ii
if j>0 and j<jub and i>0 and i<iub then
d(j,i)=d(j,i)+DF*Expo((-1)*dis*dis/(2*sigmay*sigmay))
else
exit for
end if
else
exit for
56
end if
next
next
for ii=ic to iub step 1 'Scanning the knot lines from the puff knot line, to the North
la=laB+abs(ii-ic)*pasla
for jj=jc to 0 step -1 'Scanning the knots from the puff center knot, to the West
Lo=LoB-abs(jj-jc)*pasLo
gosub [Range]
if dis<=rPuff then
j=jj
i=ii
if j>0 and j<jub and i>0 and i<iub then
d(j,i)=d(j,i)+DF*Expo((-1)*dis*dis/(2*sigmay*sigmay))
else
exit for
end if
else
exit for
end if
next
for jj=jc+1 to jub step 1 'Scanning the knots from the puff center knot, to the East
Lo=LoB+abs(jj-jc)*pasLo
gosub [Range]
if dis<=rPuff then
j=jj
i=ii
if j>0 and j<jub and i>0 and i<iub then
d(j,i)=d(j,i)+DF*Expo((-1)*dis*dis/(2*sigmay*sigmay))
else
exit for
end if
else
exit for
end if
next
next
return
* Rutinele Modelului Dosimetric vor fi redata in contextul Sectiunii 3, dedicate subiectului.
57
C2. Schiţa de concepţie a algoritmului Gaussian Plume (dialect: Liberty BASIC 4.03 – limbaj cvasi-algoritmic de nivel înalt)
'The release sources loop
'Note that model 'Plume' has the ability to cover several release sources in one run-stroke.
'Source loop starts here...
for kSrc = 1 to nSrc 'sum over physical sources
bar$ = oldbar$+". Computing release #"+str$(kSrc)+ " of "+str$(nSrc)+"..."
calldll #user32,"SetWindowTextA", WndP as long, bar$ as ptr, res as long
'Source kSrc Cartesian coordinates, in a WGS84-wise projection
xc = int(mX*(LoSrc(kSrc)-NWLo)/LonWidth)
yc = int(mY*(NWla-laSrc(kSrc))/LatWidth)
x = mX*(LoSrc(kSrc)-NWLo)/LonWidth
y = mY*(NWla-laSrc(kSrc))/LatWidth
gosub [Elevation] 'get source elevation (mASL) from resident DEMs
zSrc = z
jc = int(xc/pasx)
ic = int(yc/pasy)
'Get the event meteo from pre-processed forecast
wspd10 = wspd(kSrc)
if wspd10<wspd10crt then
wspd10 = wspd10crt
end if
wdir = wdir(kSrc)
tRelh = tRel(kSrc)/60 'min/(min/h) = h
hRel = hRel(kSrc)
deltah = hRise(kSrc)
class = class(kSrc)
if wspd10<wspd10crt then
class = 1
end if
iRain = prec(kSrc)
tRain = tprec(kSrc)
multF = multF(kSrc)
'gosub [sigma1] 'dispersion system found outsite this code sequence
if sys$ = "D" then 'get dispersion coefficients and associated data (wind shear, inversion)
gosub [Doury1]
pw = pw(class)
hInv = hInv(class)
else
gosub [sigma1]
end if
58
'Determine wind velocity at plume's stabilized centerline height
select case
case hRel> = 10
wspd = wspd10*(hRel/zref)^pH
case zref>10
wspd = wspd10*(10/zref)^pH
case else
wspd = wspd10
end select
if wspd<0.5 then wspd = 0.5 'to prevent stack height wind speed < 0.5 m/s
wspdh = wspd*3600 '(m/s).s/h = m/h
if lAssessment = 1 then 'Assumes full assessment based on a specified source term – one per every source, as appropriate
'Load nuclide mix data in memory
mixfile$ = DefaultDir$+"\public\mix\"+fMix$(kSrc)
#win.e " RELEASE #"+str$(kSrc)
#win.e " All activities to be multiplied by "+str$(multF)
open mixfile$ for input as #1
while eof(#1) = 0
line input #1,wo$
#win.e " "+wo$
wend
close #1
#win.e " "
#win.e "!contents? halfText$" '<<<
kCi = 1
open mixfile$ for input as #1
nmixk = 0
while eof(#1) = 0
line input #1,wo$
if instr(wo$,"(Ci)")>0 then
kCi = 3.7e7
end if
if instr(wo$,"(Bq)")>0 then
kCi = 0.001
end if
if instr(wo$,"|sur")>0 then
nmixk = nmixk+1
end if
wend
close #1
redim nukes$(nmixk+1)
open mixfile$ for input as #1
j = 0
while eof(#1) = 0
line input #1,wo$
if instr(wo$,"|sur")>0 then
j = j+1
nukes$(j) = wo$
end if
59
wend
close #1
nukes$(0) = str$(nmixk)
end if
'Fill the data grid by a stack-wise algorithm
gosub [FillByStack]
next kSrc
'Source loop ends here...
_____________________________________________________________________________________________________________________________________________________________________
[FillByStack]
cursor hourglass
'Creates a pseudostack in memory, as an array mimicking the data grid – dim-ed outside this listing
redim d(iub+1,jub+1) 'the test matrix; once a cell is filled it is further avoided
'Ancillary – gets coords to place a legend in the situation map without obscuring essential data – ignore now...
wleg = 140 '120
hleg = 160 '80
if wdir> = 0 and wdir<90 then
xleg = mX-wleg-3
yleg = 0
end if
if wdir> = 90 and wdir< = 180 then
xleg = mX-wleg-3
yleg = mY-hleg-3
end if
if wdir< = 0 and wdir>-90 then
xleg = 0
yleg = 0
end if
if wdir< = -90 and wdir> = -180 then
xleg = 0
yleg = mY-hleg-3
end if
'Stack search-and-fill starts here...
frak = 0.05
maxtop = 0
do
j = jc-int(frak*jub*sin(wdir*arg)+.5)-2
i = ic+int(frak*iub*cos(wdir*arg)+.5)-2
if i<iub and i>0 and j<jub and j>0 and i<>ic and j<>jc then
ix = x(j) 'int(j*pasx)
iy = y(i) 'int(i*pasy)
gosub [Target]
if test>0 then
60
exit do
end if
end if
frak = frak+0.05
loop while (test = 0 and frak<1)
'In stable atmospheres (classes E and F),
'and/or for circular areas closing on the source at small radii,
'and/or for very high release points (high stacks above a few tens of metres),
'and/or for certain varieties of dispersion systems (especially Doury),
'it MAY happen that the stack search will find no grid point to be accounted for,
'owing to dilutions/doses below the input limits defining the plume boundary
'(note that, mathematically, model sees plumes extended to infinity(!..)
'The following takes care of such cases.'
if frak> = 1 then
s$ = "Notice"+qb$
s$ = s$+"NO PLUME FOOTPRINT FOR THIS MAP COVERAGE,"+qb$
s$ = s$+"CONSIDERING CURRENT METEOROLOGY AND DISPERSION SYSTEM '"+sys$+"'."+qb$
s$ = s$+"PROGRAM WILL NOW CLOSE."+qb$
s$ = s$+"TRY A LARGER MAP RADIUS and/or DISPERSION SYSTEM 'C'."
notice s$
goto [exit]
end if
stack$ = ""
top = 0
try = 0
[exec]
do
j = j-1: gosub [push]
i = i-1: gosub [push]
j = j+1: gosub [push]
j = j+1: gosub [push]
i = i+1: gosub [push]
i = i+1: gosub [push]
j = j-1: gosub [push]
j = j-1: gosub [push]
if da = 0 then gosub [pull]
bar$ = oldbar$+". Release #"+str$(kSrc)+", Grid stack counter: "+string$(int(top/10),"|")
calldll #user32,"SetWindowTextA", WndP as long, bar$ as ptr, res as long
scan
if top>maxtop then
maxtop = top
end if
loop while top>0 '!!!
cursor normal
stack$ = ""
return
61
'Stack works on 'push' and 'pull'...
[push]
if i<0 then
i = 0
gosub [pull]
return
end if
if i>iub then
i = iub
gosub [pull]
return
end if
if j<0 then
j = 0
gosub [pull]
return
end if
if j>jub then
j = jub
gosub [pull]
return
end if
'So far the process went an assumed X-axis, irrespective of the actual wind direction.
'Now is the time where the entire grid knots exposed will be properly rotated by the angle bringing data to their true grid positions!
if wspd10>wspd10crt then
jw = jc-int(jc*sin(wdir*arg)+.5)
iw = ic+int(ic*cos(wdir*arg)+.5)
else 'Ooops! Plume models do not tolerate zero-wind velocities.
wwdir = 360*rnd(1) ' Therefore, for very low winds – i.e. below a (hard-coded) given limit, wspd10crt,
jw = jc-int(jc*sin(wwdir*arg)+.5) ' the wind directions are taken at random within a 360 degree span, at each computation step...
iw = ic+int(ic*cos(wwdir*arg)+.5)
end if
pdot = (jw-jc)*(j-jc)+(iw-ic)*(i-ic)
if pdot<0 then return
if top<0 then return
da = 0
ix = x(j)
iy = y(i)
if j<0 then return 'keep process only within the grid!..
if j>jub then return
if i<0 then return
if i>iub then return
gosub [Target] 'see below!..
'The Dosimetric Model is embedded here
'Will be explained in Section 3.
return
62
[pull]
w$ = mid$(stack$,len(stack$)-10,10)
stack$ = left$(stack$,len(stack$)-10)
top = top-10
j = val(trim$(word$(w$,1))): i = val(trim$(word$(w$,2)))return
'The Stack algorithm ends here...
_____________________________________________________________________________________________________________________________________________________________________
[Target] 'This routine organically belongs to the Dispersion engine, and is thereby rendered here...
la1 = NWla-LatWidth*yc/mY
Lo1 = NWLo+LonWidth*xc/mX
la2 = NWla-LatWidth*iy/mY
Lo2 = NWLo+LonWidth*ix/mX
gosub [distances]
if ok = 0 then
test = 0
return
end if
downwind = distance
if sys$ = "D" then
gosub [Doury]
else
gosub [sigma2]
end if
if warn$ = "none" then
s$ = "DEFECTIVE INPUT FOR DISPERSION SYSTEM."+qb$
s$ = s$+"PROGRAM WILL RESET ITSELF."
notice s$
goto [begin]
end if
x = mX*(Lo2-NWLo)/LonWidth
y = mY*(NWla-la2)/LatWidth
gosub [Elevation]
if downwind<10*deltah then
h = hRel+deltah*(downwind/(10*deltah))^(2/3)+zSrc-z 'ASL!
else
h = hRel+deltah+zSrc-z '+z*(z> = zSrc)
end if
if h<1 then h = 1
hEff = h
if hEff<1 then hEff = 1
f0 = 1/(2*pi*sigy*sigz) '1/m2
fy = Expo((-1)*crosswind*crosswind/(2*sigy*sigy)) '1
fz = Expo((-1)*hEff*hEff/(2*sigz*sigz)) '1
fzgrd = lref*fz
63
fzinv = linv*(Expo((-1)*(0-hEff-2*hInv)*(0-hEff-2*hInv)/(2*sigz*sigz))
+ Expo((-1)*(0+hEff-2*hInv)*(0+hEff-2*hInv)/(2*sigz*sigz))
+ Expo((-1)*(0-hEff+2*hInv)*(0-hEff+2*hInv)/(2*sigz*sigz)) + Expo((-1)*(0+hEff+2*hInv)*(0+hEff+2*hInv)/(2*sigz*sigz)))
DF0 = f0*fy*(fz+fzgrd+fzinv) '(1/m2)*1*1 = 1/m2 Dilution Factor
'(kBq/s)*s/m3 = kBq/m3 Concentration
test = (DF0> = DFcontour) 'observing pre-set plume boundary...
return
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4. Evaluarea radiologică a unei emisii atmosferice radioactive
'Radiological assessment has matured significantly over the past three decades. It has become the foundation of many regulations and legal cases and has provided a means for decision makers to take action on important issues such as cleanup of
contaminated sites and control of emissions to the environment from nuclear facilities. Additionally,radiological assessment has increasingly become a fundamental element in communicating information to stakeholders about exposure to radioactive materials
in the environment.' (Till, 2008)
4.1. Definiţie
In contextul N-WATCHDOG, termenul 'Evaluare radiologica' se doreste o trimitere la initiatorii conceptului Radiological Assessment – cercetarea si industria nucleara euro-atlantica. Intr-o referinta de baza a proiectului [24]
Radiological assessment is defined as the process of estimating dose and risk to humans from radioactive materials in the environment.
In integralitatea sa conceptul acopera o problematica de impresionanta si
multidisciplinara intindere. Caseta ce urmeaza retine, pentru ilustrare, doar titlurile majore din tabla de materii a referintei citate.
1 The Radiological Assessment Process 2 Radionuclide Source Terms 3 Atmospheric Transport of Radionuclides 4 Surface Water Transport of Radionuclides 5 Transport of Radionuclides in Groundwater 6 Terrestrial Food Chain Pathways: Concepts and Models 7 Aquatic Food Chain Pathways 8 Site Conceptual Exposure Models 9 Internal Dosimetry 10 External Dosimetry 11 Estimating and Applying Uncertainty in Assessment Models 12 The Risks from Exposure to Ionizing Radiation 13 The Role of Epidemiology in Estimating Radiation Risk: Basic Methods and Applications 14 Model Validation 15 Regulations for Radionuclides in the Environment
Sursa: Till J.E, Grogan H.A. (2008). Radiological Risk Assessment and Environmntal Analysis. Oxford University Press [24]
Autorii Raportului si-au luat libertatea de a evidentia in text tematicile ce au alimentat,
in mod selectiv, baza de cunostinte si date a proiectului asumat. In particular, subiectul sectiunii curente a Raportului se reclama de la temele 9 – Internal Dosimetry si 10-External Dosimetry ale listei, aduse la specificitatea N-WATCHDOG. 4.2. Mărimile fizice de bază ale dozimetriei radiaţiilor ionizante Analiza dozimetrica a expunerii la radiatii ionizante uzeaza de urmatoarele concepte si marimi fizice de baza (Tabelul 3).
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Tabelul 3. Marimi fizice de baza in Dozimetria radiatiilor ionizante
Conceptul Specia fizică Unităţi SI Unităţi tolerate Ţinta Definiţie
Expunere* Sarcina electrica C (Coulomb) R (Roentgen) Aerul The quantity of X or γ-radiation such that the associated corpuscular emission per 0.001293 gram of air produces, in air, ions carrying 1 electrostatic unit of quantity of electricity of
either sign.**
Doza absorbita Energie Gy (Gray) rad Materie Marimea dozimetrica fundamentala definita ca energia medie cedata de radiatia ionizanta unitatii de masa iradiata.***
Doza echivalenta Energie scalata cu factori de impact la materia vie
S (Sievert) rem Materie vie, Om Doza absorbita, in tesutul sau organul T, ponderata pentru calitatea radiatiei R (capacitatea de a afecta tinta).***
Doza angajata Varietate de Doza Echivalenta
S (Sievert) rem Materie vie, Om Integrala pe o durata de timp (uzual 50 ani) a debitului dozei echivalente intr-un organ sau tesut al unui organism uman, ce va fi primita in urma unei incorporari de substante radioactive.***
Doza efectiva angajata
Varietate de Doza Echivalenta
S (Sievert) rem Materie vie, Om Suma ponderata a dozelor echivalente angajate de organele si tesuturile unui organism uman in urma unei incorporari de substante radioactive; fiecare din dozele echivalente angajate de un organ sau tesut este ponderata cu factorul de pondere al organului sau tesutului respectiv.***
Doza efectiva Varietate de Doza Echivalenta
S (Sievert) rem Materie vie, Om Suma ponderata a dozelor echivalente provenite din expunerea externa si interna, efectuata pe o serie selectiva de organe si tesuturi esentiale ale corpului, stabilite de reglementarile nucleare.***
* Unitate traditionala de apreciere a expunerii la radiatie, inlocuita in practica actuala de ‘doza absorbita’. Asimilarea ei in setul de unitati folosite califica o analiza drept ‘radio-dozimetrica’. N-WATCHDOG mentine Expunerea in libraria de date, dar nu o utilizeaza efectiv in evaluarea radiologica.
In contextul sistemului, termenul ‘Expunere’ este utilizat numai in sensul sau ‘literal’ (involving the ordinary or usual meaning of a word – Merriam Webster online). * * ICRP (1950). *** CNCAN (2000). NORME FUNDAMENTALE DE SECURITATE RADIOLOGICA, NSR-01. [1]
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Definitiile unitatilor de masura ale dozelor sunt larg disponibile in literatura, inclusiv in documentele tehnice si de reglementare din bibliografia Raportului. Relativ specioase, se apreciaza ca tabelarea lor in breviarul de fata nu prezinta o reala valoare informativa. In locul definitiilor, Figura 23 ofera o imagine graitoare a relatiei dintre doze, masurate in unitatile enumerate si cele mai semnificative efecte ale acestora.
Fig.23. Unitati de masura, din perspectiva nivelelor de doza [RTM-96].
1Sv = 100 rem; 1 rem = 1000 mrem
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4.3. Dozimetria accidentelor nucleare Alegerea tipurilor de doza in evaluarea radiologica a emisiilor de radioactivitate in mediu se face in functie de relevanta dozei in diagnoza evenimentului si in determinarea eventualei necesitati de contramasuri. Termenul de apreciere in asemenea judecati il constituie accidentul nuclear sever, caracterizat prin efecte la scara regionala, de obicei trasfrontaliere; si semnificative pe perioade indelungate, de ordinul anilor sau deceniilor. 4.3.1. Fazele tipice ale unei urgenţe radiologice severe Analiza este condusa pe o scara de timp, comportand o periodizare. Se disting astfel:
(a) O ‘Faza timpurie’ (Early Phase) a evenimentului; si (b) O ‘Faza tarzie’, sau ulterioara (Late Phase).
‘Faza tarzie’ comporta o ambiguitate, in functie de acceptiunea data de diferiti autori. Sursele U.S., de obicei urmate in aplicare, numesc Faza tarzie ‘Faza intermediara’ (Intermediate Phase), atribuindu-i insa un profil ce se suprapune aproape indiscriminabil peste ceea ce aceleasi surse identifica drept ‘Faza de ingestie’ (Ingestion Phase). Pentru edificare, Tabelul 4 reproduce definitiile date de manualul de raspuns la urgente RTM-6 [28].
Tabelul 4. Fazele tipice ale unui accident nuclear, cf. RTM-96.
Faza timpurie (Early Phase)
The early phase of an accident extends from the identification of a release threat until the release (or threat of the release) has ended and any areas of major contamination have been identified. The early phase normally includes up to 4 days (100 h) of exposure to deposition*. To project the potential consequences from a radiological accident the following steps must be performed: (1) estimate the amount of activity released, (2) estimate the downwind dose from this material, and (3) determine the impact of this dose in terms of health effects and PAGs**.
Faza intermediară (Intermediate
Phase)
The intermediate phase is the period beginning after the incident source and releases have been brought under control and reliable environmental measurements are available for use as a basis for decisions on additional protective actions and extending until these protective actions are terminated. This phase may overlap the early and late phases and may last from weeks to many months. For the purpose of dose projection, the intermediate phase is assumed to last for 1 year. Two radiation exposure pathways are of primary concern during the intermediate phase: (1) exposure to deposited material (direct exposure and inhalation of resuspended material); and (2) ingestion.
Faza ingestiei (Ingestion
Phase), sau Faza tarzie
(Late Phase)
(An) Ingestion Pathway Protective Action Assessment. This (…) is used only to determine if protective actions are warranted to protect the public from ingestion of food, milk, and water that have been contaminated as a result of an accident. (To this effect,) determine the area where (…) ingestion PAGs may be exceeded based on either (1) gross gamma measurements (for a reactor accident before the isotopic contamination mixture is known) or (2) ground surface deposition.
* Metodologia europeana scaleaza Early Phase la 7 zile (168 ore) – aspect asigurat de N-WATCHDOG. ** PAG – Protective Action Guide: nivele de doza, sau nivele derivate ale concentratiilor in mediu,
furaje sau alimente ce impun recomandarea de contramasuri.
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4.3.2. Doze caractersitice fazelor Monitorizarea evolutiei unei situatii radiologice consecutive unei urgente apleleaza la proiectii de doza, pe un set de doze considerat reprezentativ, redat in Tabelul 5.
Tabelul 5. Doze reprezentative in monitorizarea evolutiei unei situatii radiologice
Faza timpurie (Early Phase)
External Doses ____________ AIR IMMERSION EXTERNAL DOSE, Ha DEPOSITION 4-DAY EXTERNAL DOSE,NON-ARID LAND, Hg4 DEPOSITION 4-DAY EXTERNAL DOSE,ARID LAND, Hg2 DEPOSITION 7-DAY EXTERNAL DOSE,GENERIC, Hg7 Inhalation Doses _____________ EARLY PHASE INHALATION COMMITTED EFFECTIVE DOSE (50 year), CEDE50 EARLY PHASE INHALATION ACUTE BONE DOSE, Dbone EARLY PHASE INHALATION ACUTE LUNG DOSE, Dlung EARLY PHASE INHALATION COMMITTED DOSE TO THYROID, CDEThy Total Doses _________ TOTAL ACUTE BONE DOSE (TABD) TOTAL ACUTE LUNG DOSE (TALD) TOTAL ACUTE THYROID DOSE (TTHD) TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE)
Faza intermediară (Intermediate
Phase)
DEPOSITION TOTAL EFFECTIVE DOSE EQUIVALENT, in 1st year, NON-ARID LAND DEPOSITION TOTAL EFFECTIVE DOSE EQUIVALENT, in 1st year, ARID LAND DEPOSITION COMMITTED EFFECTIVE DOSE EQUIVALENT (50 year) EFFECTIVE EQUIVALENT DOSE FROM INHALATION OF RESUSPENDED MATERIAL EQUIVALENT DOSE TO SKIN, FROM DEPOSITION
Faza ingestiei (Ingestion Phase)
INFANT INGESTION DOSE* CHILD INGESTION DOSE** ADULT INGESTION DOSE
* Doza de referinta in regimul de consum al laptelui si apei ** Doza de referinta in consumul de produse vegetale proaspete
Varietatile de doza cu efect direct in recomandarea de contramasuri si identificarea de efecte sanitare posibile sunt urmatoarele – cu notatiile din Tabelul 5: TABD = Ha + Hg2 + Dbone, TALD = Ha + Hg2 + Dlung, TTHD = Ha + Hg2 + CDEThy, TEDE = Ha + Hg7 + CEDE50, unde Hg2 si Hg7 sunt dozele externe din depunere (Groundshine), pe doua zile si, respectiv, 7 zile. Individualizarea, in aceasta lista, a TEDE – Doza Echivalenta Efectiva Totala se datoreaza importantei centrale a acestei marimi, atat in documentele normative de reglementare cat si in evaluarile N-WATCHDOG.
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4.3.3. Dozele de referinţă în sistemul N-WATCHDOG Proiectul N-WATCHDOG a fost propus si aprobat in conceptia dezvoltarii unui instrument 'de alertare timpurie si asistare a deciziilor'. Din aceasta perspectiva, produsul va adresa exclusiv Faza timpurie (Early Phase) a unui accident, sau alta urgenta radiologica ce rezulta intr-o distributie spatiala semnificativa a efectelor. Dozele caracteristice fazei timpurii se coreleaza in moduri specifice cu
(i) recomandarile de contramasuri; si (ii) identificarea efectelor sanitare posibile, deterministe si stochastice.
Tabelul 6 prezinta aceasta relatie, urmand ca precizarea nivelelor de doza ce fac recomandabile contramasurile, sau fac efectele sanitare probabile sa faca obiectul sectiunii 5, dedicata reglementarilor.
Tabelul 6. Relatii de principiu Doza-Efect, in Early Phase, cf. [27, 28] TEDE: Total Effective Dose Equivalent; TABD: Total Acute Bone Dose; TALD: Total Acute Lung Dose; TTHD: Total Thyroid Dose Equivalent
EFECTE TEDE TABD TALD TTHD
CONTRAMĂSURI
Adapostire (Sheltering)
Evacuare (Evacuation)
Administrare de iod stabil (Iodine Prophylaxis)
EFECTE SANITARE SEMNIFICATIVE
D*: Hipotiroidism, in decurs de unul sau mai multi ani; sau S*: Risc de cancer tiroidian fatal: 8.0e-8
D*: Voma, din prima zi de expunere
D*: Deces, in decurs de 1-2 luni; sau S*: Risc de cancer fatal: 0.1
D*: Deces, in 1-12 luni; sau S*: Risc de cancer pulmonar: 0.05
D*: Efect determinist. S*: Efect sochastic
4.3.4. Calculul dozelor Calculul efectiv al dozelor relevante in modelele adoptate de N-WATCHDOG porneste de la Factorul de Dilutie efectiv, DF(x,y,z) (sectiunea 3.2.3.3, ecuatia DF3), evaluat la nivelul solului (z = 0), unde se presupun plasate tintele prioritare ale expunerii - oamenii. Marimile ce mijlocesc obtinerea dozelor din DF sunt Factorii de Conversie la Doze (Dose Conversion Factors, DCF), ce constiuie de fapt doze pe unitatea de DF. DCF nu depind de modelul de dispersie, ci (a) de nuclid; si (b) de tipul de doza: externa, sau de inhalare (v. Tabelul 5), dozele totale rezultand in consecinta, prin simpla sumare. In implementarile IT, retetele de calcul se prezinta astfel:
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4.3.4.1. Cheia de calcul al dozelor în modelul Gaussian Puff Trails
Initialize: Ha = 0, CEDE = 0, Thy =0, Bone = 0, Lung = 0.
For every nuclide in the source term mix,
Given
DF ‘ Effective Dilution Factor (s/m3), computed under the Dispersion Algorithm
vTot = vDry + vWet ‘ Total Deposition Velocity
Compute:
vTotH = vTot*3600 '(m/s).(s/h) = m/h
DFh = DF/3600 '(s/m3)/(s/h) = h/m3
Ha = Ha+activity*DFh*dcfHa 'kBq.(h/m3).(mSv/h)/(kBq/m3) = mSv, External, Air immersion
CEDE = CEDE+activity*DFh*dcfCEDE 'kBq.(h/m3).(mSv/h)/(kBq/m3) = mSv, Committed Effective, 50 year
Thy = Thy+activity*DFh*dcfThy 'kBq.(h/m3).(mSv/h)/(kBq/m3) = mSv, Committed to Thyroid
Bone = Bone+activity*DFh*dcfBone 'kBq.(h/m3).(mSv/h)/(kBq/m3) = mSv, Acute Bone
Lung = Lung+activity*DFh*dcfLung 'kBq.(h/m3).(mSv/h)/(kBq/m3) = mSv, Acute Lung
Hg1 = Hg1+activity*vTotH*DFh*dcfHg*(1-Expo((-1)*lambdaH*2))/lambdaH 'kBq.(m/h).(h/m3).(mSv/h)/(kBq/m2)/(1/h) = mSv, Ground external, 2 days
Hg2 = Hg2+activity*vTotH*DFh*dcfHg*(1-Expo((-1)*lambdaH*7))/lambdaH 'kBq.(m/h).(h/m3).(mSv/h)/(kBq/m2)/(1/h) = mSv, Ground External, 7 days
next jk
TABD = Ha+Hg1+Bone 'mSv
TALD = Ha+Hg1+Lung 'mSv
TTHD = Ha+Hg1+Thy 'mSv
TEDE = Ha+Hg2+CEDE 'mSv
4.3.4.2. Cheia de calcul al dozelor în modelul Gaussian Plume
Initialize all arrays holding grid data in knots (j,i); j = 0,…,J columns (East to West), I = 0,…,I rows (North to South)
For every nuclide in the source term mix,
Given
DFeff ‘ Effective Dilution Factor (s/m3), computed under the Dispersion Algorithm
Wspd ‘ Average wind velocity (m/s)
vTot = vDry + vWet ‘ Total Deposition Velocity
DF=DF.wspd ‘(s/m3).(m/s) = 1/m2
d(j,i)=DF
dTot(j,i)=dTot(j,i)+d(j,i)
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activity=kCi*multF*val(trim$(word$(wk$,2))) 'kBq
actrate=activity/tRelh 'kBq/h
dcfCEDE=val(trim$(word$(wk$,4))) '(mSv/h)/(kBq/m3)
dcfBone=val(trim$(word$(wk$,5))) '(mSv/h)/(kBq/m3)
dcfLung=val(trim$(word$(wk$,6))) '(mSv/h)/(kBq/m3)
dcfThy=val(trim$(word$(wk$,7))) '(mSv/h)/(kBq/m3)
dcfHa=val(trim$(word$(wk$,9))) '(mSv/h)/(kBq/m3)
dcfHg=val(trim$(word$(wk$,8))) '(mSv/h)/(kBq/m2)
dTotHa(j,i)=dTotHa(j,i)+actrate*d(j,i)*dcfHa*tExp/wspdh '(kBq/h).(1/m2).(mSv/h)/(kBq/m3).h/(m/h) = mSv
dTotCEDE(j,i)=dTotCEDE(j,i)+actrate*d(j,i)*dcfCEDE*tExp/wspdh '(kBq/h).(1/m2).(mSv/h)/(kBq/m3).h/(m/h) = mSv
dTotThy(j,i)=dTotThy(j,i)+actrate*d(j,i)*dcfThy*tExp/wspdh '(kBq/h).(1/m2).(mSv/h)/(kBq/m3).h/(m/h) = mSv
dTotBone(j,i)=dTotBone(j,i)+actrate*d(j,i)*dcfBone*tExp/wspdh '(kBq/h).(1/m2).(mSv/h)/(kBq/m3).h/(m/h) = mSv
dTotLung(j,i)=dTotLung(j,i)+actrate*d(j,i)*dcfLung*tExp/wspdh '(kBq/h).(1/m2).(mSv/h)/(kBq/m3).h/(m/h) = mSv
dTotHg1(j,i)=dTotHg1(j,i)+activity*vTotalH*d(j,i)*dcfHg*(1-Expo((-1)*lambdaH*2))/(lambdaH*wspdh)
'kBq.(m/h).(1/m2).(mSv/h)/(kBq/m2)/((1/h).(m/h)) = mSv
dTotHg2(j,i)=dTotHg2(j,i)+activity*vTotalH*d(j,i)*dcfHg*(1-Expo((-1)*lambdaH*7))/(lambdaH*wspdh)
'kBq.(m/h).(1/m2).(mSv/h)/(kBq/m2)/((1/h).(m/h)) = mSv
dTotTABD(j,i)=dTotHa(j,i)+dTotHg1(j,i)+dTotBone(j,i) 'mSv
dTotTALD(j,i)=dTotHa(j,i)+dTotHg1(j,i)+dTotLung(j,i) 'mSv
dTotTTHD(j,i)=dTotHa(j,i)+dTotHg1(j,i)+dTotThy(j,i) 'mSv
dTotTEDE(j,i)=dTotHa(j,i)+dTotHg2(j,i)+dTotCEDE(j,i) 'mSv
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4.3.5. Nivele de doză reglementate, în N-WATCHDOG In pofida tentativelor, reluate in cateva reprize la interval de decenii (e.g. dupa accidentele nucleare de la Three Mile Island, SUA, 1979 si Cernobyl, URSS/Ucraina, 1986), de unificare a nivelelor de doza reglementate, ce se cer observate iar, in caz de urgente, utilizate in aplicarea uniforma de contramasuri si/sau aprecierea pragurilor de atentie privind posibilitatea de manifestare a efectelor sanitare, acestea continua sa varieze de la tara la tara sau, in cel mai bun caz, de regiune la regiune. Faptul reflecta diferente in perceptia riscului, cultura de securitate si disponibilitatea de suportare a costurilor, in general ridicate, de aplicare a masurilor preventive si corective ce devin obligatorii odata ce nivelele de observare/interventie au fost legiferate. Principalii arbitri in acest exercitiu sunt IAEA – International Atomic Energy Agency, ICRP – International Commission on Radiological Protection si autoritatile nationale de reglementare nucleara – in cazul Romaniei CNCAN - Comisia Nationala pentru Controlul Activitatilor Nucleare. Proiect cu declarata vocatie internationala in virtutea caracterului potential-transfrontalier al urgentelor nucleare, N-WATCHDOG a adoptat o strategie de raportare a evaluarii radiologice (Radiological Assessment) care sa tina seama de diferentele mentionate, indicand de fiecare data pozitia proiectiilor de doza realizate atat fata de normele nationale cat si, selectiv, fata de diverse nivele de reglementare ale altor parti (Tabelul 7).
Tabelul 7. Nivele reglementate de observare si interventie in N-WATCHDOG
REGULATORY ASSUMPTIONS: Observation and Intervention Dose Levels __________________________________________________________________________ TOTAL EFFECTIVE DOSE EQUIVALENT, TEDE _______________________________________ Doses unnoticeable or inconsequencial, TEDE less than 0.01 mSv 1-yr TEDE Constraint for unplanned irradiation to population, Romania: 0.01 mSv 1-yr TEDE Limit to population, all sources, Romania: 1 mSv Sheltering TEDE PAG, Romania: 3 mSv Sheltering TEDE PAG, IAEA: 10 mSv Evacuation TEDE PAG, Romania: 30 mSv Evacuation TEDE PAG, IAEA: 50 mSv Hot Intervention Zone TEDE PAG, Romania: 100 mSv COMMITTED DOSE EQUIVALENT TO THYROID ________________________________________ Sheltering THYD PAG, Romania: 30 mSv Iodine prophylaxis THYD PAG, IAEA: 100 mSv Evacuation and Iodine prophylaxis THYD PAG, Romania: 300 mSv Hypothyroidism in 1 or more yrs./8.0e-3 risk of fatal thy.cancer THYD PAG IAEA: 5000 mSv TOTAL ACUTE BONE DOSE ________________________ Vomiting in 1 day TABD PAG, IAEA: 500 mSv Death in 1-2 mnt./1.0e-1 risk of fatal cancer TABD PAG, IAEA: 1000 mSv TOTAL ACUTE LUNG DOSE ________________________ Death in 2-12 mnt./5.0e-2 risk of lung cancer TALD PAG, IAEA: 6000 mSv
Se observa ca, in general, gradul de severitate creste in ordinea listarii, ceea ce
favorizeaza introducerea unei scari de apreciere a gradului de expunere implicat in analiza de vulnerabilitate – o dimensiune specifica N-WATCHDOG.
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5. Analiza de vulnerabilitate 'Pe Ahile nu l-a ucis Riscul conditiei sale de soldat
– de care era permanent constient; ci Vulnerabilitatea ce i-a fost imprimata la nastere
– pe care n-a stiut-o sau a ignorat-o. (Anonim).'
5.1. Definiţie In sens colocvial, o entitate se considera vulnerabila daca este
(a) ‘easily hurt or harmed physically, mentally, or emotionally’; (b) ‘open to attack, harm, or damage’ (Merriam-Webster Online).
Dupa un deceniu si jumatate de la primele tentative de asimilare a conceptului in Teoria Riscului, determinate imperativ de evenimentul ‘9/11’ (atacul asupra World Trade Center, New York, eveniment ce a revelat realitatea inimaginabila in perceptia curenta: ca tara considerata prin excelenta in-vulnerabila nu este, de fapt, astfel) o sursa de autoritate ca Departamentul Securitatii Interne al Statelor Unite (U.S. Department of Homeland Security, DHS) – creatie a vremurilor ce au urmat - precizeaza, in Lexiconul sau:
Vulnerability: characteristic of design, location, security posture, operation, or any combination thereof, that renders an entity, asset, system, network or geographic area susceptible to disruption, destruction or exploitation’. (DHS Risk Lexicon 2010 Edition, U.S. Dept. Of Homeland Security).
Doua observatii se impun atentiei. Astflel, (i) comparatia intre definitia colocviala si cea tehnica nu poate ignora remarcabila lor convergenta, in sensul global; si (ii) faptul ca intre evenimentul initiator din septembrie 2001 si formalizarea in sens tehnic a conceptului de vulnerabilitate s-a interpus un deceniu de dezbateri si controverse ce nu s-au stins complet nici in prezent, reflectate intr-o consistenta literatura (v. Bibliografia). 5.1.1.Risk şi Vulnerabilitate Ezitarile academice - si politologice - in acceptarea termenului vulnerabilitate ca instrument de analiza de situatie au o dubla explicatie: prima tine de principiul tiranic al parcimoniei, ce marcheaza disciplina intelectuala inca din zorii filosofiei, cu formulari autoritare incepand mai ales din secolul XIII, conform caruia entitățile, inclusiv conceptele explicative nu trebuie să fie multiplicate dincolo de necesar: Pluralitas non est ponenda sine necessitate (Duns Scotus - Ordinatio); a doua tine de relativa dificultate a caracterizarii cantitative a vulnerabilitatii. Argumentul ‘economiei de concepte’ – ce revine, in cazul de fata, la o judecata de felul ‘daca ne-am straduit, inca din anii ’80 sa operationalizam conceptul de Risc, dandu-i expresii cantitative ce s-au dovedit utile, de ce este nevoie de inca un concept, ca Vulnerabilitatea?’ – s-a erodat rapid in lumina imposibilitatii de a explica exclusiv in termenii Riscului esecurile dramatice in administrarea raspunsului la unele dezastre inregistrate in prima decada a actualului secol, ca amenintarea terorismului si urmarile acesteia, evenimentul Katrina – New Orleans (2005), consecintele eruptiei vulcanului Eyjafjallajökull din Islanda (2010), sau ale Marelui Cutremur Japonez, insotit de catastrofa nucleara de la Fukushima (2011). In cazul ce ne preocupa, sistemul N-WATCHDOG asimileaza raportul dintre Risc si Vulnerabilitate in termenii ilustrati in Figura 24.
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Fig. 24. Riscul si Vulnerabilitatea in intelegerea N-WATCHDOG: Riscul este apanajul sursei, Vulnerabilitatea priveste tinta.
5.1.2. Evaluarea cantitativă a vulnerabilităţii Chestiunea evaluarii cantitative a Vulnerabilitatii (Quantitative Vulnerability Assessment, QVA,) ocupa un domeniu de investigatie inca emergent, bogat in initiative si alternative mai degraba complementare decat reciproc-exclusive (v.e.g. [34]). Practic, problema revine la definirea unui Indicator de Vulnerabilitate, sau a unui set cat mai compact si articulat de indicatori care sa integreze intr-un mod justificabil acei parametri obiectivi ai ‘entitatii’ vizate - ‘design, location, security posture, operation, or any combination thereof,’
(v.definitia DHS) ce fac entitatea ‘susceptible to disruption, destruction or exploitation’. Faptul ca problema este, in principiu, solubila este confirmat de secondarea definitiei citate a Vulnerabilitatii de o definitie a ‘Gradului de vulnerabilitate’ (Vulnerability degree):
Vulnerability degree: ‘qualitative or quantitative expression of the level to which an entity, asset, system, network or geographic is susceptible to harm when it experiences a hazard’ (DHS Risk Lexicon 2010 Edition, U.S. Dept. Of Homeland Security).
In conceperea unei solutii sustenabile teoretic si implementabile IT, de evaluare cantitativa a Vulnerabilitatii comunitatilor expuse la efecte ale emisiilor atmosferice radioactive, urmarind relatiile indicate in Figura 24 autorii N-WATCHDOG au fost confruntati cu urmatoarele necesitati:
Identificarea unui set minimal-suficient de indicatori primari obiectivi de caracterizare a Vulnerabilitatii Statice – variabila lenta a modelului - a comunitatilor din zona de influenta a obiectivelor nucleare;
Definirea unei metrici abstracte adimensionale, exprimata prin indicatori agregati, capabile sa concilieze natura diferita a indicatorilor primari - exprimati, inerent, in unitati diferite (persoane, unitati monetare, grade de calificare etc.);
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Normarea metricii la o scara a Vulnerabilitatii Statice convenabila raportarilor si analizei comparative a comunitatilor din aceasta perspectiva;
Definirea unei metrici aplicate (a) Expunerii comunitatilor; si (b) Impactului potential al emisiilor radioactive, menita a servi conceptul de Vulnerabilitate Dinamica – variabila rapida a modelului.
Crearea unui Indicator sinoptic bidimensional, sub-intins in cele doua dimensiuni de, respectiv, vulnerabilitatile statica si dinamica, in fapt – a unei Matrici de Vulnerabilitate, corelabila cu hartile geografice ale distributiei teritoriale a Vulnerabilitatii.
Aceste aspecte sunt explicate in continuare. 5.1.2.1. Indicatorii Vulnerabilităţii Statice
In sensul N-WATCHDOG, Vulnerabilitatea Statica (VS) a unei comunitati in fata situatiilor de urgenta exprima susceptibilitatea comunitatii de a suferi destructurari si pagube atunci cand este supusa unei amenintari. Masura VS se considera data de doi factori:
1. valorile potential amenintate (assets): populatia (oamenii); economia; functionalitatile sociale; importanta strategica – in sensul valorii/semnificatiei comunitatii in relatia cu alte comunitati si contextul national/international; si
2. capacitatea de raspuns la amenintari (mitigation capability), de absorbtie a efectelor si de refacere (resilience).
5.1.2.1.1. Indicatorii primari
De prima evidenta s-au considerat urmatorii Indicatori primari (Tabelul 8).
Tabelul 8. Indicatori primari ai Vulnerabilitatii Statice a unei comunitati.
Toate valorile numerice sunt arbitrare si pur ilustrative.
O B J E C T: AnyPlace
LOCATION (longitude, latitude): 28.054511, 44.32155
____________________________________________________________
Community strength (0.01 to 1.0): 0.68249917
Note: this indicator qualifies your integrative, subjective appraisal of the relative importance
of the target as far as population and business, strategic, cultural etc. assets/activities.
The 0.1 default would roughly place a target mid-scale, from the standpoint described.
___________________________________________________________________________________________________
TARGET INDICATORS FOR EXPOSURE/IMPACT ASSESSMENT
_________________________________________________
Adjust defaults as appropriate.
Note that while YrMin, YrMax, XrMin and XrMax (see explanations below) are model-setting parameters reflective
of your data, best guess, or beliefs, Yr in the last column SIMULATE actual values
and should therefore be as close to the community realities as possible.
When ready, 'Process current case', from menu.
The header:
YrMin - Lower bound assumed for an indicator
YrMax - Upper bound assumed for an indicator
XrMin - Lower bound assumed for an index (normalized indicator)
XrMax - Upper bound assumed for an index (normalized indicator)
Yr - Actual value assumed for an indicator, r, for the targeted community
Xr - Actual value obtained for an index (normalized indicator), for the targeted community
___________________________________________________________________________________________________________
Indicator Unit YrMin YrMax XrMin XrMax Yr
. 1 2 3 4 5 6 7
___________________________________________________________________________________________________________
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TARGET EXPOSURE/IMPACT INDICATORS (tangibles)
_____________________________________________
Demography
----------
P1|Population.total persons 300 900000 0.2 0.8 173769.747
P2|Children.(<18.yrs) persons 100 100000 0.1 0.9 62321.1787
P3|Aged.(>65) persons 25 25000 0.1 0.9 11704.7628
P4|Disabled persons 10 10000 0.1 0.9 2961.4222
P5|Other.socially-assisted persons 50 5000 0.3 0.7 159.936032
Economy
-------
E1|Fixed.assets Euro/1 50000 10000000 0.1 0.9 6680318.84
E2|Real.estate Euro/1 50000 50000000 0.3 0.7 33763939.4
E3|Business.turnover Euro/1 10000 1000000 0.4 0.6 179300.67
E4|Insurance.commited Euro/1 1000 5000000 0.2 0.8 3378948.31
E5|Workforce.employed persons 50 10000 0.4 0.6 2627.44106
Social
------
C1|Heath.care.units Euro/2 10000 1000000 0.1 0.9 464763.927
C2|Daycare.units.(<7.yrs) Euro/2 5000 50000 0.1 0.9 23487.0287
C3|Educational.facilities Euro/2 5000 100000 0.1 0.9 62383.2044
C4|Cultural.facilities.or.symbols Euro/2 5000 25000 0.3 0.7 8789.04307
C5|Sport.facilities Euro/2 5000 25000 0.4 0.6 13558.0392
Strategic
---------
S1|Major.power.infrastructure Euro/2 50000000 500000000 0.1 0.9 1.7609e8
S2|Major.gas.infrastructure Euro/2 5000000 10000000 0.1 0.9 6020685.22
S3|Major.river.or.sea.harbor Euro/2 10000000 500000000 0.1 0.9 3.048267e8
S4|Major.railroad.infrastructure Euro/2 5000000 50000000 0.2 0.8 8282974.13
S5|Major.road.infrastructure Euro/2 2500000 65000000 0.3 0.7 36993411.6
S6|Major.ITC.infrastructure Euro/2 50000 500000 0.1 0.9 278353.647
S7|Major.logistic.depots Euro/2 1000000 10000000 0.2 0.8 3056986.42
S8|Major.commercial.hub Euro/2 50000 500000 0.4 0.6 72181.1964
S9|Major.waste.management.facilities Euro/2 1000000 10000000 0.4 0.6 2501476.5
S10|Defense.interoperative Euro/2 1000000 25000000 0.1 0.9 3191656.42
S11|Defense.operative Euro/2 500000 5000000 0.2 0.8 806505.232
S12|Defense.logistics Euro/2 5000000 50000000 0.2 0.8 29989659.1
MITIGATION CAPABILITY INDICATORS (intangibles)/3
______________________________________________
M1|Infrastructure.physical.protection/4 grade 1 9 0.1 0.9 3.89290072
M2|Natural.disasters.preparedness/5 grade 1 9 0.1 0.9 4.28347568
M3|Hazard.watch.infrastructure/6 grade 2 8 0.2 0.8 4.85995317
M4|Hazard.watch.performance/7 grade 1 9 0.3 0.7 6.01376498
M5|Operational.risk.control/8 grade 3 7 0.4 0.6 4.69345946
M6|Housekeeping.quality/9 grade 4 6 0.4 0.6 4.61255773
M7|Safety.culture.of.the.administration/10 grade 3 7 0.3 0.7 5.3037871
M8|Safety.culture.of.population/11 grade 4 6 0.4 0.6 4.70013415
M9|Social.climate.monitoring/12 grade 4 6 0.4 0.6 4.97077128
___________________________________________________________________________________________________________
. 1/ Market value
. 2/ Cleanup and recovery costs
. 3/ Audit-established grades, 0 to 10
. 4/ Including power, transportation, IT, communications, fixed assets
. 5/ Including earthquakes, floods, landslide, wildfires, with emphasis on adequate budgeting,
. manning and training of emergency preparedness personnel (fire fighters, ambulance service etc.)
. 6/ Level of integration with local, regional and/or national early alert systems,
. including manning and training
. 7/ Based on incident management history on local record
. 8/ Regarding process error, human error, fraud, sabotage, system failure
. 9/ Including drinking/domestic/sewage water systems, waste disposal, roads condition,
. cleaning and lighting etc.
.10/ Level of safety regulations knowledge, mastering and implementation
.11/ Compliance with safety/emergency rules of conduct, sound crisis behavior, rigors acceptance
.12/ Pressure groups and social unrest management.
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De notat ca aspectul etic al aprecierilor de valoare in privinta factorului uman – prin unitati monetare reflecta o cutuma acceptata in analiza de risc, intemeiata in esenta pe evaluari ale costurilor indirecte, de remediere – prim-ajutor, spitalizare, recuperare fizica, pierderi economice prin indisponibilitate pentru munca etc.
5.1.2.1.2. Indicatorii agregaţi de profil
Folosirea ca atare a indicatorilor primari intr-o analiza coerenta, cu finalitati sinoptice este virtual-imposibila. Solutia adoptata [v. 35-39 si bibliografia], inspirata din expertiza elvetiana in materie [40] consta in crearea unor Indicatori agregati, definiti pentru fiecare din cele cinci profile identificate in Tabelul 8. Operatia decurge conform algoritmului redat in Tabelul 9:
Tabelul 9. Algoritmul de constructie a Indicatorilor agregati de profil
INDICATOR ANALYSIS AND AGGREGATION
__________________________________
On the input above one may now compute, for every exposed community (target),
the following aggregated Indexes:
- The Exposure/Impact Index - population: Ip = {Sum(j = 1 to 5).Xp(Yp(j))^e}^(1/e)
- The Exposure/Impact Index - economy: Ie = {Sum(j = 1 to 5).Xe(Ye(j))^e}^(1/e)
- The Exposure/Impact Index - social: Ic = {Sum(j = 1 to 5).Xc(Yc(j))^e}^(1/e)
- The Exposure/Impact Index - strategic: Is = {Sum(j = 1 to 12).Xs(Ys(j))^e}^(1/e)
as well as
- The Mitigation Capability Index: Im = {Sum(j = 1 to 9).X(Yt(j))^e}^(1/e)
where
nP, nE, nC, nS, nM are the respective number of indicators in the categories above;
Xr(Yr(j))are normalized scores of the indicators in the respective categories, r,
obtained by a linear mapping of the assigned absolute scores Yr(j) in columns 3 and 4 on the table,
on the reference intervals bounded by the user-adjustable values XrMin(j), XrMax(j)in columns 5 and 6,
according to the equation:
Xr(Y(j)) = Ar.lg(Yr(j))+Br,
with r referring to p-population; e-economy; c-social; s-strategic; and m-mitigation capability,
respectively.
The constants Ar and Br are derived from the couple of equations of type:
Ar.lg(YrMin) + Br = XrMin
Ar.lg(YrMax) + Br = XrMmax
for every indicator variety r, having as solutions:
Ar = (XrMax - XrMin)/(lg(YrMax) - lg(YrMin))
Br = (XrMax.lg(YrMin) - XrMin.lg(YrMax))/(lg(YrMin) - lg(YrMax)).
Quantity e is a sensitive metric exponent, determined in such a manner that the minima and maxima of the
Exposure/Impact Indexes (not the 'indicators') be close to 10 times the minima and maxima XrMin and Xrmax,
respectively, of the normalized indicator scores - and that, irrespective of the values YrMin and YrMax,
and the nature (units) of the assumed bounds of the 'raw' indicators Yr themselves.
The 'magic' value of e satisfying the convenient condition above was obtained, by trial and error, to be
e = 0.52 and is hard-coded into the program.
In spirit, daca nu si riguros in metoda, algoritmul indicat a fost calificat drept 'fuzzy'
(vag).
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5.1.2.1.3. Indicatorul sintetic al Vulnerabilităţii Statice
Marimi cu dimensionalitate hibrida - expresii ale unei metrici pseudo-euclidiene sui generis pe spatiul indicatorilor primari obiectivi ('bruti'), indicatorii agregati de profil permit construirea unui Indicator sintetic al Vulnerabilitatii Statice. Solutia ne-fiind unica, N-WATCHDOG adopta ceea ce constituie, probabil, cea mai simpla forma (Tabelul 10):
Tabelul 10. Indicatorul Vulnerabilitatii Statice a unei comunitati, in N-WATCHDOG
(valori rezultate din date primare arbitrare, ilustrative)
THE AGGREGATED INDEXES
_______________________
POPULATION: Ip = 3.04198417
ECONOMY: Ie = 2.94831032
SOCIAL: Ic = 2.74619287
STRATEGIC: Is = 2.23942544
MITIGATION CAPABILITY: Im = 2.59481137
The model computes the OVERALL STATIC VULNERABILITY INDEX, Vstatic, as:
Vstatic = (Ip + Ie + Ic + Is) - Im
One obtains:
STATIC VULNERABILITY: 8.38110144
Assess the situation knowing that:
- The highest Static Vulnerability possible is 10.6511887;
- The lowest Static Vulnerability possible 2.41235968.
In aceasta acceptiune, Vulnerabilitatea Statica a unei comunitati creste atunci cand valoarea indicatorilor agregati de profil creste; si scade atunci cand valoarea capcitatii de raspuns la amenintari creste, dand marimii o evidenta valoare intuitiva.
5.1.2.2. Indicatorii Vulnerabilităţii Dinamice
In sensul N-WATCHDOG, Vulnerabilitatea Dinamica (VD) a unei comunitati in fata
situatiilor de urgenta exprima marimea amenintarii ce confrunta comunitatea in virtutea a doi
factori:
i) Pozitia geografica a comunitatii in raport cu dispersia atmosferica a emisiei virtuale de referinta, exprimata in esenta prin distanta fata de traiectoria maselor de aer contaminate; si
ii) Severitatea conditiilor meteorologice pe perioada de prognoza considerata, exprimata in esenta prin clasa de stabilitate atmosferica, asociata cu viteza vantului, nebulozitatea, inaltimea stratului de inversie termica si regimul precipitatiilor.
Dupa cum s-a explicat in sectiunile anterioare, contributia termenului sursa al emisiei in evaluarea Vulnerabilitatii Dinamice, desi dezirabila, ramane optionala: VD se poate evalua in doua ipoteze de lucru:
1) prin Expunere, masurata prin distributia teritoriala a Factorului de Dilutie, DF(s/m3) - v. sectiunea 2; si/sau
2) prin Impactul dozimetric asteptat – v. sectiunea 3 a Raportului. In contrast cu Vulnerabilitate Statica, ce a necesitat construirea, relativ elaborata, a unui indicator unic pe o metrica 'fuzzy', abstracta, indicatorii VD – expunere sau impact - se plaseaza cu usurinta pe scari de valori numerice imediat inteligibile. Tabelul 11 rezuma retetele respective de calcul:
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Tabelul 11. Retetele de calcul al indicatorilor Vulnerabilitatii Dinamice
A. EXPUNEREA
E(x,y,0) = E0 - log10[DF(x,y,0)],
E0 = (-1)log10(DFmin), DFmin – minimm de referinta al Factorului de Dilutie, DF(s/m3).
Valoare recomandabila: 1.0e-13, acoperitoare pentru
termenii sursa asteptati intr-o urgenta radiologica severa.
DF(x,y,0)- Factorul de Dilutie (s/m3) la nivelul solului, in punctul de harta (x,y).
Scara naturala a Expunerii, rezultata din definitie: 0 la 13 grade.
B. IMPACTUL VIRTUAL, I(x,y,0), pe scara sa naturala:
I(x,y,0) Diagnoza de situatie asteptata:
praguri reglementate depasite; contramsuri recomandate; efecte sanitare posibile
______________________________________________________________________________________________
TOTAL EFFECTIVE DOSE EQUIVALENT
_______________________________
1 1-yr TEDE Constraint for unplanned irradiation to population, Romania: 0.01 mSv
2 1-yr TEDE Limit to population, all sources, Romania: 1 mSv
3 Sheltering TEDE PAG, Romania: 3 mSv
4 Sheltering TEDE PAG, IAEA: 10 mSv
5 Evacuation TEDE PAG, Romania: 30 mSv
6 Evacuation TEDE PAG, IAEA: 50 mSv
7* Hot Intervention Zone TEDE PAG, Romania: 100 mSv
COMMITTED DOSE EQUIVALENT TO THYROID
____________________________________
8 Sheltering THYD PAG, Romania: 30 mSv
9 Iodine prophylaxis THYD PAG, IAEA: 100 mSv
10 Evacuation and Iodine prophylaxis THYD PAG, Romania: 300 mSv
11 Hypothyroidism in 1 or more yrs./8.0e-3 risk of fatal thy.cancer THYD PAG IAEA: 5000 mSv
TOTAL ACUTE BONE DOSE
________________________
12 Vomiting in 1 day TABD PAG, IAEA: 500 mSv
13 Death in 1-2 mnt./1.0e-1 risk of fatal cancer TABD PAG, IAEA: 1000 mSv
TOTAL ACUTE LUNG DOSE
________________________
14 Death in 2-12 month/5.0e-2 risk of lung cancer TALD PAG, IAEA: 6000 mSv
* Utila in orientarea lucratorilor de interventie (salvare, decontaminare);
numai indirect relevanta ca indicator de vulnerabilitate al comunitatii.
5.1.2.3. Matricea de vulnerabilitate
5.1.2.3.1. Metoda
Analiza descrisa ofera, pentru fiecare comunitate din zona de influenta a unui obiectiv nuclear doi parametri de apreciere a vulnerabilitatii: (1) Vulnerabilitatea Statica – variabila lenta a modelului, VS; si (2) Vulnerabilitatea Dinamica – variabila rapida. Solutia naturala de utilizare a acestora consta in construirea unui produs cartezian discret, in fapt a unei matrici, sau 'harti', sub-intinse de cele doua dimensiuni, VS in abscisa si VD in ordonata.
Operatia necesita o minima prelucrare suplimentara – re-scalarea VS si VD pe acelasi interval-standard de apreciere, convenabil fiind intervalul 0 – 100. Judecata este rezumata in Tabelul 12.
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Tabelul 12. Re-scalarea indicatorilor vulnerabilitatii, pentru construirea Matricii de Vulnerabilitate.
1. Mapping Static Vulnerability on a Lvs scale, 0 to Lvs:
VSmap = Lvs*(VS-VSmin)/(VSmax-VSmin), (1)
where
VS is the 'raw' Static Vulnerability as assessed,
VSmin, VSmax are the lowest and highest values of VS, respectively.
2. Mapping Dynamic Vulnerability on a Lvd scale, 0 to Lvd:
VDmap = Lvd*(E/13 + Imax/14)/2, (2)
where
E is the community Exposure evaluated as E = 13 + log(DF)/log(10),
with DF(s/m3) – the Dilution Factor,
Imax is the index, in Table 11, of the highest impact level expected
at the community location, following a virtual emission event (0 to 14).
Number 13, appearing in the E definition and also as a denominator of
the
Exposure term in Eq.(2) indicates the maximum Exposure attainable;
Denominator 14 of the Impact term in Eq.(2) indicates the maximum
Impact attainable;
Note the following properties, consolidating the meaning of Eq.(2:
- If Imax = 0, then VDmap is given by only the term Lvd*E/13;
- If E = 0, one would also automatically have Imax = 0, for one cannot
contemplate an 'Impact' if there is no 'Exposure' – meaning that
the community is simply falling off the area accounted for
by the model;
- If E = 13 and Imax = 14, then VDmap = 100; i.e. the simultaneous
attainment of the all-possible Exposure and Impact levels would
result in the highst-possible Dynamic Vulnerability, for the
respective community.
For all intent and purposes, N-WATCHDOG will assume Lvs = Lvd.
Completand informatia data de hartile geografice de caz (v. Figura 26) si fisierele-text Input/Output ce raporteaza sistematic toate operatiile sesiunilor de lucru, Matricea de Vulnerabilitate (Figura 25) va constitui un sinoptic imediat-inteligibil al situatiei curente din zona de influenta a obiectivului nuclear monitorizat. Solutia aleasa permite compararea vizuala a vulnerabilitatii comunitatilor aflate sub efectul maselor de aer ce survoleaza sursa virtuala de emisii atmosferice radioactive.
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Fig. 25. Descendenta analitica a indicatorilor vulnerabilitatii statice si dinamice ai comunitatilor si Matricea Vulnerabilitatii. Bazinele de acceptabilitate, pentru valorile 0.1 si, respectiv, 0.3 ale parametrului de frontiera dintre bazine.
Verde – vulnerabilitate scazuta (acceptabila); Galben – vulnerabilitate moderata (tolerabila); Rosu – vulnerabilitate mare (inacceptabila).
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Fig. 26. Trei expresii ale hartilor geografice sinoptice de situatie, corespunzatoare Matricii de Vulnerabilitate a cazului redat in Figura 25. Imagini de 'storyboard', din faza de proiectare a codurilor si testare a fezabilitatii solutiilor.
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Valorificarea Matricii de Vulnerabilitate ca instrument de evaluare comparata se face:
a) prin constatarea pozitiei relative a diverselor comunitati in sistemul de axe VS/VD; si b) prin introducerea, la discretia judecatii utilizatorului, a unui argument de
acceptabilitate a situatiei comunitatilor. 5.1.2.3.2. Argumentul de acceptabilitate Contextul problemei a fost fixat in analiza traditionala a Riscului, unde o 'Matrice a Riscului', sub-intinsa in abscisa de o metrica a Consecintelor, iar in ordonata de metrica naturala a Probabilitatilor (0-1) ofera imaginea pozitionarii relative a diferitelor evenimente cauzatoare de probleme. Alternativ, la un nivel de sofisticare superior, in ordonata se plaseaza valorile CDF(x) – Cumulative Distribution Function, ce exprima probabilitatea y = P(x) ca o consecinta sa prezinte o valoare mai mica decat x; sau valorile CCDF – Complementary Cumulative Distribution Function, ce exprima probabilitatea y' = P'(x) ca o consecinta sa prezinte o valoare mai mare decat x. Pe campul bidimensional fixat de cantitatile descrise se obisnuieste ca analistul sa fixeze trei bazine de interes. Adoptate sub diferite nume, ce pot include si popularele DEFCON 1, 2, 3 din strategia defensiva transatlantica, bazinele de interes exprima grade de risc ce necesita grade ale strategiilor de raspuns preventiv si/sau corectiv, planificate. Prin simpla translatie de sensuri, in campul bidimensional al Matricii de vulnerabilitate se pot fixa cu folos trei bazine de interes:
(1) Vulnerabilitate scazuta, sau acceptabila; (2) Vulnerabilitate moderata, sau tolerabila; si (3) Vulnerabilitate mare, sau inacceptabila.
Sarcina consecutiva este ca judecata experta sa stabileasca un criteriu sustenabil de definire a frontierelor dintre bazine. Solutia aleasa de autorii N-WATCHDOG, inspirata din Fizica proceselor termodinamice izoterme este ca frontierele sa fie trasate prin curbele F(VS,VD) in planul celor doua variabile, pentru care produsul VS × VD este constant, la valori alese de utilizator in intervalul 0-1. Asfel, de exemplu,
o Daca vulnerabilitatea unei comunitati se apreciaza ca scazuta / acceptabila pana la o fractiune de 0.1 din valoarea maxima posibila de 100 × 100 a ariei 'hartii' (matricii) de vulnerabilitate, atunci ecuatia frontierei dintre zonele de vulnerabilitate 'acceptabila' si 'moderata' este
VS × VD = 0.1,
toate punctele, inclusiv comunitatile, dintre originea axelor si curba apartinand bazinului de vulnerabilitate acceptabila.
o Analog, daca vulnerabilitatea se considera mare / inacceptabila peste o fractiune de 0.3 din aria hartii, atunci ecuatia frontierei dintre zonele de vulnerabilitate 'tolerabila' si 'inacceptabila' este
VS × VD = 0.3,
iar bazinele de vulnerabilitate inacceptabila si tolerabila se contureaza in consecinta. Factorul din membrul al doilea al ecuatiilor s-a numit 'parametru de frontiera' (Figura 25) si se va seta la interfata de catre utilizator. Rationamentul ce a condus la alegerea de frontiere hiperbolice intre bazine este astfel explicat, la interfata-utilizator a codului:
84
The rationale behind the solution rests on the observation that lower Static Vulnerabilities – in the sense of the definition adopted - would associate higher mitigative capabilities, thus warranting higher potential radiological impacts to be entrusted for management; whereas higher Static Vulnerabilities would indicate a community less prepared to face crises, so that only lower impacts should be assumed manageable.
Pe scurt, celor mai bine pregatiti sa infrunte crizele li se vor fixa exigente mai inalte, iar celor mai putin pregatiti – exigente mai modeste. Principiul, calificat uneori drept cinic, iar alteori doar pragmatic este, de asemenea, cutumiar in managementul urgentelor – de orice natura. Analiza poate fi elaborata in continuare, de exemplu prin conturarea si calcularea, in planul 'hartii' de vulnerabilitate, a ariei de circumscriere a comunitatilor expuse (convex hull) si crearea, pe acesta baza, a unui indicator global, numeric, de vulnerabilitate indusa de obiectivul nuclear pe fereastra de prognoza curenta etc. In spiritul 'minimei complexitati necesare' pe care proiectul si-a propus sa o cultive, versiunea propusa a Demonstratorului de concept N-WATCHDOG se abtine de la asemenea dezvoltari, ce pot mai degraba ingreuna asimilarea produsului de catre utilizatori.
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6. Datele în N-WATCHDOG: biblioteci şi gestiune
'Data are of high quality if, "they are fit for their intended uses in operations, decision making and planning." (J. M. Juran).
Alternatively, data are deemed of high quality if they correctly represent the real-world construct to which they refer...'
(Wikipedia, 2014) Modelele N-WATCHDOG necesita trei categorii de date: (1) date radiologice; (2) date meteorologice; si (3) date geografice – fapt reflectat si in sectiunile precedente ale Raportului. Natura subiectului adresat – asistarea experta a managementului urgentelor nucleare - confera termenului ‘date’ un sens mai larg fata de cel uzual, de ‘numere’ pur si simplu. Deoarece numerele cerute de modele au adesea in subtext concepte cu un anumit grad de complexitate, a caror buna intelegere este indispensabila in a le da un sens in aplicatii, bibliotecile (libraries) ce le structureaza in formate adecvate utilizarii de catre coduri pot fi mai degraba calificate drept ‘biblioteci de date si cunostinte asociate’. 6.1. Relaţiile bibliotecilor de date cu modulele funcţionale Sistemul de date al N-WATCHDOG serveste modulele functionale ale sistemului pe ambele dimensiuni ale interfetei de comunicare cu utilizatorul: input si output. O schema a relatiilor este indicata in Figura 27.
Fig. 27. Relatia intre bibliotecile de date si modulele functionale ale N-WATCHDOG.
Pentru orientare, Tabelul 13 detaliaza aceste relatii indicand si adresele, din Anexa, ale tabelelor numerice respective.
86
Tabelul 13. Datele N-WATCHDOG - Misiunea
Specia Misiunea
Datele
radiologice
Modulul Source Term
- Input pentru algoritmul ‘4Factor Formula’: calculul
activitatilor
amestecului de nuclizi efectiv emis in atmosfera
- Input pentru Selectia arborilor interactivi de eveniment
relevanti in cazul de studiu
----------------------------------------------------------
Anexa A.1.1: 21-28; 37-42
Anexa A.1.2
Anexa A.1.3
Anexa A.1.4
Anexa A.1.5
Modulul Dispersie
- Input pentru calculul fractiilor de depunere/saracire, ale
norului radioactiv
--------------------------------------------------------
Anexa A.1.1: 1-4; 49-51
Anexa A.2
Modulul Dozimetrie
- Input pentru calculul dozelor
- Input pentru evaluarea oportunitatii contramasurilor
- Input pentru evaluarea eventualitatii efectelor sanitare
----------------------------------------------------------
Anexa A.1.1: 1-15
Anexa A.1.2
Anexa A.1.3
Anexa A.1.4
Anexa A.1.5
Modulul Vulnerabilitate
- Input pentru calculul gradului de Expunere
- Input pentru calculul gradului de Impact
- Input pentru calculul Vulnerabilitatii Dinamice
Modulul Comunicare
- Output catre Arhiva de termeni sursa
- Output catre Arhiva de caz desktop
- Output catre Serverul N-WATCHDOG
Datele
Meteorologice
Modulul Source Term
- Input pentru Algoritmele ‘Plume Rise’: calculul inaltimii
Stabilizate a norului radioactiv
Modulul Dispersie
- Input pentru calulul traiectoriilor de advectie
- Input pentru inferarea stabilitatii atmosferice
- Input pentru calculul coeficientilor de dispersie
Modulul Comunicare
- Output catre Arhiva de prognoze meteorologice
- Output catre Arhiva de caz desktop
- Output catre Serverul N-WATCHDOG
Datele GIS Modulul Source Term
- Input pentru masina web/desktop de localizare interactiva a sursei
Modulul Dispersie
- Input pentru crearea in mod runtime a hartilor desktop de caz
(ad-hoc maps)
- Input pentru selectia dinamica (case-specific) a comunitatilor
efectiv expuse, din zona de influenta a obiectivului nuclear.
Modulul Vulnerabilitate
- Input pentru calculul Vulnerabilitatii Statice a comunitatilor
Modulul Comunicare
- Output pentru Arhiva de date primare, de caracterizare a comunitatilor
- Output pentru Arhiva de caz desktop
- Output pentru Serverul N-WATCHDOG
87
6.2. Gestiunea librăriilor de date 6.2.1. Stocarea
Datele rezidente ale Demonstratorului de concept (PoC) N-WATCHDOG sunt stocate astfel:
Datele DEM (Digital Elevation Maps) – in fisiere tip Random-Access, pre-procesate in cadrul proiectului din fisierele secventiale sau binare obtinute din surse web publice.
Orice alte date si cunostinte asociate – in fisiere secventiale cu acces I/O editabile la interfata.
6.2.2. Utilizarea
Librariile de date N-WATHDOG se acceseaza in doua situatii: (1) in sesiunile de evaluare; si (2) in sesiunile de mentenanta.
In sesiunile de evaluare modulele functionale sunt echipate cu rutinele necesare spre
a adresa fisierele relevante, a cauta datele adecvate si a le livra masinii de calcul. In fisierele Random-Access operatia automata decurge prin cautare standard de campuri indexate; in fisierele secventiale operatia comporta, in general, (i) identificarea de linii text; si/sau (ii) extractia de ‘cuvinte’ (words) prin operatii conventionale cu variabile de tip string$.
In mod caracteristic, pentru colectiile de date aduse la interfata in procesul de calcul s-a prevazut facilitatea editarii directe, in mod text – ce raspunde cerintei cutumiare a utilizatorilor experti, de a putea inlocui anumite valori, sau seturi intregi de valori, cu cele carora le acorda personal incredere – noile valori fiind refectate in outputul sesiunilor. Editarea directa nu altereaza datele-default ale bibliotecilor.
Sesiunile de mentenanta sunt rezervate Dezvoltatorului, sau Administratorului de sistem acreditat de acesta in temeiul unei competente verificate.
Dat fiind caracterul static si volumul considerabil al datelor DEM (resursa maximala SRTM90, de exemplu totalizeaza cca 54 GigaByte de hard disk) sesiunile de mentenanta nu prevad solutii de editare interactiva, la interfata. Asemenea solutii sunt insa disponibile pentru toate celelalte resurse, in cadrul fiecarui modul functional.
Pentru datele radiologice, de importanta centrala in sistem, N-WATCHDOG va oferi un modul dedicat, accesabil direct din pagina de intrare a platformei.
Aspectele teoretice si datele esentiale ale librariilor N-WATCHDOG – cu exceptia datelor DEM - se prezinta in Anexele Raportului.
__________
Nota: Autorii multumesc Dr. Bogdan I. Vamanu pentru contributia esentiala adusa la solutionarea unor probleme de analiza si dezvoltare IT a N-WATCHDOG PoC – proces in curs de desfasurare. Afilierea curenta a colegului si colaboratorului nostru este EC Joint Research Centre Ispra, Institute for Energy and Transport.
88
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(https://narac.llnl.gov/HotSpot/HotSpot.html) 19. Napier B.A.(2011). GENII Version 2 Users’ Guide. PNNL-14583, Rev.3. (http://www.pnnl.gov/main/publications/external/technical_reports/PNNL-14583Rev3.pdf) 20. Chanin D., Young M.L. et al.(1998). Code Manual for MACCS2: Volume 1, User's Guide. NUREG-CR-6613, SAND97-0594. (http://www.doeal.gov/SWEIS/OtherDocuments/481%20MACCS2%20Vol%201.pdf) 21. Imai K., Chino M. et al. (1985). SPEEDI: A Computer Code System for the Real-Time Prediction of Radiation Dose to the Public due to an Accidental Release. Japan Atomic Energy Research Institute. JAERI-1297. (http://jolissrch-inter.tokai-sc.jaea.go.jp/pdfdata/JAERI-1297.pdf) 22. Vamanu D.V., Gheorghe A.V., Acasandrei V.T. and Vamanu B.I. Environmental Modeling for Blue Collars. International Journal of Environment and Pollution Vol. 46, Nos. 3/4, pp. 246–266, 2011. 23. Consultancy meeting 'Advising on evaluating options for the development of assessment capabilities related to source term calculations for nuclear power plant accidents'. IAEA, Incidents and Emergency Center, 9-10 April 2013. 24. Till J.E., Grogan H.A. (2008). Radiological Risk Assessment and Environmental Analysis. Oxford University Press. ISBN 978–0 19–512727–0. 25. IAEA (1997). Generic Assessment Procedures for Determining Protective Actions During a Reactor Accident. IAEA-TECDOC-955, ISSN 1011-4289. 26. Acasandrei V.T., Vamanu D.V., Vamanu B.I. (2012). Fast Methods for Source Term Assessment. CNCAN, Afumati, 3-5 December, 2012. 27. U.S. NRC (1995). International RTM-95 Response Technical Manual. U.S. Nuclear Regulatory Commission, Washington D.C., May 1995. 28. McKenna T., Trefethen J., Gant K., Jolicoeur J., Kuzo G., Athey G. (2006). RTM-96 Response Technical Manual. NUREG/BR-0150, Vol.1, Rev.4, March 1996. U.S. Nuclear Regulatory Commission, Washington D.C. 29. Ministère de l’Ecologie et du Développement Durable – République Francaise (2002). Méthodes pour l’évaluation et la prévention des risques accidentels, Dispersion atmosphérique
(Mécanismes et outils de calcul). DRA-006, -12, INERIS-DRA-2002-25427. 30. Gheorghe A.V., Vamanu D.V. Disaster Risk and Vulnerability Management. From Awareness to Practice, in Gheorghe A.V. (Ed.), Integrated Risk and Vulnerability Management Assisted by Decision Support Systems. Relevance and Impact on Governance, Springer, Dordrecht, ISBN-10 1-4020-3451-2 (HB), ISBN-13 978-1-4020-3451-0 (HB), ISBN-10 1-4020-3721-X (e-book), ISBN-13 978-4020-3721-4 (e-book), Volume 8, pp. 1-320, 2005. 31. Vamanu D.V., Vamanu B.I., Acasandrei V.T. Slavnicu D.S., and Gheorghiu D. Urgenta radiologica la transportul de combustibil nuclear uzat LEU tip EK-10. Accidentul ipotetic, de severitate superioara autorizarii. Suplimente tehnice la solicitarea CNCAN. Partea I. Accident pe segmentul aerian.. IFIN-HH, Raport tehnic intern, comanda 684/09.04.2012, aprilie 2012. 32. Vamanu D.V., Vamanu B.I., Acasandrei V.T. Slavnicu D.S., and Gheorghiu D. Urgenta radiologica la transportul de combustibil nuclear uzat LEU tip EK-10. Accidentul ipotetic, de severitate superioara autorizarii. Suplimente tehnice la solicitarea CNCAN. Partea II. Accident pe segmentul rutier. IFIN-HH, Raport tehnic intern, comanda 684/09.04.2012, mai 2012. 33. Vamanu D.V., Galeriu D., Slavnicu D.S., Gheorghiu D., Melintescu A., Acasandrei V.T. Dezafectarea Reactorului VVR-S al IFIN-HH. Scenarii de accident sever. IFIN-HH, Raport tehnic intern, comanda nr. 545/18.03.2009, aprilie 2009.
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34. Calida B.Y., Gheorghe A.V., Unal R., Vamanu D.V., and Radu C.V. Complexity-Induced Vulnerability Assessment: How Resilient are Our Academic Programs? In Infranomics - Sustainability, Engineering Design and Governance. A.V. Gheorghe, M. Masera, P. F. Katina – Editors. ISBN: 978-3-319-02492-9 (Print), 978-3-319-02493-6 (Online). Topics in Safety, Risk, Reliability and Quality, Volume 24, pp 377-393, 2014. 35. Adrian V. Gheorghe and Dan V. Vamanu. Faces of Resilience. In "Energy Security. International and Local Issues, Theoretical Perspectives, and Critical Energy Infrastructures". NATO Science for Peace and Security Series-C. Part II. Theoretical Prespectives for Energy Security. Edited by A.Gheorghe and L.Muresan. Published by Springer, The Nethelands. ISBN 978-94-007-0721-4 (PB); ISBN 978-94-007-0718-4 (HB); ISBN 978-94-007-0719-1 (e-book), pp. 79-109, 2011. 36. Gheorghe A.V., Vamanu D.V. Towards QVA - Quantitative Vulnerability Assessment: A Generic Practical Model. Journal Risk Research, 7 (6), 616-628, 2004 37. Gheorghe A.V. and Vamanu D.V. Resilience and vulnerability in critical infrastructure systems – a physical analogy. International Journal of Critical Infrastructures, Volume 5, Number 4, pp. 389-397, 2009. 38. Gheorghe A.V., Vamanu D.V. System of Systems concept for Vulnerability Assessment of Large Scale Critical Infrastructures. Atlantic Treaty Association (ATA) Meeting, Norfolk, Virginia, USA, 18 February 2009. 39. Gheorghe A.V. and Vamanu D.V. Mining intelligence data in the benefit of critical infrastructures security: vulnerability modelling, simulation and assessment, system of systems engineering. International Journal of System of Systems Engineering, Vol. 1, Nos. 1/2, 2008, pp. 189-221, 2008 40. BUWAL (1991). Federal Ordinance of April the 1
st, 1991, and the ensuing implementation
guidelines and manuals. Bundesamt fur Umwelt, Wald und Landschaft Storfallverordnong.
A1.1
ANEXA 1
Datele Radiologice Cuprins
Introducere ................................................................................................................ A1.2 A.1.1. Radiological Data - The Inventory ................................................................... A1.3 A.1.2. Selective definitions, assumptions, limitations ................................................. A1.4 A.1.3. Radiological data – the numbers ................................................................... A1.11 A.1.4. Source term specific data ............................................................................. A1.25 A.1.5. Reference data in N-WATCHDOG dosimetry ............................................... A1.29 A.1.6. Nuclear emergency-oriented knowledge elements and guides ..................... A1.32
A1.2
Introducere Dat fiind primatul, in ordinea logicii Proiectului, al Radiologiei (domeniul Radiation Protetction and Nuclear Safety), sectiunile 2 – 4 ale Raportului au tratat, la nivelul de breviar presupus suficient dezvoltarii produselor IT, aspectele teoretice corespunzatoare. Prezenta Anexa va dispensa, in consecinta, lectura de reveniri asupra sensului si misiunii datelor in relatie cu modulele functionale ale sistemului N-WATCHDOG, concentrandu-se asupra datelor in sine, detaliind (a) definitiile tehnice; si (b) seturile de valori. Abordarea aleasa se justifica in lumina unei ipoteze provizorii asupra ordinii naturale in care se va desfasura tranzitia de la Dezvoltatorul de concept N-WATCHDOG PoC spre produsul final asteptat – modelul experimental N-WATCHDOG EM – o secventa de activitati in care datele ocupa prima pozitie:
(1) bazele de date si instrumentele de management al acestora; (2) masina geografica - achizitia de date, localizare, reprezentare; (3) masina meteorologica - achizitia de date si solutiile de management; (4) aplicatiile propriuzise.
Datele radiologice redate fac efectiv parte din inventarul pe care N-WACHDOG PoC il dezvolta. Faptul ca volumul datelor informatiilor redate in tabelele A.1.1 – A.1.3 excede necesitatile stricte de operare a aplicatiilor se explica prin preocuparea autorilor de a respecta dimensiunea educationala asumata explicit de Proiectul PCCA – de a familiariza diversele categorii de utilizatori angajati, sau interesati, in managementul situatiilor de urgenta, dar fara formatie/educatie profesionala in materie, cu cerinte de cunostinte si date specifice in domeniu. Pentru o orientare coreapunzatoare, datele radiologice strict necesare operarii N-WATCHDOG sunt individualizate in tabelele separate A.1.4 si A.1.5.
A1.3
A.1.1. Radiological Data - The Inventory Primary sources: EURATOM, U.S.NRC/DOE/EPA/FRMAC/ORNL, AECL
Data Item
1. ELEMENT
2. ATOMIC NUMBER
3. HALFLIFE T1/2 [hours]
4. HALFLIFE T1/2 [days]
5. MEAN HALFLIFE Tm [days]
6. EARLY PHASE EFFECTIVE EXPOSURE PERIOD Tepeep [eff.hrs/100hrs]
7. EARLY PHASE INHALATION DCFe50 CEDE [(mSv/h)/(kBq/m3)]
8. EARLY PHASE INHALATION DCFab Acute Bone [(mSv/h)/(kBq/m3)]
9. EARLY PHASE INHALATION DCFal Acute Lung [(mSv/h)/(kBq/m3)]
10. EARLY PHASE INHALATION DCFthy Thyroid [(mSv/h)/(kBq/m3)]
11. EARLY PHASE DEPO.EXTNL.EXPOSURE RATE ECFg [(mGy/h)/(kBq/m3)]
12. EARLY PHASE DEPO.EXTNL.EDE DOSE RATE DCFg [(mSv/h)/(kBq/m2)]
13. DEPO.4-DAY DOSE EXT.& NON-ARID DCFepgna [(mSv/7d)/(kBq/m2)]
14. DEPO.4-DAY DOSE EXT.& ARID RSPN. DCFepga [(mSv/7d)/(kBq/m2)]
15. AIR IMMERSION EXTERNAL EDE DOSE RATE DCFa [((mSv/h)/(kBq/m3)]
16. INTERMEDIATE PHASE EFF.EXPOSURE PERIOD Tipeep [eff.hrs/1year]
17. INTERMD.PH.DCF DEPO 1st year NORMAL [(mSv in 1st y)/(kBq/m2)]
18. INTERMD.PH.DCF DEPO 1st month NON-ARID [(mSv in 1st mnt)/(kBq/m2)]
19. INTERMD.PH.DCF DEPO 2nd month NORMAL [(mSv 2nd mnt)/(kBq/m2)]
20. INTERMD.PH.DCF DEPO 50 y NORMAL [(mSv 50 y)/(kBq/m2)]
21. ISOTOPE/Cs-137 RATIO FOR REACTOR CORE DAMAGE ACCIDENTS 1 hr
22. ISOTOPE/Cs-137 RATIO FOR REACTOR CORE DAMAGE ACCIDENTS 6 hrs
23. ISOTOPE/Cs-137 RATIO FOR REACTOR CORE DAMAGE ACCIDENTS 12 hrs
24. ISOTOPE/Cs-137 RATIO FOR REACTOR CORE DAMAGE ACCIDENTS 24 hrs
25. ISOTOPE/Cs-137 RATIO FOR REACTOR CORE DAMAGE ACCIDENTS 3 d
26. ISOTOPE/Cs-137 RATIO FOR REACTOR CORE DAMAGE ACCIDENTS 7 d
27. ISOTOPE/Cs-137 RATIO FOR REACTOR CORE DAMAGE ACCIDENTS 15 d
28. ISOTOPE/Cs-137 RATIO FOR REACTOR CORE DAMAGE ACCIDENTS 30 d
29. INTERMD.PH.DCF INHL.RESPND.MAT.DCFipa [(mSv 1st mnt)/(kBq/m3)]
30. INTERMD.PH.DCF SKIN DOSE FROM DEPO [(mSv in 1st y)/(kBq/m2)]
31. COW TRANSFER FACTOR [(kBq/L)/(kBq/d)]
32. INGESTION CRITICAL ORGAN
33. CHILD INGESTION DOSE CONVERSION FACTOR DCFingch [mSv/kBq]
34. INFANT INGESTION DOSE CONVERSION FACTOR DCFingch [mSv/kBq]
35. INFANT INGESTION CEDE CONVERSION FACTOR [mSv/kBq]
36. ISOTOPE SPECIFIC ACTIVITY [Ci/g]
37. LWR TYPICAL CORE INVENTORY [Ci/MWe]
38. BWR TYPICAL COOLANT CONTAMINATION [Ci/g]
39. PWR TYPICAL COOLANT CONTAMINATION [Ci/g]
40. LWR CORE RELEASE FRACTIONS AT 650 C
41. LWR CORE RELEASE FRACTIONS AT 1250 C
42. LWR CORE RELEASE FRACTIONS AT 1650 C
43. ISOTOPE DECAY MODES
44. TARGET NUCLIDE FOR NEUTRON ACTIVATION
45. TARGET MATERIAL FOR NUCLIDE ACTIVATION
46. NEUTRON TARGET NUCLIDE ABUNDANCE IN TARGET MATERIAL [%]
47. NEUTRON ACTIVATION CROSS-SECTION OF TARGET NUCLIDE [cm2]
48. ELEMENT DENSITY [g/cm3]
49. DEPOSITION VELOCITY [m/s]
50. WASHOUT RATE [1/s]
51. WASHOUT EXPONENT []
A1.4
A.1.2. Selective definitions, assumptions, limitations - cf. A.1.1. box indexing -
3. On HALFLIFE T1/2 [hours]
_________________________________________________________________________
The halflife given for the following nuclides in the left column actually
applies to the mixtures in the right column:
Ti-44 ........... Ti-44 + Sc-44
Ge-68 ........... Ge-68 + Ga-68
Kr-88 ........... Kr-88 + Rb-88
Mo-99 ........... Mo-99 + Tc-99m
Ru-106 ........... Ru-106 + Rh-106
Cd-109 ........... Cd-109 + Ag-109m
Sn-113 ........... Sn-113 + In-113m
Sn-126 ........... Sn-126 + Sb-126m
I-135 ........... I-135 + Xe-135m
Cs-137 ........... Cs-137 + Br-137m
Ce-144 ........... Ce-144 + Pr-144m
4. On HALFLIFE T1/2 [days]
_________________________________________________________________________
The halflife given for the following nuclides in the left column actually
applies to the mixtures in the right column:
Ti-44 ........... Ti-44 + Sc-44
Ge-68 ........... Ge-68 + Ga-68
Kr-88 ........... Kr-88 + Rb-88
Mo-99 ........... Mo-99 + Tc-99m
Ru-106 ........... Ru-106 + Rh-106
Cd-109 ........... Cd-109 + Ag-109m
Sn-113 ........... Sn-113 + In-113m
Sn-126 ........... Sn-126 + Sb-126m
I-135 ........... I-135 + Xe-135m
Cs-137 ........... Cs-137 + Br-137m
Ce-144 ........... Ce-144 + Pr-144m
5. On MEAN HALFLIFE Tm [days]
_________________________________________________________________________
The MEAN HALFLIFE is defined as:
Tm = T1/2 x 1.44
with T1/2 - the radiological halflife .
6. On EARLY PHASE EFFECTIVE EXPOSURE PERIOD Tepeep [eff.hrs/100hrs]
_________________________________________________________________________
The halflife given for the following nuclides in the left column actually
applies to the mixtures in the right column:
Ti-44 ........... Ti-44 + Sc-44
Ge-68 ........... Ge-68 + Ga-68
Kr-88 ........... Kr-88 + Rb-88
Mo-99 ........... Mo-99 + Tc-99m
Ru-106 ........... Ru-106 + Rh-106
Cd-109 ........... Cd-109 + Ag-109m
Sn-113 ........... Sn-113 + In-113m
Sn-126 ........... Sn-126 + Sb-126m
A1.5
I-135 ........... I-135 + Xe-135m
Cs-137 ........... Cs-137 + Br-137m
Ce-144 ........... Ce-144 + Pr-144m
For isotopes with short lived daughters (e.g.Cs-137, Br-137m), that are
expected to be in equilibrium the Effective Period is based on the half
life of their parent.
Early Phase Effective Exposure Period is calculated by:
Tepeep = T1/2 x [1 - 0.5**(100/(T1/2))]
1 hour is assumed to be the minimum Effective Exposure Period.
7. On EARLY PHASE INHALATION DCFe50 CEDE [mrem/h)/(uCi/m3)]
_________________________________________________________________________
CEDE Factor (DCFe50) is the Committed Effective Dose Equivalent exposure-
to-dose conversion factor:
DCFe50 = EDCFe50 x BR x CF
where
EDCFe50 - Exposure-to-Dose Conversion Factors from EPA-520/1-88-020,
'Limiting Values of Radionuclides Intake and Air concentration and Dose
Conversion Factors for Inhalation Submersion and Ingestion; Federal
Guidance Report No 11', Table 2.1 page 121 'Effective' column.
BR - breathing rate for an adult performing light activity, EPA-520/1-88-
020 op.cit., page 10: 0.020 m3/min x 60 min/hr = 1.2 m3/hr.
CF - conversion factor for units:
Sv/Bq x 1.0E+05 mrem/Sv x Bq/(2.7E-05 uCi) = 3.7E+09 mrem/uCi
For H-3 CEDE Dose factor was doubled to account for skin absorption.
For Natural and Depleted Uranium it is assumed that all the release is
U-238. For Enriched Uranium it is assumed that all the release is U-234.
The specific activity of Natural and Depleted Uranium is dominated by the
concentration of U-238, whereas the Enriched Uranium is dominated by
U-234 (because of its high SpA). While releases from Natural and Enriched
Uranium will be composed principally of a mixture of U-234, U-235 and
U-238, the Dose factors are all within 10%, so it is reasonable to use a
single factor.
8. On EARLY PHASE INHALATION DCFab Acute Bone [mrem/h)/(uCi/m3)]
_________________________________________________________________________
Acute Bone Marrow Dose Factors (DCFab) from inhalation by an adult, i.e.
30 day equivalent dose acquired in red bone marrow:
DCFab = ABM-AD x QF x BR x CF
where
ABM-AD - Acute Bone Marrow Absorbed Dose (Gy/Bq) from NRPB R-162 'Dose
from Intake of Radionuclides by Adults and Young People', Table A.4, page
40. The most conservative lung clearance class was used.
QF - Quality Factor. The dose equivalent was computed using a QF = 10 to
better represent the acute dose.
A1.6
BR - breathing rate for an adult performing light activity, EPA-520/1-88-
020 op.cit., page 10: 0.020 m3/min x 60 min/hr = 1.2 m3/hr.
CF - conversion factor for units:
Sv/Bq x 1.0E+05 mrem/Sv x Bq/(2.7E-05 uCi) = 3.7E+09 mrem/uCi
9. On EARLY PHASE INHALATION DCFal Acute Lung [mrem/h)/(uCi/m3)]
_________________________________________________________________________
Acute Lung Dose Factors (DCFal) from inhalation by an adult, i.e.
30 day equivalent dose in the lung:
DCFal = AL-AD x QF x BR x CF
where
AL-AD - Acute Lung - Absorbed Dose (Gy / Bq) from NRPB R - 162 'Dose
from Intake of Radionuclides by Adults and Young People', Table A.5, page
43. The most conservative lung clearance class was used.
QF - Quality Factor. The dose equivalent was computed using a QF = 10 to
better represent the acute dose.
BR - breathing rate for an adult performing light activity, EPA-520/1-88-
020 op.cit., page 10: 0.020 m3/min x 60 min/hr = 1.2 m3/hr.
CF - conversion factor for units:
Sv/Bq x 1.0E+05 mrem/Sv x Bq/(2.7E-05 uCi) = 3.7E+09 mrem/uCi
10. On EARLY PHASE INHALATION DCFthy Thyroid [mrem/h)/(uCi/m3)]
_________________________________________________________________________
Thyroid Dose Conversion Factor (DCFthy) from inhalation by an adult:
DCFthy = EDCFt x BR x CF
where
EDCFt - EPA-520/1-88-020 'Limiting Values of radionuclides Intake and Air
Concentration and Dose Conversion Factors for Inhalation Submersion and
Ingestion; Federal Guidance report No 11. Table 2.2, page 121 'Effective'
Column.
BR - breathing rate for an adult performing light activity, EPA-520/1-88-
020 op.cit., page 10: 0.020 m3/min x 60 min/hr = 1.2 m3/hr.
CF - conversion factor for units:
Sv/Bq x 1.0E+05 mrem/Sv x Bq/(2.7E-05 uCi) = 3.7E+09 mrem/uCi
11. On EARLY PHASE DEPO.EXTNL.EXPOSURE RATE ECFg [(mR/h)/(uCi/m2)]
_________________________________________________________________________
Quantity is the exposure rate at 1m AGL from 1 uCi/m2 deposition of iso-
tope, corrected for ground roughness. based on 'Dose Conversion for Expo-
sure to Contaminated Ground Surface' (DCECGS) factors from 'External Ex-
posure to Radionuclides in Air, Water and Soil, Federal Guidance Report
No.12', EPA-402-R-93-081, Table III.3. The effective dose was multiplied
by 1.4 to estimate exposure. The external dose from daughters expected to
be in equilibrium is included for the following: T-44+Sc-44, Ge-68+Ga-68,
A1.7
Kr-88+Rb-88, Mo-99+Tc-99m, Ru-106+Rh-106, Cd-109+Ag-109m, Sn-113+In-113m,
Sn-126+Sb-126m, I-135+Xe-135m, Cs-137+Ba-137m, Ce-144+Pr-144.
ECFg = DCECGS x SiCF x GRCF x 1.4
where
GRCF = Ground roughness correction factor of .7 to convert the dose pro-
jected for a smooth plane to typical ground surface.
SiCF = IS unit conversion factor:
Sv/s 3.6E+03 s 1E+05 mrem Bq 1.33 E+13 mrem/hr
---- x --------- x ---------- x ----------- = -----------------
Bq hr Sv 2.7E-05 uCi uCi/m2
For Natural and Depleted Uranium it is assumed that all the release is
U-238. For Enriched Uranium the release is assumed as consisting of U-234
only. The activity of Natural and depleted Uranium is dominated by the
concentration of U-238 whereas that of Enriched Uranium is dominated by
the concentration of U-234 (because of its high SpA). While releases from
Natural and Enriched Uranium will be composed principally of a mixture of
U-234, U-235 and U-238, the dose factors are all within 10%, so that it
is reasonable to use a single factor.
12. On EARLY PHASE DEPO.EXTNL.EDE DOSE RATE DCFg [(mrem/h)/(uCi/m2)]
_________________________________________________________________________
Quantity is Effective Dose Equivalent (EDE) from 1 hour external exposure
at 1 m above ground level (AGL) from a contaminated ground surface (CGS).
Based on 'Dose Coefficients for Exposure to Contaminated Ground Surface'
(DCECGS) factors from 'External Exposure to Radionuclides in Air, Water
and Soil, Federal Guidance Report No.12', EPA-402-R-93-081, Table III.3.
Daughters contribution included as follows: T-44+Sc-44, Ge-68+Ga-68,
Kr-88+Rb-88, Mo-99+Tc-99m, Ru-106+Rh-106, Cd-109+Ag-109m, Sn-113+In-113m,
Sn-126+Sb-126m, I-135+Xe-135m, Cs-137+Ba-137m, Ce-144+Pr-144.
DCFg = DCECGS x SiCF x GRCF
where
GRCF = Ground roughness correction factor of .7 to convert the dose pro-
jected for a smooth plane to typical ground surface.
SiCF = IS unit conversion factor:
Sv/s 3.6E+03 s 1E+05 mrem Bq 1.33 E+13 mrem/hr
---- x --------- x ---------- x ----------- = -----------------
Bq hr Sv 2.7E-05 uCi uCi/m2
For Natural and Depleted Uranium it is assumed that all the release is
U-238. For Enriched Uranium the release is assumed as consisting of U-234
only. The activity of Natural and depleted Uranium is dominated by the
concentration of U-238 whereas that of Enriched Uranium is dominated by
the concentration of U-234 (because of its high SpA). While releases from
Natural and Enriched Uranium will be composed principally of a mixture of
U-234, U-235 and U-238, the dose factors are all within 10%, so that it
is reasonable to use a single factor.
13. On DEPO.4-DAY DOSE EXT.& NON-ARID DCFepgna [(mrem/4d)/(uCi/m2)]
_________________________________________________________________________
A1.8
Quantity is the total dose from remaining on contaminated ground for four
days, and includes the external exposure from GSC and the CEDE from
resuspension. The dose is calculated for two different resuspension
factors: arid (Rs = 1E-04), and non-arid (Rs = 1E-06). See Method M.3.3
in Manual for a full description of how DCFepg is calculated.
Daughters contribution included as follows: T-44+Sc-44, Ge-68+Ga-68,
Kr-88+Rb-88, Mo-99+Tc-99m, Ru-106+Rh-106, Cd-109+Ag-109m, Sn-113+In-113m,
Sn-126+Sb-126m, I-135+Xe-135m, Cs-137+Ba-137m, Ce-144+Pr-144.
For Natural and Depleted Uranium it is assumed that all the release is
U-238. For Enriched Uranium the release is assumed as consisting of U-234
only. The activity of Natural and depleted Uranium is dominated by the
concentration of U-238 whereas that of Enriched Uranium is dominated by
the concentration of U-234 (because of its high SpA). While releases from
Natural and Enriched Uranium will be composed principally of a mixture of
U-234, U-235 and U-238, the dose factors are all within 10%, so that it
is reasonable to use a single factor.
15. On AIR IMMERSION EXTERNAL EDE DOSE RATE DCFa [(mrem/h)/(uCi/m3)]
_________________________________________________________________________
Quantity is the external EDE from 1 hr exposure to a semi-infinite cloud
of constant concentration. Based on 'Dose Coefficients for Air Submersion'
(DCAS) from 'External Exposure to Radionuclides in Air, Water and Soil,
Federal Guidance Report No.12', EPA-402-R-93-081, Table III.1. One has:
DCFa = DCAS x SiCF
Daughters contribution included as follows: T-44+Sc-44, Ge-68+Ga-68,
Kr-88+Rb-88, Mo-99+Tc-99m, Ru-106+Rh-106, Cd-109+Ag-109m, Sn-113+In-113m,
Sn-126+Sb-126m, I-135+Xe-135m, Cs-137+Ba-137m, Ce-144+Pr-144.
SiCF = IS unit conversion factor:
Sv/s 3.6E+03 s 1E+05 mrem Bq 1.33 E+13 mrem/hr
---- x --------- x ---------- x ----------- = -----------------
Bq hr Sv 2.7E-05 uCi uCi/m2
For Natural and Depleted Uranium it is assumed that all the release is
U-238. For Enriched Uranium the release is assumed as consisting of U-234
only. The activity of Natural and depleted Uranium is dominated by the
concentration of U-238 whereas that of Enriched Uranium is dominated by
the concentration of U-234 (because of its high SpA). While releases from
Natural and Enriched Uranium will be composed principally of a mixture of
U-234, U-235 and U-238, the dose factors are all within 10%, so that it
is reasonable to use a single factor.
16. On INTERMEDIATE PHASE EFF.EXPOSURE PERIOD Tipeep [eff.hrs/1year]
_________________________________________________________________________
The halflife given for the following nuclides in the left column actually
applies to the mixtures in the right column:
Ti-44 ........... Ti-44 + Sc-44
Ge-68 ........... Ge-68 + Ga-68
Kr-88 ........... Kr-88 + Rb-88
Mo-99 ........... Mo-99 + Tc-99m
Ru-106 ........... Ru-106 + Rh-106
Cd-109 ........... Cd-109 + Ag-109m
Sn-113 ........... Sn-113 + In-113m
Sn-126 ........... Sn-126 + Sb-126m
I-135 ........... I-135 + Xe-135m
A1.9
Cs-137 ........... Cs-137 + Br-137m
Ce-144 ........... Ce-144 + Pr-144m
For isotopes with short lived daughters (e.g.Cs-137, Br-137m), that are
expected to be in equilibrium the Effective Period is based on the half
life of their parent.
Intermediate Phase Effective Exposure Period is calculated by:
Tepeep = T1/2 x [1 - 0.5**(8760/(T1/2))]
1 hour is assumed to be the minimum Effective Exposure Period.
17. On INTERMD.PH.DCF DEPO 1st year NORMAL [(mrem in 1st y)/(uCi/m2)]
_________________________________________________________________________
Dose includes external dose from groundshine and CEDE from resuspension.
Groundshine Dose factors are from Federal Guidance Report No 12 (EPA93)
and are corrected for ground roughness. All doses based on RASCAL 2.1.
Decay, ingrowth and weathering considered. Doses are calculated using the
method recommended by EPA (EPA91).
Initial resuspension rates for arid areas (1E-04) are from An-75, whereas
those for normal areas (1E-06) are from IAEA86. The effects of weathering
using EPA assumptions was considered for the 1st year dose.The respective
assumptions are seen as very conservative.
For Strontium the beta dose to the skin from resuspension may be critical.
For Natural and Depleted Uranium it is assumed that all the release is
U-238, whereas for the Enriched Uranium it assumed as consisting of U-234.
For isotopes with short lived daughters (e.g.Cs-137, Br-137m), that are
expected to be in equilibrium the Effective Period is based on the half
life of their parent.
Intermediate Phase Effective Exposure Period is calculated by:
Tepeep = T1/2 x [1 - 0.5**(8760/(T1/2))]
1 hour is assumed to be the minimum Effective Exposure Period.
20. On INTERMD.PH.DCF DEPO 50 y NORMAL [(mrem 50 y)/(uCi/m2)]
_________________________________________________________________________
Dose includes external dose from groundshine and CEDE from resuspension.
Groundshine Dose factors are from Federal Guidance Report No 12 (EPA93)
and are corrected for ground roughness. All doses based on RASCAL 2.1.
Decay, ingrowth and weathering considered. Doses are calculated using the
method recommended by EPA (EPA91).
Initial resuspension rates for arid areas (1E-04) are from An-75, whereas
those for normal areas (1E-06) are from IAEA86. The effects of weathering
using EPA assumptions was considered for the 1st year dose.The respective
assumptions are seen as very conservative.
For Strontium the beta dose to the skin from resuspension may be critical.
For Natural and Depleted Uranium it is assumed that all the release is
U-238, whereas for the Enriched Uranium it assumed as consisting of U-234.
For isotopes with short lived daughters (e.g.Cs-137, Br-137m), that are
expected to be in equilibrium the Effective Period is based on the half
life of their parent.
A1.10
Intermediate Phase Effective Exposure Period is calculated by:
Tepeep = T1/2 x [1 - 0.5**(8760/(T1/2))]
1 hour is assumed to be the minimum Effective Exposure Period.
21-28. On ISOTOPE/Cs-137 RATIO FOR REACTOR CORE DAMAGE ACCIDENTS
1 hr, 6hr, 12hr, 24hr, 3d, 7d, 15d, 30d
_________________________________________________________________________
The isotopes the most important to the intermediate and ingestion path-
ways for reactor accidents are included. Decay and ingrowth considered.
The ratio is believed to be valid for most accidents involving such
isotopes (NRC95).
29. On INTERMD.PH.DCF INHL.RESPND.MAT.DCFipa [(mrem 1st y)/(uCi/m3)]
_________________________________________________________________________
DCF calculated using dose factors in EPA/520/1-88-020 'Federal Guidance
Report 11' (EPA88), Table 2.1. Short lived daughters are not listed
separately because entries include the dose from both the daughter and
the parent. Such factors are based on the concentration of the parent
only, at the beginning of the exposure period. The lung clearance class
chosen is that which results in the highest dose conversion factor.
Parent-daughter cases include: Ge-68+Ga-68; Kr-88+Rb-88; Ru-106+Rh-106;
Cd-109+Ag-109m; Sn-126+Sb-126m; Te-129m+Te-129; I-135+Xe-135m; Cs-137+
Ba-137m; Ce-144+Pr-144.
Quantities are committed effective dose equivalents for one year per
unit air concentration considering only decay.
30. On INTERMD.PH.DCF SKIN DOSE FROM DEPO [(mrem in 1st y)/(uCi/m2)]
_________________________________________________________________________
Factors from EPA Manual of PAGs (EPA91) multiplied by 1E+06 to convert
to mrem/uCi. Doses for Pu isotopes are from EPA89 Table A1.
Quantities are dose equivalents integrated for a one-year exposure at one
meter height plus the estimated dose to the skin from materials deposited
on the skin as a result of resuspension (EPA91). Doses estimated based on
these factors consider decay and weathering and should be conservative.
The skin dose from resuspension is not considered critical for a reactor
accident. Skin dose is projected based on ground concentration due to the
difficulty in estimating skin dose based on other methods.
31. On COW TRANSFER FACTOR [(uCi/L)/(uCi/d)]
_________________________________________________________________________
Source: NUREG/CR-3323, (NRC83).
32. On INGESTION CRITICAL ORGAN
_________________________________________________________________________
Organs with the highest dose from ingestion.
Abbreviations used:
Bone S = Bone Surface /1 = ICRP-56 Age-dependent Doses
Bone M = Red Bone Marrow to Members of the Public
Stomch = Stomach
St.wll = Stomach Wall /2 = NRPB-GS7 Committed Dose
Pancrs = Pancreas to Selective Organs...
A1.11
LLI = Lower Large Intestine
LLIW = Lower Large Intestine Wall
ULI = Upper Large Intestine
33. On CHILD INGESTION DOSE CONVERSION FACTOR DCFingch [mrem/uCi]
_________________________________________________________________________
HHS guidance states that the critical tissue and population (receiving
the highest dose) for each isotope should be used. For milk ingestion HHS
recommends that the infant be used as the critical population. For simpli-
city, for other foods and water it was decided to use the child (10 years
old) as the critical population. Considering ingestion rates and dose fac-
tors, the child was considered to be representative but conservative.
Table 5.5 in Manual lists the ingestion DCFs used throughout both Manual
and this code, which are based on the methods described in ICRP-56 where
available and ICRP-30 for the other isotopes. The DCFs in the EPA Federal
Report No.11 (D) were not used because they did not conform to the HHS
guidance that the dose to the critical population is calculated.
To convert from Sv/Bq to mrem/uCi use:
Sv 1.0E+05 mrem Bq mrem
-- x ------------ x ----------- = 3.7E+09 ----
Bq Sv 2.7E-05 uCi uCi
34. On INFANT INGESTION DOSE CONVERSION FACTOR DCFingch [mrem/uCi]
_________________________________________________________________________
HHS guidance states that the critical tissue and population (receiving
the highest dose) for each isotope should be used. For milk ingestion HHS
recommends that the infant be used as the critical population. For simpli-
city, for other foods and water it was decided to use the child (10 years
old) as the critical population. Considering ingestion rates and dose fac-
tors, the child was considered to be representative but conservative.
Table 5.5 in Manual lists the ingestion DCFs used throughout both Manual
and this code, which are based on the methods described in ICRP-56 where
available and ICRP-30 for the other isotopes. The DCFs in the EPA Federal
Report No.11 (D) were not used because they did not conform to the HHS
guidance that the dose to the critical population is calculated.
To convert from Sv/Bq to mrem/uCi use:
Sv 1.0E+05 mrem Bq mrem
-- x ------------ x ----------- = 3.7E+09 ----
Bq Sv 2.7E-05 uCi uCi
A.1.3. Radiological data – the numbers Primary sources: EURATOM, U.S.NRC/DOE/EPA/FRMAC/ORNL, AECL
RADIOLOGICAL NUCLIDE DATA
_________________________
1. ELEMENT
2. ATOMIC NUMBER
3. HALFLIFE T1/2 [hours]
4. HALFLIFE T1/2 [days]
5. MEAN HALFLIFE Tm [days]
6. EARLY PHASE EFFECTIVE EXPOSURE PERIOD Tepeep [eff.hrs/100hrs]
7. EARLY PHASE INHALATION DCFe50 CEDE [(mSv/h)/(kBq/m3)]
A1.12
8. EARLY PHASE INHALATION DCFab Acute Bone [(mSv/h)/(kBq/m3)]
9. EARLY PHASE INHALATION DCFal Acute Lung [(mSv/h)/(kBq/m3)]
10. EARLY PHASE INHALATION DCFthy Thyroid [(mSv/h)/(kBq/m3)]
__________________________________________________________________
1 2 3 4 5 6 7 8 9 10
_____________________________________________________________________________________________________________________________________________________________________
H-3 hydrogen 1 1.1e05 4.5e03 6.5e03 100 5.40e-05 2.58e-06 2.58e-06 NC
C-14 carbon 6 5.0e07 2.1e06 3.0e06 100 2.40e-03 2.27e-05 2.27e-05 NC
Na-22 sodium 11 2.3e04 9.5e02 1.4e03 100 1.56e-03 NC NC NC
Na-24 sodium 11 1.5e01 6.3e-01 9.0e-01 21 3.24e-04 1.72e-04 1.34e-03 NC
P-32 phosphorus 15 3.4e02 1.4e01 2.1e01 90 4.08e-03 4.50e-04 4.30e-03 NC
P-33 phosphorus 15 6.1e02 2.5e01 3.7e01 94 1.80e-03 NC NC NC
S-35 sulfur 16 2.1e03 8.7e01 1.3e02 98 1.68e-03 7.50e-06 3.28e-04 NC
Cl-36 chlorine 17 2.6e09 1.1e08 1.6e08 100 8.76e-03 NC NC NC
K-40 potassium 19 1.1e13 4.7e11 6.7e11 100 2.52e-03 NC NC NC
K-42 potassium 19 1.2e01 5.2e-01 7.4e-01 18 1.44e-04 NC NC NC
Ca-45 calcium 20 3.9e03 1.6e02 2.3e02 99 3.24e-03 NC NC NC
Sc-46 scandium 21 2.0e03 8.4e01 1.2e02 98 8.16e-03 NC NC NC
Ti-44 titanium 22 4.1e05 1.7e04 2.5e04 100 1.44e-01 NC NC NC
V-48 vanadium 23 3.9e02 1.6e01 2.3e01 91 2.88e-03 NC NC NC
Cr-51 chromium 24 6.6e02 2.8e01 4.0e01 95 4.44e-05 3.56e-06 4.30e-05 NC
Mn-54 manganese 25 7.5e03 3.1e02 4.5e02 99 1.02e-03 9.20e-05 3.00e-04 NC
Mn-56 manganese 25 2.6e00 1.1e-01 1.5e-01 4 1.44e-04 NC NC NC
Fe-55 iron 26 2.4e04 9.9e02 1.4e03 100 4.56e-04 1.11e-06 3.76e-05 NC
Co-58 cobalt 27 1.7e03 7.1e01 1.0e02 98 1.92e-03 6.90e-05 5.70e-04 NC
Fe-59 iron 26 1.1e03 4.5e01 6.4e01 97 4.44e-03 1.29e-04 1.21e-03 NC
Co-60 cobalt 27 4.6e04 1.9e03 2.8e03 100 1.20e-02 1.66e-04 1.46e-03 NC
Ni-63 nickel 28 8.4e05 3.5e04 5.0e04 100 1.56e-03 3.16e-06 1.14e-04 NC
Cu-64 copper 29 1.3e01 5.3e-01 7.6e-01 18 1.44e-04 NC NC NC
Zn-65 zinc 30 5.9e03 2.4e02 3.5e02 99 1.92e-03 4.80e-05 2.60e-04 NC
Ga-68 gallium 31 1.1e00 4.7e-02 6.8e-02 2 5.88e-05 2.50e-06 2.52e-04 NC
Ge-68 germanium 32 6.9e03 2.9e02 4.1e02 99 1.68e-02 NC 9.32e-01 NC
Se-75 selenium 34 2.9e03 1.2e02 1.7e02 99 1.56e-03 5.30e-05 2.80e-04 NC
Kr-85 krypton 36 9.4e04 3.9e03 5.6e03 100 1.98e-07 NC NC NC
Kr-85m krypton 36 4.5e00 1.9e-01 2.7e-01 6 1.26e-07 NC NC NC
Kr-87 krypton 36 1.3e00 5.3e-02 7.6e-02 2 4.22e-07 NC NC NC
Kr-88 krypton 36 2.8e00 1.2e-01 1.7e-01 4 1.01e-06 NC NC NC
Rb-86 rubidium 37 4.5e02 1.9e01 2.7e01 92 1.12e-03 2.17e-04 1.88e-03 NC
Rb-87 rubidium 37 4.1e14 1.7e13 2.5e13 100 6.00e-04 NC NC NC
Rb-88 rubidium 37 3.0e-01 1.2e-02 1.8e-02 1 1.92e-05 NC NC NC
Sr-89 strontium 38 1.2e03 5.1e01 7.3e01 97 7.32e-03 2.20e-04 3.92e-03 NC
Sr-90 strontium 38 2.6e05 1.1e04 1.5e04 100 4.32e-02 2.36e-04 3.30e-03 NC
Sr-91 strontium 38 9.50e00 4.00e-01 5.70e-01 14 4.92e-04 NC NC NC
Y-90 yttrium 39 6.40e01 2.70e00 3.80e00 61 1.80e-03 9.30e-05 4.52e-03 NC
Y-91 yttrium 39 1.40e03 5.90e01 8.40e01 97 1.07e-02 9.90e-05 4.10e-03 NC
Y-91m yttrium 39 8.3e-01 3.5e-02 5.0e-02 1 1.32e-05 NC NC NC
Zr-93 zirconium 40 1.3e10 5.6e08 8.0e08 100 3.00e-02 NC NC NC
Zr-95 zirconium 40 1.5e03 6.4e01 9.2e01 98 5.76e-03 2.05e-04 1.06e-03 NC
Nb-94 niobium 41 1.8e08 7.4e06 1.1e07 100 5.88e-02 NC NC NC
Nb-95 niobium 41 8.4e02 3.5e01 5.1e01 96 1.80e-03 7.00e-05 5.40e-04 NC
Mo-99 molybdenum 42 6.6e01 2.8e00 4.0e00 62 1.07e-03 1.24e-04 2.04e-03 NC
Tc-99 technetium 43 1.9e09 7.8e07 1.1e08 100 4.80e-03 1.20e-05 6.80e-04 NC
Tc-99m technetium 43 6.0e00 2.5e-01 3.6e-01 9 2.28e-05 3.62e-06 3.52e-05 NC
Ru-103 ruthenium 44 9.4e02 3.9e01 5.7e01 96 2.88e-03 6.10e-05 9.10e-04 NC
Ru-105 ruthenium 44 4.4e00 1.9e-01 2.7e-01 6 2.04e-04 NC NC NC
Rh-106 rhodium 45 8.3e-02 3.5e-04 5.0e-04 1 NC NC NC NC
Ru-106 ruthenium 44 8.8e03 3.7e02 5.3e02 99 3.36e-02 2.39e-04 9.80e-03 NC
Ag-110m silver 47 6.0e03 2.5e02 3.6e02 99 9.12e-03 2.30e-04 1.51e-03 NC
Cd-109 cadmium 48 1.1e04 4.6e02 6.7e02 100 9.72e-03 NC NC NC
Cd-113m cadmium 48 1.2e05 5.0e03 7.1e03 100 1.32e-01 NC NC NC
In-114m indium 49 1.2e03 5.0e01 7.1e01 97 1.12e-02 NC NC NC
A1.13
Sn-113 tin 50 2.8e03 1.2e02 1.7e02 99 3.24e-03 NC NC NC
Sn-123 tin 50 3.1e03 1.3e02 1.9e02 99 9.72e-03 NC NC NC
Sn-126 tin 50 8.8e08 3.7e07 1.8e01 100 3.36e-02 NC NC NC
Sb-124 antimony 51 1.4e03 6.0e01 8.7e01 97 7.68e-03 2.82e-04 3.10e-03 NC
Sb-126 antimony 51 3.0e02 1.2e01 1.8e01 89 3.36e-03 NC NC NC
Sb-126m antimony 51 3.2e-01 1.3e-02 1.9e-02 1 2.28e-05 NC NC NC
Sb-127 antimony 51 9.2e01 3.9e00 5.5e00 70 2.04e-03 NC NC NC
Sb-129 antimony 51 4.3e00 1.8e-01 2.6e-01 6 2.76e-04 NC NC NC
Te-127 tellurium 52 9.4e00 3.9e-01 5.6e-01 13 1.56e-04 NC NC NC
Te-127m tellurium 52 2.6e03 1.1e02 1.6e02 99 8.88e-03 1.32e-04 1.57e-03 NC
Te-129 tellurium 52 1.2e00 4.8e-02 7.0e-02 2 4.44e-05 NC NC NC
Te-129m tellurium 52 8.1e02 3.4e01 4.8e01 96 7.92e-03 2.72e-04 3.92e-03 NC
Te-131 tellurium 52 4.2e-01 1.7e-02 2.5e-02 1 3.36e-05 NC NC 3.16e-03
Te-131m tellurium 52 3.0e01 1.3e00 1.8e00 39 1.13e-03 1.26e-04 1.64e-03 4.33e-02
Te-132 tellurium 52 7.8e01 3.3e00 4.7e00 66 2.40e-03 9.90e-05 6.40e-04 3.00e-02
I-125 iodine 53 1.4e03 6.0e01 8.7e01 97 6.12e-03 5.44e-06 8.50e-05 1.20e-01
I-129 iodine 53 1.4e11 5.7e09 8.3e09 100 4.32e-02 5.66e-06 1.92e-04 8.52e-01
I-131 iodine 53 1.9e02 8.0e00 1.2e01 84 8.88e-03 2.38e-05 5.66e-04 1.80e-01
I-132 iodine 53 2.3e00 9.6e-02 1.4e-01 3 1.13e-04 1.68e-05 3.24e-04 1.68e-03
I-133 iodine 53 2.1e01 8.7e-01 1.2e00 29 1.80e-03 2.74e-05 8.64e-04 3.36e-02
I-134 iodine 53 8.8e-01 3.7e-02 5.3e-02 1 5.40e-05 7.32e-06 1.68e-04 3.12e-04
I-135 iodine 53 6.6e00 2.8e-01 4.0e-01 10 3.84e-04 2.64e-05 5.18e-04 6.84e-03
Xe-131m xenon 54 2.9e02 1.2e01 1.7e01 89 NC NC NC NC
Xe-133 xenon 54 1.3e02 5.2e00 7.6e00 77 5.19e-07 NC NC NC
Xe-133m xenon 54 5.3e01 2.2e00 3.2e00 55 NC NC NC NC
Xe-135 xenon 54 9.1e00 3.8e-01 5.5e-01 13 6.81e-07 NC NC NC
Xe-135m xenon 54 2.5e-01 1.1e-02 1.5e-02 1 NC NC NC NC
Xe-138 xenon 54 2.4e-01 9.8e-03 1.4e-02 1 NC NC NC NC
Cs-134 caesium 55 1.8e04 7.5e02 1.1e03 100 7.92e-03 2.01e-04 8.20e-04 NC
Cs-135 caesium 55 2.0e10 8.4e08 1.2e09 100 8.28e-04 1.66e-05 2.02e-04 NC
Cs-136 caesium 55 3.1e02 1.3e01 1.9e01 90 1.44e-03 2.26e-04 8.10e-04 NC
Cs-137 caesium 55 2.6e05 1.1e04 1.6e04 100 5.52e-03 1.20e-04 8.60e-04 NC
Cs-138 caesium 55 5.4e-01 2.2e-02 3.2e-02 1 2.88e-05 NC NC NC
Ba-133 barium 56 9.4e04 3.9e03 5.6e03 100 3.72e-03 NC NC NC
Ba-137m barium 56 4.3e-02 1.8e-03 2.6e-03 0 NC NC NC NC
Ba-140 barium 56 3.1e02 1.3e01 1.8e01 89 6.12e-03 1.54e-04 1.18e-03 NC
La-140 lanthanum 57 4.0e01 1.7e00 2.4e00 48 1.32e-03 2.16e-04 2.60e-03 NC
Ce-141 cerium 58 7.8e02 3.3e01 4.7e01 96 3.84e-03 2.21e-05 1.17e-03 NC
Ce-144 cerium 58 6.8e03 2.8e02 4.1e02 99 4.32e-02 1.02e-04 8.90e-03 NC
Pr-144 praseodymium 59 2.9e-01 1.2e-02 1.7e-02 1 2.16e-05 NC NC NC
Pr-144m praseodymium 59 1.2e-01 5.0e-03 7.2e-03 1 NC NC NC NC
Pm-145 promethium 61 1.6e05 6.5e03 9.3e03 100 4.32e-03 NC NC NC
Pm-147 promethium 61 2.3e04 9.6e02 1.4e03 100 6.00e-03 9.40e-06 4.40e-04 NC
Sm-147 samarium 62 9.3e14 3.9e13 5.6e13 100 1.15e01 NC NC NC
Sm-151 samarium 62 7.9e05 3.3e04 4.7e04 100 4.80e-03 2.98e-06 1.33e-04 NC
Eu-152 europium 63 1.2e05 4.9e03 7.0e03 100 5.04e-02 1.13e-04 1.31e-03 NC
Eu-154 europium 63 7.7e04 3.2e03 4.6e03 100 6.36e-02 1.38e-04 2.36e-03 NC
Eu-155 europium 63 4.3e04 1.8e03 2.6e03 100 8.28e-03 2.04e-05 4.50e-04 NC
Gd-153 gadolinium 64 5.8e03 2.4e02 3.5e02 99 2.52e-03 NC NC NC
Tb-160 terbium 65 1.7e03 7.2e01 1.0e02 98 8.40e-03 NC NC NC
Ho-166m holmium 67 1.1e07 4.4e05 6.3e05 100 1.44e-01 NC NC NC
Tm-170 thulium 69 3.1e03 1.3e02 1.9e02 99 8.40e-03 NC NC NC
Yb-169 ytterbium 70 7.7e02 3.2e01 4.6e01 95 3.00e-03 7.10e-05 9.90e-04 NC
Hf-172 hafnium 72 1.6e04 6.8e02 9.8e02 100 3.84e-02 NC NC NC
Hf-181 hafnium 72 1.0e03 4.2e01 6.1e01 96 6.00e-03 NC NC NC
Ta-182 tantalum 73 2.8e03 1.1e02 1.7e02 99 1.20e-02 NC NC NC
W-187 tungsten 74 2.4e01 1.0e00 1.4e00 33 2.28e-04 NC NC NC
Ir-192 iridium 77 1.8e03 7.4e01 1.1e02 98 7.92e-03 1.02e-04 1.77e-03 NC
Au-198 gold 79 6.5e01 2.7e00 3.9e00 61 1.03e-03 NC NC NC
Hg-203 mercury 80 1.1e03 4.7e01 6.7e01 97 2.88e-03 NC NC NC
Tl-204 thallium 81 3.3e04 1.4e03 2.0e03 100 4.68e-04 NC NC NC
Pb-210 lead 82 1.9e05 8.1e03 1.2e04 100 6.72e00 6.32e-05 1.93e-02 NC
Bi-207 bismuth 83 3.3e05 1.4e04 2.0e04 100 6.72e-03 NC NC NC
A1.14
Bi-210 bismuth 83 1.2e02 5.0e00 7.2e00 76 1.12e-01 NC NC NC
Po-210 polonium 84 3.3e03 1.4e02 2.0e02 99 3.96e00 7.70e-03 3.54e-01 NC
Ra-226 radium 88 1.4e07 5.8e05 8.4e05 100 4.20e00 1.55e-03 3.18e-01 NC
Ac-227 actinium 89 1.9e05 7.9e03 1.1e04 100 2.64e02 NC NC NC
Ac-228 actinium 89 6.1e00 2.6e-01 3.7e-01 9 3.00e-02 NC NC NC
Th-227 thorium 90 4.5e02 1.9e01 2.7e01 92 1.02e01 1.91e-02 5.51e-01 NC
Th-228 thorium 90 1.7e04 7.0e02 1.0e03 100 4.80e01 3.07e-02 7.91e-01 NC
Th-230 thorium 90 6.7e08 2.8e07 4.0e07 100 1.20e02 9.80e-03 3.30e-01 NC
Th-231 thorium 90 2.6e01 1.1e00 1.5e00 34 3.72e-04 NC NC NC
Th-232 thorium 90 1.2e14 5.1e12 7.4e12 100 1.32e02 8.40e-03 2.78e-01 NC
Pa-231 protactinium 91 2.9e08 1.2e07 1.7e07 100 1.68e02 6.71e-03 3.51e-01 NC
Pa-233 protactinium 91 6.5e02 2.7e01 3.9e01 95 4.68e-03 NC NC NC
U-232 uranium 92 6.3e05 2.6e04 3.8e04 100 9.36e00 3.34e-03 3.74e-01 NC
U-233 uranium 92 1.4e09 5.8e07 8.4e07 100 4.32e00 NC NC NC
U-234 uranium 92 2.1e09 8.9e07 1.3e08 100 4.20e00 2.96e-03 3.34e-01 NC
U-235 uranium 92 6.2e12 2.6e11 3.7e11 100 3.72e00 2.80e-03 3.08e-01 NC
U-236 uranium 92 2.0e11 8.5e09 1.2e10 100 3.84e00 2.80e-03 3.14e-01 NC
U-238 uranium 92 3.9e13 1.6e12 2.3e12 100 3.48e00 2.61e-03 2.94e-01 NC
U-Depleted-Nat uranium 92 3.9e13 1.6e12 2.3e12 100 3.84e01 2.61e-03 2.94e-01 NC
U-Enriched uranium 92 2.1e09 8.9e07 1.3e08 100 4.30e01 2.96e-03 3.34e-01 NC
UF6 U-hexafluoride 0 0 0 0 0 8.65e-04 2.96e-03 0 0
Np-237 neptunium 93 1.9e10 7.8e08 1.1e09 100 2.76e01 7.32e-03 3.19e-01 NC
Np-239 neptunium 93 5.7e01 2.4e00 3.4e00 58 1.12e-03 3.70e-05 1.23e-03 NC
Pu-236 plutonium 94 2.5e04 1.0e03 1.5e03 100 4.80e01 NC NC NC
Pu-238 plutonium 94 7.7e05 3.2e04 4.6e04 100 5.52e01 8.30e-03 3.78e-01 NC
Pu-239 plutonium 94 2.1e08 8.8e06 1.3e07 100 6.00e01 7.90e-03 3.56e-01 NC
Pu-240 plutonium 94 5.7e07 2.4e06 3.4e06 100 6.00e01 7.90e-03 3.58e-01 NC
Pu-241 plutonium 94 1.3e05 5.3e03 7.6e03 100 1.08e00 1.06e-06 4.84e-05 NC
Pu-242 plutonium 94 3.3e09 1.4e08 2.0e08 100 5.76e01 7.30e-03 3.38e-01 NC
Am-241 americium 95 3.8e06 1.6e05 2.3e05 100 5.04e01 8.22e-03 3.70e-01 NC
Am-242m americium 95 1.3e06 5.5e04 8.0e04 100 4.44e01 NC NC NC
Am-243 americium 95 6.5e07 2.7e06 3.9e06 100 4.92e01 7.94e-03 3.55e-01 NC
Cm-242 curium 96 3.9e03 1.6e02 2.4e02 99 6.24e00 9.20e-03 4.08e-01 NC
Cm-243 curium 96 2.5e05 1.0e04 1.5e04 100 3.72e01 8.84e-03 3.93e-01 NC
Cm-244 curium 96 1.6e05 6.6e03 9.5e03 100 3.24e01 8.80e-03 3.92e-01 NC
Cm-245 curium 96 7.4e07 3.1e06 4.5e06 100 5.04e01 NC NC NC
Cf-252 californium 98 2.3e04 9.6e02 1.4e03 100 2.40e01 NC NC NC
RADIOLOGICAL NUCLIDE DATA (continued)
_____________________________________
11. EARLY PHASE DEPO.EXTNL.EXPOSURE RATE ECFg [(mGy/h)/(kBq/m3)]
12. EARLY PHASE DEPO.EXTNL.EDE DOSE RATE DCFg [(mSv/h)/(kBq/m2)]
13. DEPO.4-DAY DOSE EXT.& NON-ARID DCFepgna [(mSv/7d)/(kBq/m2)]
14. DEPO.4-DAY DOSE EXT.& ARID RSPN. DCFepga [(mSv/7d)/(kBq/m2)]
15. AIR IMMERSION EXTERNAL EDE DOSE RATE DCFa [((mSv/h)/(kBq/m3)]
16. INTERMEDIATE PHASE EFF.EXPOSURE PERIOD Tipeep [eff.hrs/1year]
17. INTERMD.PH.DCF DEPO 1st year NORMAL [(mSv in 1st y)/(kBq/m2)]
18. INTERMD.PH.DCF DEPO 1st month NON-ARID [(mSv in 1st mnt)/(kBq/m2)]
19. INTERMD.PH.DCF DEPO 2nd month NORMAL [(mSv 2nd mnt)/(kBq/m2)]
20. INTERMD.PH.DCF DEPO 50 y NORMAL [(mSv 50 y)/(kBq/m2)]
__________________________________________________________________
11 12 13 14 15 16 17 18 19 20
_____________________________________________________________________________________________________________________________________________________________________
H-3 0.0 0.0 NC NC 0.0 8501 NC NC NC NC
C-14 5.68e-11 4.57e-11 1.20e-07 1.14e-05 9.36e-09 8743 4.70e-06 5.03e-07 4.75e-07 1.01e-04
Na-22 7.41e-06 7.38e-06 8.93e-04 2.02e-03 3.67e-04 7675 3.08e-02 3.67e-03 3.39e-03 8.38e-02
Na-24 1.27e-05 1.29e-05 2.01e-04 4.85e-04 7.49e-04 22 1.98e-04 1.94e-04 0.0 1.98e-04
P-32 1.03e-08 3.07e-07 1.76e-06 7.34e-05 1.93e-06 494 5.89e-06 4.59e-06 1.01e-06 5.89e-06
A1.15
P-33 1.57e-10 1.31e-10 1.32e-07 1.15e-05 5.22e-08 878 7.11e-07 4.15e-07 1.73e-07 7.11e-07
S-35 5.93e-11 4.79e-11 1.38e-07 1.31e-05 1.12e-08 2855 2.04e-06 5.28e-07 3.93e-07 2.11e-06
Cl-36 2.37e-09 4.03e-08 1.48e-06 1.20e-04 5.98e-07 8744 5.76e-05 6.15e-06 5.81e-06 1.23e-03
K-40 5.15e-07 7.34e-07 6.29e-05 2.11e-04 2.85e-05 8744 2.44e-03 2.60e-04 2.46e-04 5.22e-02
K-42 9.38e-07 1.43e-06 1.21e-05 2.84e-05 5.33e-05 18 1.19e-05 1.19e-05 0.0 1.19e-05
Ca-45 1.63e-10 1.36e-10 3.74e-07 3.55e-05 5.51e-08 4435 8.05e-06 1.49e-06 1.24e-06 9.35e-06
Sc-46 6.81e-06 6.77e-06 8.01e-04 1.93e-03 3.37e-04 2755 1.14e-02 3.30e-03 2.23e-03 1.17e-02
Ti-44 7.76e-06 4.25e-07 9.63e-04 7.57e-03 1.69e-05 8680 3.81e-02 4.08e-03 3.88e-03 6.05e-01
V-48 9.81e-06 9.79e-06 1.02e-03 2.33e-03 4.90e-04 561 3.73e-03 2.76e-03 7.11e-04 3.73e-03
Cr-51 1.09e-07 1.07e-07 1.21e-05 2.76e-05 4.97e-06 957 6.95e-05 3.84e-05 1.71e-05 6.95e-05
Mn-54 2.86e-06 2.85e-06 3.44e-04 7.88e-04 1.38e-04 5995 9.54e-03 1.39e-03 1.23e-03 1.40e-02
Mn-56 5.57e-06 5.83e-06 1.50e-05 3.43e-05 2.94e-04 4 1.48e-05 1.48e-05 0.0 1.48e-05
Fe-55 0.0 0.0 1.46e-07 1.46e-05 0.0 7711 5.08e-06 6.04e-07 5.59e-07 1.42e-05
Co-58 3.53e-06 3.33e-06 NC NC 1.60e-04 2378 NC NC NC NC
Fe-59 3.59e-06 3.96e-06 4.53e-04 1.10e-03 2.02e-04 1537 3.59e-03 1.58e-03 9.38e-04 3.89e-03
Co-60 8.29e-06 8.28e-06 1.01e-03 3.45e-03 4.28e-04 8193 3.70e-02 4.17e-03 3.90e-03 1.66e-01
Ni-63 0.0 0.0 1.69e-07 1.69e-05 0.0 8712 6.57e-06 7.03e-07 6.64e-07 1.21e-04
Cu-64 6.60e-07 6.59e-07 8.70e-06 1.88e-05 3.06e-05 18 8.59e-06 8.60e-06 0.0 8.59e-06
Zn-65 1.95e-06 1.95e-06 2.35e-04 6.32e-04 9.79e-05 5447 6.00e-03 9.40e-04 8.16e-04 7.95e-03
Ga-68 3.32e-06 3.60e-06 NC NC 1.54e-04 2 NC NC NC NC
Ge-68 3.32e-06 2.37e-06 3.96e-04 1.13e-03 1.65e-04 5818 1.08e-02 1.61e-03 1.42e-03 1.53e-02
Se-75 1.33e-06 1.30e-06 1.58e-04 3.85e-04 6.05e-05 3639 2.86e-03 6.15e-04 4.88e-04 3.08e-03
Kr-85 9.31e-09 0.0 NC NC 9.17e-07 8467 NC NC NC NC
Kr-85m 5.36e-07 0.0 NC NC 2.46e-05 6 NC NC NC NC
Kr-87 2.58e-06 0.0 NC NC 1.42e-04 2 NC NC NC NC
Kr-88 8.22e-06 0.0 NC NC 3.50e-04 4 NC NC NC NC
Rb-86 3.28e-07 6.01e-07 3.53e-05 1.09e-04 1.78e-05 645 1.46e-04 1.00e-04 3.11e-05 1.46e-04
Rb-87 3.10e-10 2.63e-10 NC NC 1.19e-07 8744 NC NC NC NC
Rb-88 2.10e-06 2.67e-06 NC NC 1.20e-04 1 NC NC NC NC
Sr-89 8.01e-09 2.47e-07 3.06e-06 2.16e-04 1.57e-06 1734 2.95e-05 1.10e-05 6.88e-06 2.95e-05
Sr-90 1.00e-09 5.90e-09 7.20e-05 7.07e-03 3.54e-07 8640 2.84e-03 3.05e-04 2.89e-04 3.78e-02
Sr-91 2.39e-06 2.62e-06 3.40e-05 6.29e-05 1.18e-04 14 3.41e-05 3.38e-05 8.05e-08 3.41e-05
Y-90 1.88e-08 3.96e-07 1.25e-06 2.31e-05 2.85e-06 92 1.48e-06 1.48e-06 5.87e-10 1.48e-06
Y-91 2.03e-08 2.69e-07 4.90e-06 2.60e-04 2.24e-06 1995 5.30e-05 1.79e-05 1.19e-05 5.35e-05
Y-91m 1.85e-06 1.84e-06 1.60e-06 3.42e-06 8.53e-05 1 NC NC NC NC
Zr-93 0.0 0.0 1.75e-05 1.75e-03 0.0 8744 6.84e-04 7.28e-05 6.89e-05 1.55e-02
Zr-95 2.55e-06 2.53e-06 3.18e-04 7.88e-04 1.21e-04 2170 6.68e-03 1.38e-03 1.30e-03 6.81e-03
Nb-94 5.40e-06 5.36e-06 6.75e-04 3.68e-04 2.59e-04 8743 2.61e-02 2.80e-03 2.64e-03 5.59e-01
Nb-95 2.64e-06 2.62e-06 2.97e-04 6.79e-04 1.26e-04 1214 2.09e-03 9.98e-04 5.21e-04 2.09e-03
Mo-99 9.53e-07 6.41e-07 5.05e-05 1.23e-04 2.52e-05 95 6.05e-05 6.05e-04 3.08e-08 6.05e-05
Tc-99 2.75e-10 2.33e-10 4.86e-07 4.54e-05 1.03e-07 8744 1.89e-05 2.03e-06 1.92e-06 4.05e-04
Tc-99m 4.27e-07 4.10e-07 2.68e-06 5.74e-06 1.89e-05 9 2.65e-06 2.65e-06 5.75e-15 2.65e-06
Ru-103 1.63e-03 1.62e-06 1.86e-04 4.44e-04 7.49e-05 1355 1.44e-03 6.39e-04 3.56e-04 1.45e-03
Ru-105 2.71e-06 2.82e-06 1.37e-05 2.84e-05 1.28e-04 6 1.36e-05 1.36e-05 1.82e-12 1.36e-05
Rh-106 7.48e-07 1.24e-06 NC NC 3.82e-05 1 NC NC NC NC
Ru-106 7.48e-07 1.24e-06 1.15e-04 2.77e-03 3.82e-05 6324 3.35e-03 4.69e-04 4.19e-04 5.30e-03
Ag-110m 9.35e-06 9.29e-06 1.12e-03 2.90e-03 4.57e-04 5498 2.89e-02 4.51e-03 3.92e-03 3.86e-02
Cd-109 1.14e-07 8.11e-08 1.97e-05 6.35e-04 1.75e-06 6740 6.11e-04 8.09e-05 7.31e-05 1.08e-03
Cd-113m 9.28e-10 6.37e-09 8.33e-05 8.32e-03 3.26e-07 8525 3.19e-03 3.47e-04 3.26e-04 2.86e-02
In-114m 3.23e-07 3.11e-07 4.28e-05 5.38e-04 1.40e-05 1701 4.03e-04 1.52e-04 9.46e-05 4.05e-04
Sn-113 9.88e-07 7.06e-07 1.14e-04 2.93e-04 4.49e-05 3536 2.03e-03 4.64e-04 3.53e-04 2.18e-03
Sn-123 2.95e-08 2.34e-07 5.23e-06 1.81e-04 2.51e-06 3835 9.89e-05 2.05e-05 1.65e-05 1.09e-04
Sn-126 5.29e-06 1.09e-05 7.16e-04 3.40e-03 7.70e-04 8744 3.22e-02 3.15e-03 3.23e-03 6.97e-01
Sb-124 6.03e-06 6.12e-06 7.02e-04 1.72e-03 3.10e-04 2049 7.73e-03 2.56e-03 1.71e-03 7.81e-03
Sb-126 9.81e-06 9.79e-06 9.81e-04 2.17e-03 4.61e-04 429 2.92e-03 2.40e-03 4.24e-04 2.92e-03
Sb-126m 5.36e-06 5.58e-06 NC NC 2.52e-04 1 NC NC NC NC
Sb-127 2.38e-06 2.43e-06 1.65e-04 3.75e-04 1.12e-04 133 2.28e-04 2.26e-04 1.12e-06 2.28e-04
Sb-129 4.87e-06 4.93e-06 2.32e-05 5.03e-05 2.42e-04 6 2.31e-05 2.30e-05 4.79e-08 2.31e-05
Te-127 1.83e-08 3.71e-08 1.80e-07 5.12e-07 1.20e-06 13 1.77e-07 1.78e-07 0.0 1.78e-07
Te-127m 3.99e-08 3.08e-08 7.74e-06 1.22e-04 4.03e-07 3397 1.36e-04 3.07e-05 2.41e-05 1.45e-04
Te-129 2.12e-07 4.10e-07 2.56e-07 5.36e-07 1.03e-05 2 2.53e-07 2.53e-07 3.15e-16 2.53e-07
Te-129m 1.33e-07 2.05e-07 3.10e-05 1.91e-04 5.62e-06 1161 2.11e-04 1.03e-04 5.27e-05 2.11e-04
Te-131 1.45e-06 1.71e-06 8.84e-07 1.63e-06 6.91e-05 0 NC 1.14e-06 3.73e-08 1.18e-06
A1.16
Te-131m 4.83e-06 4.82e-06 1.72e-04 3.58e-04 2.36e-04 43 1.99e-04 1.96e-04 3.17e-06 1.99e-04
Te-132 8.04e-07 8.89e-06 5.31e-04 6.12e-04 4.21e-04 113 6.89e-04 6.87e-04 1.13e-06 6.89e-04
I-125 1.51e-07 1.13e-07 1.86e-05 1.49e-04 1.34e-06 2047 2.08e-04 6.87e-05 4.60e-05 2.09e-04
I-129 9.10e-08 7.02e-08 2.04e-05 9.61e-04 1.01e-06 8744 7.95e-04 8.50e-05 8.03e-05 1.70e-02
I-131 1.33e-06 1.31e-06 1.21e-04 3.92e-04 6.08e-05 278 2.61e-04 2.42e-04 1.72e-05 2.61e-04
I-132 7.80e-06 7.92e-06 1.87e-05 4.10e-05 3.78e-04 3 1.85e-05 1.85e-05 0.0 1.85e-05
I-133 2.11e-06 2.22e-06 4.55e-05 1.04e-04 9.94e-05 30 4.51e-05 4.51e-05 0.0 4.51e-05
I-134 8.93e-06 9.11e-06 8.16e-06 1.80e-05 4.39e-04 1 8.05e-06 8.06e-06 0.0 8.05e-06
I-135 5.40e-06 5.29e-06 3.58e-05 8.35e-05 2.71e-04 10 3.54e-05 3.53e-05 0.0 3.54e-05
Xe-131m 7.27e-08 0.0 NC NC 1.33e-06 411 NC NC NC NC
Xe-133 1.63e-07 0.0 NC NC 5.00e-06 181 NC NC NC NC
Xe-133m 1.44e-07 0.0 NC NC 4.58e-06 76 NC NC NC NC
Xe-135 8.54e-07 0.0 NC NC 4.00e-05 13 NC NC NC NC
Xe-135m 1.50e-06 0.0 NC NC 6.67e-05 1 NC NC NC NC
Xe-138 3.63e-06 0.0 NC NC 1.96e-04 1 NC NC NC NC
Cs-134 5.36e-06 5.33e-06 6.47e-04 1.65e-03 2.54e-04 7426 2.17e-02 2.65e-03 2.44e-03 5.11e-02
Cs-135 1.17e-10 9.68e-11 NC NC 3.42e-08 8744 NC NC NC NC
Cs-136 7.37e-06 7.31e-06 7.46e-04 1.67e-03 3.58e-04 453 2.32e-03 1.87e-03 3.63e-04 2.32e-03
Cs-137 2.07e-06 1.98e-06 2.38e-04 7.00e-04 9.18e-05 8643 9.14e-03 9.86e-04 9.30e-04 1.24e-01
Cs-138 7.73e-06 8.14e-06 NC NC 4.14e-04 1 NC NC NC NC
Ba-133 1.40e-06 1.34e-06 1.69e-04 3.90e-04 5.83e-05 8467 6.38e-03 7.00e-04 6.58e-04 4.78e-02
Ba-137m 2.07e-06 2.08e-06 NC NC 9.68e-05 1 NC NC NC NC
Ba-140 6.35e-07 6.84e-07 5.93e-04 6.81e-04 2.91e-05 442 2.52e-03 1.98e-03 4.36e-04 2.52e-03
La-140 7.62e-06 7.78e-06 3.01e-04 6.93e-04 4.00e-04 58 3.14e-04 3.14e-04 1.19e-09 3.14e-04
Ce-141 2.60e-07 2.49e-07 2.96e-05 1.06e-04 1.12e-05 1123 1.95e-04 9.79e-05 4.88e-05 1.95e-04
Ce-144 2.01e-07 6.55e-07 4.47e-05 2.07e-03 1.23e-05 5790 1.21e-03 1.81e-04 1.59e-04 1.70e-03
Pr-144 1.33e-07 5.87e-07 4.02e-08 8.92e-08 9.54e-06 1 NC 3.97e-08 0.0 3.97e-08
Pr-144m 4.59e-08 3.78e-08 2.23e-08 2.52e-08 7.92e-07 1 NC 2.22e-08 0.0 2.22e-08
Pm-145 1.15e-07 9.40e-08 1.54e-05 1.87e-04 1.98e-06 8575 5.89e-04 6.42e-05 6.04e-05 6.22e-03
Pm-147 1.20e-10 1.01e-10 2.14e-06 2.13e-04 3.12e-08 7684 NC 8.86e-06 8.19e-06 NC
Sm-147 0.0 0.0 NC NC 0.0 8744 7.46e-05 NC NC 2.04e-04
Sm-151 1.77e-11 1.27e-11 1.63e-06 1.63e-04 8.86e-11 8710 6.35e-05 6.81e-06 6.43e-06 1.15e-03
Eu-152 3.88e-06 3.89e-06 4.81e-04 2.24e-03 1.90e-04 8520 1.82e-02 1.99e-03 1.87e-03 1.62e-01
Eu-154 4.20e-06 4.21e-06 5.23e-04 2.68e-03 2.07e-04 8408 1.95e-02 2.16e-03 2.03e-03 1.29e-01
Eu-155 2.08e-07 1.93e-07 2.73e-05 2.75e-04 7.70e-06 8160 9.97e-04 1.13e-04 1.06e-04 4.27e-03
Gd-153 3.74e-07 3.32e-07 4.58e-05 2.10e-04 1.12e-05 5420 1.17e-03 1.84e-04 1.60e-04 1.54e-03
Tb-160 3.81e-06 3.82e-06 4.47e-04 1.11e-03 1.87e-04 2423 5.68e-03 1.67e-03 1.18e-03 5.78e-03
Ho-166m 6.00e-06 5.94e-06 7.66e-04 5.78e-03 2.82e-04 8741 2.97e-02 3.17e-03 3.00e-03 6.27e-01
Tm-170 2.09e-08 9.50e-08 3.87e-06 1.45e-04 1.32e-06 3823 7.30e-05 1.51e-05 1.22e-05 8.03e-05
Yb-169 1.07e-06 1.00e-06 1.20e-04 2.81e-04 4.07e-05 1104 7.84e-04 3.97e-04 1.96e-04 7.84e-04
Hf-172 3.99e-07 3.57e-07 NC NC 1.22e-05 7306 NC NC NC NC
Hf-181 1.93e-06 1.89e-06 2.21e-04 5.48e-04 8.71e-05 1461 1.83e-03 7.67e-04 4.44e-04 1.83e-03
Ta-182 4.34e-06 4.32e-06 5.16e-04 1.38e-03 2.16e-04 3528 9.05e-03 2.00e-03 1.58e-03 9.73e-03
W-187 1.56e-06 1.68e-06 4.07e-05 8.80e-05 7.67e-05 34 4.05e-05 4.05e-05 7.21e-05 4.05e-05
Ir-192 2.83e-06 2.80e-06 3.33e-04 8.60e-04 1.30e-04 2474 4.32e-03 1.24e-03 8.88e-04 4.41e-03
Au-198 1.41e-06 1.47e-06 7.92e-05 1.78e-04 6.52e-05 93 9.35e-05 9.34e-05 3.90e-08 9.35e-05
Hg-203 8.18e-07 7.99e-07 9.42e-05 2.40e-04 3.74e-05 1603 8.43e-04 3.32e-04 2.01e-04 8.46e-04
Tl-204 5.22e-09 3.89e-08 7.59e-07 1.43e-05 6.16e-07 7989 2.73e-05 3.14e-06 2.92e-06 9.57e-05
Pb-210 8.75e-09 7.67e-09 7.41e-04 7.39e-02 1.61e-07 8609 3.84e-02 3.22e-03 3.30e-03 5.70e-01
Bi-207 5.22e-06 5.22e-06 6.32e-04 1.50e-03 2.53e-04 8664 2.42e-02 2.62e-03 2.47e-03 3.43e-01
Bi-210 3.70e-09 1.26e-07 7.12e-06 6.83e-04 9.29e-07 173 3.65e-04 6.64e-05 6.05e-05 4.08e-04
Po-210 2.92e-11 2.91e-11 5.02e-04 5.02e-02 1.40e-09 4014 9.92e-03 1.98e-03 1.61e-03 1.11e-02
Ra-226 2.27e-08 2.20e-08 7.67e-04 4.70e-02 1.02e-06 8742 4.51e-02 4.33e-03 4.61e-03 9.78e-01
Ac-227 5.54e-10 5.08e-10 3.64e-01 3.64e+01 1.84e-08 8606 1.41e+01 1.52e+00 1.43e+00 1.66e+02
Ac-228 3.27e-06 3.38e-06 2.19e-05 1.35e-04 1.62e-04 9 2.57e-04 5.02e-05 2.68e-05 5.49e-04
Th-227 3.67e-07 3.53e-07 8.53e-04 7.77e-02 1.59e-05 647 5.35e-03 3.18e-03 1.42e-03 5.35e-03
Th-228 8.29e-09 7.67e-09 1.88e-02 1.85e+00 2.92e-07 7335 6.43e-01 7.90e-02 7.31e-02 1.44e+00
Th-230 2.65e-09 2.29e-09 1.77e-02 1.77e+00 5.33e-08 8744 6.92e-01 7.40e-02 6.99e-02 1.48e+01
Th-231 6.53e-08 5.58e-08 NC NC 1.65e-06 37 NC NC NC NC
Th-232 1.94e-09 1.64e-09 8.92e-02 8.92e+00 2.61e-08 8744 3.49e+00 3.72e-01 3.52e-01 8.68e+01
Pa-231 1.44e-07 1.36e-07 6.96e-02 6.96e+00 5.65e-06 8744 2.92e+00 2.92e-01 2.80e-01 1.99e+02
Pa-233 6.88e-07 6.70e-07 NC NC 3.08e-05 933 NC NC NC NC
U-232 3.56e-09 2.91e-09 3.58e-02 3.58e+00 4.21e-08 8744 1.50e+00 1.51e-01 1.44e-01 3.65e+01
A1.17
U-233 2.53e-09 2.16e-09 7.34e-03 7.34e-01 5.11e-08 8744 2.86e-01 3.06e-02 2.89e-02 6.35e+00
U-234 2.64e-09 2.11e-09 7.18e-03 7.18e-01 2.20e-08 8744 2.81e-01 2.99e-02 2.83e-02 6.00e+00
U-235 5.22e-07 5.04e-07 6.76e-03 6.69e-01 2.33e-05 8702 2.64e-01 2.82e-02 2.66e-02 5.65e+00
U-236 2.29e-09 1.81e-09 6.85e-03 6.85e-01 1.39e-08 8744 NC 2.86e-02 2.70e-02 5.73e+00
U-238 1.94e-09 1.52e-09 6.42e-03 6.42e-01 9.00e-09 8744 2.51e-01 2.68e-02 2.53e-02 5.38e+00
U-Depleted-Nat 1.94e-09 1.39e-09 6.42e-03 6.42e-01 1.23e-08 8744 2.51e-01 2.68e-02 2.53e-02 5.38e+00
U-Enriched 2.64e-09 1.88e-09 7.18e-03 7.18e-01 2.74e-08 8744 2.81e-01 2.99e-02 2.83e-02 6.00e+00
UF6 2.64e-09 1.88e-09 1.49e-04 1.48e-02 2.74e-08 0 NC 6.21e-04 5.87e-04 1.27e-01
Np-237 1.01e-07 9.07e-08 2.94e-02 2.94e+00 3.19e-06 8744 1.15e+00 1.23e-01 1.16e-01 2.46e+01
Np-239 5.75e-07 5.54e-07 2.95e-05 6.79e-05 2.50e-05 81 3.35e-05 3.34e-05 1.17e-08 3.49e-05
Pu-236 3.46e-09 2.65e-09 7.87e-03 7.87e-01 1.68e-08 7762 2.81e-01 3.26e-02 3.03e-02 2.08e+00
Pu-238 2.96e-09 2.25e-09 2.13e-02 2.13e+00 1.26e-08 8709 8.30e-01 8.89e-02 8.40e-02 1.50e+01
Pu-239 1.29e-09 1.02e-09 2.33e-02 2.33e+00 1.25e-08 8744 9.11e-01 9.73e-02 9.20e-02 1.95e+01
Pu-240 2.83e-09 2.16e-09 2.33e-02 2.33e+00 1.23e-08 8743 9.11e-01 9.73e-02 9.20e-02 1.95e+01
Pu-241 6.81e-12 6.19e-12 4.48e-04 4.48e-02 2.28e-10 8537 1.78e-02 1.87e-03 1.78e-03 5.35e-01
Pu-242 2.35e-09 1.79e-09 2.24e-02 2.24e+00 1.04e-08 8744 8.73e-01 9.32e-02 8.81e-02 1.87e+01
Am-241 9.70e-08 8.39e-08 2.42e-02 2.41e+00 2.43e-06 8737 9.41e-01 1.01e-01 9.52e-02 1.95e+01
Am-242m 1.07e-08 8.14e-09 2.32e-02 2.32e+00 8.96e-08 8724 9.16e-01 9.69e-02 9.18e-02 1.81e+01
Am-243 1.89e-07 1.72e-07 2.40e-02 2.39e+00 6.66e-06 8743 9.38e-01 1.00e-01 9.47e-02 2.01e+01
Cm-242 3.37e-09 2.53e-09 9.27e-04 9.27e-02 1.45e-08 4443 2.19e-02 3.72e-03 3.14e-03 9.73e-02
Cm-243 4.41e-07 4.25e-07 1.67e-02 1.67e+00 1.91e-05 8638 6.46e-01 6.98e-02 6.58e-02 8.59e+00
Cm-244 3.10e-09 2.32e-09 1.35e-02 1.35e+00 1.22e-08 8578 5.16e-01 5.62e-02 5.29e-02 5.54e+00
Cm-245 3.07e-07 2.90e-07 2.48e-02 2.47e+00 1.26e-05 8743 9.68e-01 1.03e-01 9.77e-02 2.12e+01
Cf-252 2.55e-09 1.89e-09 8.52e-03 8.52e-01 1.31e-08 7690 2.97e-01 3.52e-02 3.26e-02 8.14e-01
RADIOLOGICAL NUCLIDE DATA (continued)
_____________________________________
21. ISOTOPE/Cs-137 RATIO FOR REACTOR CORE DAMAGE ACCIDENTS 1 hr
22. ISOTOPE/Cs-137 RATIO FOR REACTOR CORE DAMAGE ACCIDENTS 6 hrs
23. ISOTOPE/Cs-137 RATIO FOR REACTOR CORE DAMAGE ACCIDENTS 12 hrs
24. ISOTOPE/Cs-137 RATIO FOR REACTOR CORE DAMAGE ACCIDENTS 24 hrs
25. ISOTOPE/Cs-137 RATIO FOR REACTOR CORE DAMAGE ACCIDENTS 3 d
26. ISOTOPE/Cs-137 RATIO FOR REACTOR CORE DAMAGE ACCIDENTS 7 d
27. ISOTOPE/Cs-137 RATIO FOR REACTOR CORE DAMAGE ACCIDENTS 15 d
28. ISOTOPE/Cs-137 RATIO FOR REACTOR CORE DAMAGE ACCIDENTS 30 d
29. INTERMD.PH.DCF INHL.RESPND.MAT.DCFipa [(mSv 1st mnt)/(kBq/m3)]
30. INTERMD.PH.DCF SKIN DOSE FROM DEPO [(mSv in 1st y)/(kBq/m2)]
__________________________________________________________________
21 22 23 24 25 26 27 28 29 30
_____________________________________________________________________________________________________________________________________________________________________
H-3 NC NC NC NC NC NC NC NC 2.96e-02 NC
C-14 NC NC NC NC NC NC NC NC 4.86e-01 NC
Na-22 NC NC NC NC NC NC NC NC 1.77e+00 NC
Na-24 NC NC NC NC NC NC NC NC 8.48e-03 NC
P-32 NC NC NC NC NC NC NC NC 1.90e+00 NC
P-33 NC NC NC NC NC NC NC NC 3.69e-01 NC
S-35 NC NC NC NC NC NC NC NC 5.13e-01 NC
Cl-36 NC NC NC NC NC NC NC NC 5.11e+00 NC
K-40 NC NC NC NC NC NC NC NC 2.88e+00 NC
K-42 NC NC NC NC NC NC NC NC 7.84e-03 NC
Ca-45 NC NC NC NC NC NC NC NC 1.45e+00 NC
Sc-46 NC NC NC NC NC NC NC NC 6.12e+00 NC
Ti-44 NC NC NC NC NC NC NC NC 2.37e+02 NC
V-48 NC NC NC NC NC NC NC NC 1.34e+00 NC
Cr-51 NC NC NC NC NC NC NC NC 5.48e-02 NC
Mn-54 NC NC NC NC NC NC NC NC 1.51e+00 NC
Mn-56 NC NC NC NC NC NC NC NC 4.54e-04 NC
Fe-55 NC NC NC NC NC NC NC NC 6.20e-01 NC
A1.18
Co-58 NC NC NC NC NC NC NC NC 2.20e+00 1.20e-01
Fe-59 NC NC NC NC NC NC NC NC 2.76e+00 NC
Co-60 NC NC NC NC NC NC NC NC 5.07e+01 4.20e-01
Ni-63 NC NC NC NC NC NC NC NC 7.23e-01 NC
Cu-64 NC NC NC NC NC NC NC NC 1.64e-03 NC
Zn-65 NC NC NC NC NC NC NC NC 4.56e+00 NC
Ga-68 NC NC NC NC NC NC NC NC 7.32e-05 NC
Ge-68 NC NC NC NC NC NC NC NC 1.16e+01 NC
Se-75 NC NC NC NC NC NC NC NC 1.81e+00 NC
Kr-85 NC NC NC NC NC NC NC NC 1.42e-04 NC
Kr-85m NC NC NC NC NC NC NC NC 8.16e-07 NC
Kr-87 NC NC NC NC NC NC NC NC 7.72e-07 NC
Kr-88 NC NC NC NC NC NC NC NC 4.11e-06 NC
Rb-86 NC NC NC NC NC NC NC NC 9.31e-01 6.30e01
Rb-87 NC NC NC NC NC NC NC NC 7.54e-01 NC
Rb-88 NC NC NC NC NC NC NC NC 1.16e-05 NC
Sr-89 2.4e00 2.4e00 2.4e00 2.4e00 2.3e00 2.2e00 2.0e00 1.6e-01 7.92e+00 1.50e02
Sr-90 1.0e-01 1.0e-01 1.0e-01 1.0e-01 1.0e-01 1.0e-01 1.0e-01 1.0e-01 3.02e+02 1.20e01
Sr-91 2.60e00 1.80e00 1.20e00 5.00e-01 0 0 0 0 7.37e-03 NC
Y-90 0 0 0 0 1.00e-01 1.00e-01 1.00e-01 1.00e-01 2.52e-01 2.20e02
Y-91 2.00e-01 2.00e-01 2.00e-01 2.00e-01 2.00e-01 2.00e-01 2.00e-01 2.00e-01 9.58e+00 1.60e02
Y-91m NC NC NC NC NC NC NC NC 1.41e-05 NC
Zr-93 NC NC NC NC NC NC NC NC 7.48e+01 NC
Zr-95 3.0e-01 3.0e-01 3.0e-01 3.0e-01 3.0e-01 2.0e-01 2.0e-01 2.0e-01 4.65e+00 7.20e-01
Nb-94 NC NC NC NC NC NC NC NC 9.66e+01 NC
Nb-95 3.0e-01 3.0e-01 3.0e-01 3.0e-01 3.0e-01 3.0e-01 3.0e-01 2.0e-01 1.02e+00 6.10e-01
Mo-99 1.1e00 1.0e00 1.0e00 8.0e-01 5.0e-01 2.0e-01 0.0 0.0 1.22e-01 4.40e00
Tc-99 NC NC NC NC NC NC NC NC 1.94e+00 NC
Tc-99m 1.0e00 9.0e-01 9.0e-01 8.0e-01 5.0e-01 2.0e-01 0.0 0.0 9.15e-05 7.70e-03
Ru-103 7.0e-01 7.0e-01 7.0e-01 7.0e-01 7.0e-01 7.0e-01 6.0e-01 4.0e-01 1.62e+00 6.80e-01
Ru-105 4.0e-01 2.0e-01 1.0e-01 0.0 0.0 0.0 0.0 0.0 9.44e-04 NC
Rh-106 NC NC NC NC NC NC NC NC NC NC
Ru-106 2.0e-01 2.0e-01 2.0e-01 2.0e-01 2.0e-01 2.0e-01 2.0e00 2.0e-01 1.08e+02 6.40e-01
Ag-110m NC NC NC NC NC NC 0.0 NC 1.80e+01 NC
Cd-109 NC NC NC NC NC NC NC NC 2.61e+01 NC
Cd-113m NC NC NC NC NC NC NC NC 3.55e+02 NC
In-114m NC NC NC NC NC NC NC NC 1.69e+01 NC
Sn-113 NC NC NC NC NC NC NC NC 2.27e+00 NC
Sn-123 NC NC NC NC NC NC NC NC 7.00e+00 NC
Sn-126 NC NC NC NC NC NC NC NC 2.32e+01 NC
Sb-124 NC NC NC NC NC NC NC NC 4.96e+00 NC
Sb-126 NC NC NC NC NC NC NC NC 1.33e+00 NC
Sb-126m NC NC NC NC NC NC NC NC 5.02e-06 NC
Sb-127 8.0e-01 7.0e-01 7.0e-01 7.0e-01 5.0e-01 2.0e-01 1.0e-01 0.0 2.59e-01 NC
Sb-129 3.6e00 1.6e00 6.0e-01 1.0e-01 0.0 0.0 0.0 0.0 1.30e-03 NC
Te-127 8.0e-01 8.0e-01 8.0e-01 7.0e-01 6.0e-01 3.0e-01 2.0e-01 1.0e-01 1.39e-03 1.00e00
Te-127m 1.0e-01 1.0e-01 1.0e-01 1.0e-01 1.0e-01 1.0e-01 1.0e-01 1.0e-01 4.56e+00 7.80e-01
Te-129 3.8e00 2.2e00 1.1e00 5.0e-01 4.0e-01 3.0e-01 3.0e-01 2.0e-01 4.85e-05 5.00e-01
Te-129m 7.0e-01 7.0e-01 7.0e-01 7.0e-01 6.0e-01 6.0e-01 5.0e-01 4.0e-01 4.16e+00 3.40e01
Te-131 NC NC NC NC NC NC NC NC 9.29e-05 NC
Te-131m 1.6e00 1.4e00 1.3e00 1.0e00 3.0e-01 0.0 0.0 0.0 8.97e-02 2.90e-01
Te-132 14.2e00 14.5e00 13.8e00 12.4e00 8.1e00 3.5e00 6.0e-01 0.0 3.44e-01 5.40e-03
I-125 NC NC NC NC NC NC NC NC 4.76e+00 NC
I-129 NC NC NC NC NC NC NC NC 4.04e+01 NC
I-131 24.2e00 24.8e00 24.3e00 23.2e00 19.6e00 3.9 7.0e00 1.9e00 2.74e+00 8.50e-01
I-132 30.4e00 18.2e00 14.7e00 12.8e00 8.3e00 3.6e00 7.0e-01 0.0 4.09e-04 5.00e01
I-133 49.0e00 41.5e00 34.0e00 22.8e00 4.6e00 2.0e-01 0.0 0.0 5.68e-02 NC
I-134 25.7e00 5.0e-01 0.0 0.0 0.0 0.0 0.0 0.0 5.38e-05 NC
I-135 40.2e00 23.8e00 12.7e00 3.6e00 0.0 0.0 0.0 0.0 3.79e-03 NC
Xe-131m NC NC NC NC NC NC NC NC NC NC
Xe-133 NC NC NC NC NC NC NC NC 9.23e-05 NC
Xe-133m NC NC NC NC NC NC NC NC NC NC
Xe-135 NC NC NC NC NC NC NC NC 8.92e-06 NC
A1.19
Xe-135m NC NC NC NC NC NC NC NC NC NC
Xe-138 NC NC NC NC NC NC NC NC NC NC
Cs-134 1.6e00 1.6e00 1.6e00 1.6e00 1.6e00 1.6e00 1.6e00 1.6e00 1.06e+01 2.60e01
Cs-135 NC NC NC NC NC NC NC NC 1.06e+00 NC
Cs-136 6.0e-01 6.0e-01 6.0e-01 6.0e-01 5.0e-01 4.0e-01 3.0e-01 1.0e-01 8.56e-01 1.40e-01
Cs-137 1.0e00 1.0e00 1.0e00 1.0e00 1.0e00 1.0e00 1.0e00 1.0e00 7.44e+00 2.10e01
Cs-138 NC NC NC NC NC NC NC NC 2.54e-05 NC
Ba-133 NC NC NC NC NC NC NC NC 1.81e+00 NC
Ba-137m NC NC NC NC NC NC NC NC NC NC
Ba-140 5.4e00 5.4e00 5.3e00 4.2e00 4.6e00 3.7e00 2.4e00 1.1e00 4.30e-01 9.10e00
La-140 4.0e-01 8.0e-01 1.2e00 2.0e00 3.6e00 4.0e00 2.8e00 1.2e00 9.12e-02 1.20e01
Ce-141 1.3e00 1.3e00 1.3e00 1.2e00 1.2e00 1.1e00 9.0e-01 7.0e-01 1.54e+00 6.60e-01
Ce-144 7.0e-01 7.0e-01 7.0e00 7.0e-01 7.0e-01 7.0e-01 7.0e-01 7.0e-01 8.40e+01 8.70e-01
Pr-144 NC NC NC NC NC NC NC NC 5.82e-06 NC
Pr-144m NC NC NC NC NC NC NC NC NC NC
Pm-145 NC NC NC NC NC NC NC NC 7.09e+00 NC
Pm-147 NC NC NC NC NC NC NC NC 9.04e+00 NC
Sm-147 NC NC NC NC NC NC NC NC 1.74e+04 NC
Sm-151 NC NC NC NC NC NC NC NC 6.98e+00 NC
Eu-152 NC NC NC NC NC NC NC NC 5.14e+01 NC
Eu-154 NC NC NC NC NC NC NC NC 6.64e+01 NC
Eu-155 NC NC NC NC NC NC NC NC 9.60e+00 NC
Gd-153 NC NC NC NC NC NC NC NC 5.31e+00 NC
Tb-160 NC NC NC NC NC NC NC NC 5.06e+00 NC
Ho-166m NC NC NC NC NC NC NC NC 1.80e+02 NC
Tm-170 NC NC NC NC NC NC NC NC 5.66e+00 NC
Yb-169 NC NC NC NC NC NC NC NC 1.38e+00 NC
Hf-172 NC NC NC NC NC NC NC NC 7.30e+01 NC
Hf-181 NC NC NC NC NC NC NC NC 2.84e+00 NC
Ta-182 NC NC NC NC NC NC NC NC 9.54e+00 NC
W-187 NC NC NC NC NC NC NC NC 6.90e-03 NC
Ir-192 NC NC NC NC NC NC NC NC 5.72e+00 NC
Au-198 NC NC NC NC NC NC NC NC 9.91e-02 NC
Hg-203 NC NC NC NC NC NC NC NC 1.38e+00 NC
Tl-204 NC NC NC NC NC NC NC NC 5.56e-01 NC
Pb-210 NC NC NC NC NC NC NC NC 3.16e+03 NC
Bi-207 NC NC NC NC NC NC NC NC 4.66e+00 NC
Bi-210 NC NC NC NC NC NC NC NC 1.08e+01 NC
Po-210 NC NC NC NC NC NC NC NC 2.03e+03 NC
Ra-226 NC NC NC NC NC NC NC NC 2.00e+03 NC
Ac-227 NC NC NC NC NC NC NC NC 1.56e+06 NC
Ac-228 NC NC NC NC NC NC NC NC 8.82e-01 NC
Th-227 NC NC NC NC NC NC NC NC 2.28e+03 NC
Th-228 NC NC NC NC NC NC NC NC 7.84e+04 NC
Th-230 NC NC NC NC NC NC NC NC 7.59e+04 NC
Th-231 NC NC NC NC NC NC NC NC 1.05e-02 NC
Th-232 NC NC NC NC NC NC NC NC 3.82e+05 NC
Pa-231 NC NC NC NC NC NC NC NC 2.99e+05 NC
Pa-233 NC NC NC NC NC NC NC NC 1.55e+00 NC
U-232 NC NC NC NC NC NC NC NC 2.86e+04 NC
U-233 NC NC NC NC NC NC NC NC 2.92e+04 NC
U-234 NC NC NC NC NC NC NC NC 2.76e+04 NC
U-235 NC NC NC NC NC NC NC NC 2.76e+04 NC
U-236 NC NC NC NC NC NC NC NC 3.09e+04 NC
U-238 NC NC NC NC NC NC NC NC 6.22e-01 NC
U-Depleted-Nat NC NC NC NC NC NC NC NC 1.54e+05 NC
U-Enriched NC NC NC NC NC NC NC NC 3.09e+04 NC
UF6 0 0 0 0 0 0 0 0 0 0
Np-237 NC NC NC NC NC NC NC NC 1.26e+05 NC
Np-239 13.8e00 13.0e00 12.0e00 10.4e00 5.8e00 1.8 2.0e-01 0.0 6.62e-02 3.40e-02
Pu-236 NC NC NC NC NC NC NC NC 3.34e+04 NC
Pu-238 NC NC NC NC NC NC NC NC 9.14e+04 .00
Pu-239 NC NC NC NC NC NC NC NC 1.00e+05 .00
A1.20
Pu-240 NC NC NC NC NC NC NC NC 1.00e+05 .00
Pu-241 NC NC NC NC NC NC NC NC 1.92e+03 .00
Pu-242 NC NC NC NC NC NC NC NC 9.57e+04 NC
Am-241 NC NC NC NC NC NC NC NC 1.03e+05 4.60e-02
Am-242m NC NC NC NC NC NC NC NC 9.92e+04 NC
Am-243 NC NC NC NC NC NC NC NC 1.03e+05 NC
Cm-242 NC NC NC NC NC NC NC NC 3.78e+03 .00
Cm-243 NC NC NC NC NC NC NC NC 7.15e+04 NC
Cm-244 NC NC NC NC NC NC NC NC 5.77e+04 0
Cm-245 NC NC NC NC NC NC NC NC 1.06e+05 NC
Cf-252 NC NC NC NC NC NC NC NC 3.62e+04 NC
RADIOLOGICAL NUCLIDE DATA (continued)
_____________________________________
31. COW TRANSFER FACTOR [(kBq/L)/(kBq/d)]
32. INGESTION CRITICAL ORGAN
33. CHILD INGESTION DOSE CONVERSION FACTOR DCFingch [mSv/kBq]
34. INFANT INGESTION DOSE CONVERSION FACTOR DCFingch [mSv/kBq]
35. INFANT INGESTION CEDE CONVERSION FACTOR [mSv/kBq]
36. ISOTOPE SPECIFIC ACTIVITY [Ci/g]
37. LWR TYPICAL CORE INVENTORY [Ci/MWe]
38. BWR TYPICAL COOLANT CONTAMINATION [Ci/g]
39. PWR TYPICAL COOLANT CONTAMINATION [Ci/g]
40. LWR CORE RELEASE FRACTIONS AT 650 C
__________________________________________________________________
31 32 33 34 35 36 37 38 39 40
_____________________________________________________________________________________________________________________________________________________________________
H-3 1.4e-02 All/1 1.90e-05 4.10e-05 1.60e-05 9.729000e3 0 0.99999997e-8 0.99999999e-6 0
C-14 1.5e-02 All/1 7.70e-04 1.50e-03 5.60e-03 4e0 0 0 0 0
Na-22 3.5e-02 Bone-S/2 1.10e-02 2.70e-02 3.10e-03 6.216000e3 0 0 0 0
Na-24 3.5e-02 Stomch/2 2.50e-03 6.60e-03 3.70e-04 2.44e01 1.7e01 8.648648e6 0 0
P-32 1.6e-02 Bone-M/2 1.90e-02 5.70e-02 2.10e-03 2.972970e5 0 0 0 0
P-33 1.6e-02 NC NC NC NC 1.567560e5 0 0 0 0
S-35 NC LLI/2 1.30e-03 4.00e-03 1.20e-04 4.324300e4 0 0 0 0
Cl-36 NC Stomch/2 2.60e-03 7.80e-03 8.20e-04 3.243243e-2 0 0 0 0
K-40 7.2e-03 NC NC NC NC 7.027027e-6 0 0 0 0
K-42 7.2e-03 Stomch/2 4.20e-03 1.20e-02 2.90e-04 5.945945e6 0 0 0 0
Ca-45 1.1e-02 Bone-S/2 1.20e-02 3.40e-02 8.10e-04 1.783700e4 0 0 0 0
Sc-46 NC LLI/2 2.20e-02 5.70e-02 1.50e-03 3.513500e4 0 0 0 0
Ti-44 NC LLI/2 8.40e-02 2.40e-01 5.70e-03 1.720000e2 0 0 0 0
V-48 NC LLI/2 2.80e-02 7.20e-02 2.10e-03 1.675670e5 0 0 0 0
Cr-51 2.0e-03 LLI/2 6.90e-04 1.90e-03 3.90e-05 9.189100e4 0 0 0 0
Mn-54 8.4e-05 LLI/2 4.00e-03 8.60e-03 7.20e-04 7.837000e3 0 0.69999997e-10 0.15999997e-8 0
Mn-56 8.4e-05 ULI/2 3.10e-03 8.90e-03 2.50e-04 2.162162e7 0 0 0 0
Fe-55 5.9e-05 Spleen/2 1.00e-03 3.00e-03 1.60e-04 2.405000e3 0 0 0 0
Co-58 2.0e-03 LLI/2 1.40e-01 3.20e-01 7.30e-01 3.243200e4 0 0.19999997e-9 0.45945943e-8 0
Fe-59 5.9e-05 NC 1.80e-02 4.90e-02 1.80e-03 4.864800e4 0 0 0 0
Co-60 2.0e-03 LLI/2 2.50e-02 5.90e-02 7.00e-03 1.135000e3 0 0.39999997e-9 0.5297297e-9 0
Ni-63 1.0e-02 LLI/2 2.10e-03 6.20e-03 1.50e-04 5.900000e1 0 0 0 0
Cu-64 1.7e-03 LLI/2 1.70e-03 5.00e-03 1.20e-04 3.783783e6 0 0 0 0
Zn-65 1.0e-02 LLI/2 8.60e-03 1.80e-02 3.90e-03 8.108000e3 0 0 0 0
Ga-68 NC Stomch/2 1.40e-03 3.90e-03 8.90e-05 4.054054e7 0 0 0 0
Ge-68 NC Kidney/2 1.60e-03 4.70e-03 2.90e-04 6.756000e3 0 0 0 0
Se-75 NC LLI/2 1.40e-02 3.30e-02 2.50e-02 1.459400e4 0 0 0 0
Kr-85 2.0e-02 NC NC NC NC 4.050000e2 559.45933 0 0.4297297e-6 .05
Kr-85m 2.0e-02 NC NC NC NC 8.108108e6 24000 0 0.15999999e-6 .05
Kr-87 2.0e-02 NC NC NC NC 2.702703e7 47027.016 0 0.14999999e-6 .05
Kr-88 2.0e-02 NC NC NC NC 1.243243e7 68108.1 0 0.28108106e-6 .05
A1.21
Rb-86 1.2e-02 Bone-S/2 1.60e-02 4.70e-02 2.50e-03 8.108100e4 26 0 0 0
Rb-87 1.2e-02 Bone-S/2 8.70e-03 2.60e-02 1.30e-03 8.648648e-8 0 0 0 0
Rb-88 1.2e-02 Stomch/2 1.70e-03 5.10e-03 4.40e-05 1.189189e8 0 0 0 0
Sr-89 1.4e-03 LLI/2 6.80e-02 2.00e-01 2.30e-03 2.972900e4 94054.043 0.99999997e-10 0.13999997e-9 0
Sr-90 1.4e-03 Bone-S/1 5.50e-01 7.40e-01 3.50e-02 1.370000e2 3702.7017 0.69999997e-11 0.11999997e-10 0
Sr-91 1.40e-03 LLI/2 1.20e-02 2.40e-02 8.10e-04 3.51e06 110000 4.00e-09 9.59E-10 0
Y-90 2.00e-05 LLI/2 7.40e-02 2.20e-01 2.70e-01 5.41e05 3891.8908 0 0 0
Y-91 2.00e-05 LLI/2 7.10e-02 2.10e-01 2.40e-03 2.46e04 120000 4.00E-11 5.19E-12 0
Y-91m 2.0e-05 Stomch/2 9.70e-05 2.40e-04 1.00e-05 4.054054e7 0 0 0 0
Zr-93 8.0e-02 Bone-S/2 1.10e-02 1.80e-02 4.20e-04 2.513514e7 0 0 0 0
Zr-95 8.0e-02 LLIW/1 1.60e-02 5.20e-02 1.10e-03 2.135100e4 150000 0 0 0
Nb-94 2.0e-02 LLI/2 7.50e-02 2.00e-01 1.80e-02 1.864865e-1 0 0 0 0
Nb-95 2.0e-02 LLIW/1 8.10e-03 2.40e-02 6.80e-04 3.783700e4 150000 0 0 0
Mo-99 1.4e-03 LLI/2 3.20e-02 9.40e-02 1.20e-03 4.864860e5 160000 0.19999997e-8 0.64054052e-8 0
Tc-99 9.9e-03 Stomch/2 8.00e-03 2.40e-02 3.50e-04 1.702703e-2 0 0.19999997e-8 0.47027025e-8 0
Tc-99m 9.9e-03 Thyroid/2 1.90e-04 5.40e-04 1.60e-05 5.135135e6 140000 0 0 0
Ru-103 6.1e-07 LLIW/1 1.40e-02 4.50e-02 8.10e-04 3.243200e4 110000 0.19999997e-10 0.75135133e-8 0
Ru-105 6.1e-07 ULI/2 3.60e-03 1.00e-02 2.80e-04 6.756756e6 71891.883 0 0 0
Rh-106 NC LLIW/1 1.50e-01 5.20e-01 7.50e-03 3.513514e9 0 0 0 0
Ru-106 NC LLI/2 1.70e-01 4.90e-01 5.80e-03 3.243000e3 25000 0.29999997e-11 0.95945943e-7 0
Ag-110m NC LLI/2 2.10e-02 5.30e-02 2.90e-03 4.864000e3 0 0 0 0
Cd-109 NC Kidney/2 7.80e-02 2.30e-01 3.00e-03 2.594000e3 0 0 0 0
Cd-113m NC Kidney/2 7.20e-01 1.70e+00 4.00e-02 2.320000e2 0 0 0 0
In-114m NC LLI/2 1.00e-01 3.00e-01 4.00e-03 2.324300e4 0 0 0 0
Sn-113 NC LLI/2 1.80e-02 5.30e-02 7.40e-04 1e4 0 0 0 0
Sn-123 NC LLI/2 6.10e-02 1.80e-01 2.10e-03 8.108000e3 0 0 0 0
Sn-126 NC LLI/2 9.90e-02 2.90e-01 4.70e-03 2.972973e-2 0 0 0 0
Sb-124 2.0e-05 LLI/2 5.20e-02 1.50e-01 2.60e-03 1.756700e4 0 0 0 0
Sb-126 2.0e-05 NC NC NC NC 8.378300e4 0 0 0 0
Sb-126m 2.0e-05 NC NC NC NC 7.837838e7 0 0 0 0
Sb-127 2.0e-05 LLI/2 4.50e-02 1.30e-01 1.80e-03 2.675670e5 6108.1072 0 0 0
Sb-129 2.0e-05 ULI/2 7.50e-03 2.00e-02 4.70e-04 5.675675e6 32972.964 0 0 0
Te-127 2.0e-04 LLI/2 2.90e-03 8.70e-03 1.80e-04 2.648648e6 5891.8909 0 0 0
Te-127m 2.0e-04 Bone-S/2 4.70e-02 1.40e-01 2.20e-03 9.459000e3 1100 0 0 0
Te-129 2.0e-04 Stomch/2 9.30e-04 2.80e-03 5.20e-05 2.081081e7 31081.072 0 0 0
Te-129m 2.0e-04 LLI/2 5.80e-02 1.70e-01 2.70e-03 2.972900e4 5297.2964 0.39999997e-10 0.18999997e-9 0
Te-131 2.0e-04 Thyroid/2 2.50e-03 7.60e-03 5.10e-05 5.675675e7 0 0 0 0
Te-131m 2.0e-04 Thyroid/2 4.00e-02 1.20e-01 1.50e-03 8.108100e5 13000 0.99999997e-10 0.14999997e-8 0
Te-132 2.0e-04 Thyroid/2 6.00e-02 2.20e-01 2.00e-03 2.972970e5 120000 0.99999997e-11 0.16999997e-8 0
I-125 9.9e-03 Thyroid/2 7.60e-01 1.30e+00 9.20e-03 1.729700e4 0 0 0 .05
I-129 9.9e-03 Thyroid/2 3.80e+00 4.30e+00 6.40e-02 1.756757e-4 0 0 0 .05
I-131 9.9e-03 Thyroid/2 1.10e+00 3.60e+00 1.30e-02 1.243240e5 85135.126 0.21999997e-8 0.45135133e-7 .05
I-132 9.9e-03 Thyroid/2 8.50e-03 3.60e-02 1.70e-04 1.027027e7 120000 0.21999997e-7 0.20999999e-6 .05
I-133 9.9e-03 Thyroid/2 2.30e-01 8.60e-01 2.50e-03 1.135135e6 170000 0.14999997e-7 0.13999989e-6 .05
I-134 9.9e-03 Thyroid/2 1.50e-03 5.60e-03 5.00e-05 2.675676e7 190000 0.4297297e-7 0.34054052e-6 .05
I-135 9.9e-03 Thyroid/2 4.40e-02 1.60e-01 4.80e-04 3.513513e6 150000 0.21999997e-7 0.25999997e-6 .05
Xe-131m NC NC NC NC NC 8.378300e4 1000 0 0.7297297e-6 .05
Xe-133 NC NC NC NC NC 1.864860e5 170000 0 0.25999999e-5 .05
Xe-133m NC NC NC NC NC 4.594590e5 6000 0 0.69999999e-7 .05
Xe-135 NC NC NC NC NC 2.540540e6 34054.044 0 0.85135133e-6 .05
Xe-135m NC NC NC NC NC 9.189189e7 0 0 0 .05
Xe-138 NC NC NC NC NC 9.729730e7 170000 0 0.11999989e-6 .05
Cs-134 7.1e-03 Pancrs/1 1.60e-02 1.70e-02 1.90e-02 1.297000e3 7513.5126 0.29999997e-10 0.71081079e-8 .05
Cs-135 7.1e-03 Stomch/2 2.10e-03 3.00e-03 1.70e-03 1.162162e-3 0 0 0 .05
Cs-136 7.1e-03 Uterus/2 5.80e-03 1.00e-02 2.80e-03 7.297200e4 3000 0.19999997e-10 0.87027025e-9 .05
Cs-137 7.1e-03 St.wll/1 1.00e-02 1.20e-02 1.30e-02 8.600000e1 4702.7016 0.79999997e-10 0.94054052e-8 .05
Cs-138 7.1e-03 Stomch/2 1.60e-03 4.60e-03 4.20e-05 4.324324e7 0 0 0 .05
Ba-133 NC LLI/2 8.20e-03 2.20e-02 8.50e-04 2.510000e2 0 0 0 0
Ba-137m NC NC NC NC NC 5.405406e8 0 0 0 0
Ba-140 NC Stomch/2 6.00e-02 1.80e-01 2.30e-03 7.297200e4 160000 0.39999997e-10 0.12999997e-7 0
La-140 NC LLI/2 3.90e-02 1.10e-01 2.10e-03 5.675670e5 160000 0.39999997e-9 0.24999997e-7 0
Ce-141 NC LLI/2 2.00e-002 1.60e-02 7.00e-04 2.972900e4 150000 0 0 0
Ce-144 NC LLIW/1 1.50e-01 4.97e-01 5.80e-03 3.243000e3 85135.126 0.29999997e-11 0.39999997e-8 0
A1.22
Pr-144 NC Stomch/2 9.60e-04 2.90e-03 3.00e-05 7.567567e7 0 0 0 0
Pr-144m NC NC NC NC NC 1.810811e8 0 0 0 0
Pm-145 NC NC NC NC NC 1.400000e2 0 0 0 0
Pm-147 NC NC NC NC NC 9.180000e2 0 0 0 0
Sm-147 NC Bone-S/2 1.10e+00 2.50e+00 4.80e-02 2.297297e-8 0 0 0 0
Sm-151 NC LLI/2 2.40e-03 7.10e-03 9.20e-05 2.600000e1 0 0 0 0
Eu-152 NC LLI/2 2.20e-02 6.00e-02 1.60e-03 1.750000e2 0 0 0 0
Eu-154 NC LLI/2 4.00e-02 1.20e-01 2.50e-03 2.640000e2 0 0 0 0
Eu-155 NC LLI/2 8.00e-03 2.30e-02 3.70e-04 4.590000e2 0 0 0 0
Gd-153 NC LLI/2 6.00e-03 1.70e-02 2.90e-04 3.513000e3 0 0 0 0
Tb-160 NC NC NC NC NC 1.135100e4 0 0 0 0
Ho-166m NC NC NC NC NC 1e0 0 0 0 0
Tm-170 NC NC 3.90e-02 1.20e-01 1.40e-03 5.945000e3 0 0 0 0
Yb-169 NC LLI/2 1.60e-02 4.70e-02 7.60e-04 2.405400e4 0 0 0 0
Hf-172 NC NC NC NC NC 1.108000e3 0 0 0 0
Hf-181 NC LLI/2 2.60e-02 7.60e-02 4.40e-04 1.702700e4 0 0 0 0
Ta-182 2.8e-06 LLI/2 3.10e-02 8.80e-02 1.60e-03 6.216000e3 0 0 0 0
W-187 2.9e-04 LLI/2 1.50e-02 4.30e-02 7.40e-04 7.027020e5 0 0 0 0
Ir-192 5.0e-06 LLI/2 2.90e-02 8.40e-02 1.40e-03 9.189000e3 0 0 0 0
Au-198 5.0e-06 LLI/2 2.50e-02 7.20e-02 1.10e-03 2.459450e5 0 0 0 0
Hg-203 9.7e-06 LLI/2 4.10e-02 1.20e-01 2.70e-03 1.378300e4 0 0 0 0
Tl-204 1.3e-03 Kidney/2 1.10e-02 3.20e-02 8.70e-04 4.590000e2 0 0 0 0
Pb-210 2.6e-04 Bone-S/2 2.70e+01 5.60e+01 1.40e+00 7.500000e1 0 0 0 0
Bi-207 5.0e-04 LLI/2 2.00e-02 5.30e-02 1.30e-03 4.500000e1 0 0 0 0
Bi-210 5.0e-04 LLI/2 3.60e-02 1.10e-01 1.60e-03 1.243240e5 0 0 0 0
Po-210 1.4e-02 Spleen/2 9.90e+00 3.00e+01 4.30e-01 4.594000e3 0 0 0 0
Ra-226 4.5e-04 Bone-S/2 9.00e+00 2.00e+01 3.00e-01 1e0 0 0 0 0
Ac-227 2.0e-05 Bone-S/2 8.20e+01 1.60e+02 3.80e+00 7.200000e1 0 0 0 0
Ac-228 2.0e-05 Bone-S/2 5.50e-03 1.60e-02 5.60e-04 2.243243e6 0 0 0 0
Th-227 5.0e-06 LLI/2 2.10e-01 6.30e-01 9.80e-03 2.972900e4 0 0 0 0
Th-228 5.0e-06 Bone-S/2 4.30e+00 1.30e+01 1.00e-01 8.100000e2 0 0 0 0
Th-230 5.0e-06 Bone-S/2 4.40e+00 8.10e+00 1.40e-01 2.027027e-2 0 0 0 0
Th-231 5.0e-06 LLI/2 7.90e-03 2.40e-02 3.50e-04 5.405400e5 0 0 0 0
Th-232 5.0e-06 Bone-S/2 2.10e+01 3.10e+01 7.40e-01 1.108108e-7 0 0 0 0
Pa-231 5.0e-06 Bone-S/2 9.30e+01 1.30e+02 2.90e+00 4.594594e-2 0 0 0 0
Pa-233 5.0e-06 LLI/2 2.40e-02 7.00e-02 9.00e-04 2.081000e4 0 0 0 0
U-232 6.1e-04 Bone-S/2 7.80e+00 1.50e+01 3.40e-01 3.513514e-7 0 0 0 0
U-233 6.1e-04 Bone-S/2 1.50e+00 3.10e+00 7.10e-02 6.756757e-7 0 0 0 0
U-234 6.1e-04 Bone-S/2 1.40e+00 3.10e+00 7.00e-02 2.405406e-6 0 0 0 0
U-235 6.1e-04 Bone-S/2 1.30e+00 2.80e+00 6.60e-02 2.100000e1 0 0 0 0
U-236 6.1e-04 Bone-S/2 1.40e+00 2.90e+00 6.60e-02 9.729730e-3 0 0 0 0
U-238 6.1e-04 Bone-S/2 1.30e+00 2.70e+00 6.30e-02 6.216216e-3 0 0 0 0
U-Depleted-Nat 6.1e-04 LLI/2 1.30e+00 2.70e+00 6.30e-02 2.162162e-6 0 0 0 0
U-Enriched 6.1e-04 Bone-S/2 1.40e+00 3.10e+00 7.00e-02 3.243243e-7 0 0 0 0
UF6 0 0 0 0 0 0 0 0 0 0
Np-237 5.0e-06 Bone-S/1 9.90e+00 8.90e+00 4.50e-01 7.027027e-4 0 0 0 0
Np-239 5.0e-06 LLIW/1 1.90e-02 6.40e-02 8.70e-02 2.324320e5 1600000 0.79999997e-8 0.21999997e-8 0
Pu-236 2.7e-09 LLI/2 4.70e+00 1.20e+01 1.80e+01 5.400000e2 0 0 0 0
Pu-238 2.7e-09 LLI/2 1.90e+01 3.40e+01 8.60e-01 1.700000e1 57.027017 0 0 0
Pu-239 2.7e-09 LLI/2 2.20e+01 3.70e+01 9.50e-01 6.216216e-2 21 0 0 0
Pu-240 2.7e-09 LLI/2 2.20e+01 3.70e+01 9.50e-01 2.270270e-1 21 0 0 0
Pu-241 2.7e-09 Bone-M/1 3.70e-01 3.40e-01 1.90e-02 1.020000e2 3405.4045 0 0 0
Pu-242 2.7e-09 LLI/2 2.10e+01 3.50e+01 9.00e-01 4.054054e-3 0 0 0 0
Am-241 2.0e-05 Bone-S/1 1.90e+01 1.90e+01 8.90e-01 3e0 1.6999998 0 0 0
Am-242m 2.0e-05 Bone-S/2 2.10e+01 3.50e+01 9.50e-01 9e0 0 0 0 0
Am-243 2.0e-05 Bone-S/2 2.20e+01 3.80e+01 9.80e-01 2e-1 0 0 0 0
Cm-242 2.0e-05 Bone-S/2 8.90e-01 2.60e+00 3.00e-02 3.243000e3 500 0 0 0
Cm-243 2.0e-05 Bone-S/2 1.50e+01 2.90e+01 6.70e-01 5.100000e1 0 0 0 0
Cm-244 2.0e-05 Bone-S/2 1.20e+01 2.50e+01 5.40e-01 8.100000e1 23 0 0 0
Cm-245 2.0e-05 Bone-S/2 2.30e+01 3.90e+01 1.00e+00 1.729730e-1 0 0 0 0
Cf-252 2.0e-05 Bone-S/2 4.90e+00 1.40e+01 1.40e-01 5.400000e2 0 0 0 0
A1.23
RADIOLOGICAL NUCLIDE DATA (continued)
_____________________________________
41. LWR CORE RELEASE FRACTIONS AT 1250 C
42. LWR CORE RELEASE FRACTIONS AT 1650 C
43. ISOTOPE DECAY MODES
44. TARGET NUCLIDE FOR NEUTRON ACTIVATION
45. TARGET MATERIAL FOR NUCLIDE ACTIVATION
46. NEUTRON TARGET NUCLIDE ABUNDANCE IN TARGET MATERIAL [%]
47. NEUTRON ACTIVATION CROSS-SECTION OF TARGET NUCLIDE [cm2]
48. ELEMENT DENSITY [g/cm3]
49. DEPOSITION VELOCITY [m/s]
50. WASHOUT RATE [1/s]
__________________________________________________________________
41 42 43 44 45 46 47 48 49 50
_____________________________________________________________________________________________________________________________________________________________________
H-3 0 0 b- Ho-165 HO2 100.00 6.00e-23 8.80 0.001 0.00012
C-14 0 0 ba- N-14 KNO3 99.63 1.75e-24 1.25 0.001 0.00012
Na-22 0 0 EC,b+ Mg-24 Mg 78.60 6.30e-26 1.74 0.001 0.00012
Na-24 0 0 b- Na-23 Na2CO3,NaCl,NaH100.00 5.30e-25 0.97 0.001 0.00012
P-32 0 0 b- P-31 S 95.018 5.20e-25 1.82 0.001 0.00012
P-33 0 0 b- NC NC NC NC NC 0.001 0.00012
S-35 0 0 b- S-34 S 4.215 2.60e-25 2.07 0.001 0.00012
Cl-36 0 0 EC,b+,b- Cl-35 KCl 75.4 3.38e-23 1.56 0.001 0.00012
K-40 0 0 EC K-39 K 100.0 7.0e-23 0.86 0.001 0.00012
K-42 0 0 b- K-41 KCl,K2Co3 6.91 2.07e-24 0.86 0.001 0.00012
Ca-45 0 0 b- Ca-44 CaCO3 2.06 7.2e-25 1.55 0.001 0.00012
Sc-46 0 0 b- Sc-45 Sc2O3 100.00 22.3e-24 3.0 0.001 0.00012
Ti-44 0 0 EC NC NC NC NC NC 0.001 0.00012
V-48 0 0 EC,b+ Cr-50 Cr 4.31 NC 5.8 0.001 0.00012
Cr-51 0 0 EC Cr-50 Cr,Cr2O3 4.31 NC 7.19 0.001 0.00012
Mn-54 0 0 EC Fe-56 Fe,Cr 91.68 NC 7.43 0.001 0.00012
Mn-56 0 0 b- Mn-55 Mn 100.00 13.3e-24 7.43 0.001 0.00012
Fe-55 0 0 EC Fe-54 Fe,Fe2O3 5.84 2.8e-24 7.86 0.001 0.00012
Co-58 0 0 EC,b+ Ni-58 Ni 67.76 NC 8.9 0.001 0.00012
Fe-59 0 0 b- Fe-58 Fe,Fe2O3 0.31 1.01e-24 7.86 0.001 0.00012
Co-60 0 0 b- Co-59 Co 100.00 36.3e-24 8.9 0.001 0.00012
Ni-63 0 0 b- Ni-62 Ni 3.66 21.0e-24 8.9 0.001 0.00012
Cu-64 0 0 b-,EC,b+ Cu-63 Cu 69.1 4.51e-24 8.96 0.001 0.00012
Zn-65 0 0 EC,b+ Zn-64 Zn 48.89 4.7e-25 7.14 0.001 0.00012
Ga-68 0 0 EC,b+ NC NC NC NC 5.91 0.001 0.00012
Ge-68 0 0 EC NC NC NC NC 5.32 0.001 0.00012
Se-75 .15 .44 EC Se-74 Se 0.87 26.0e-24 4.79 0.001 0.00012
Kr-85 .95 .95 b- Kr-84 Kr,U 56.90 0.060e-24 2.6 0.001 0.00012
Kr-85m .95 .95 IT,b- Kr-84 Kr 56.90 0.10e-24 2.6 0.001 0.00012
Kr-87 .95 .95 b- NC NC NC NC 2.6 0.001 0.00012
Kr-88 .95 .95 b- NC NC NC NC 2.6 0.001 0.00012
Rb-86 .25 .64 b- Rb-85 RbCl 72.15 0.91e-24 1.53 0.001 0.00012
Rb-87 .25 .64 b- NC NC NC NC 1.53 0.001 0.00012
Rb-88 .25 .64 b- NC NC NC NC 1.53 0.001 0.00012
Sr-89 .03 .15 b- Sr-88 SrCO3 82.56 0.005e-24 2.6 0.001 0.00012
Sr-90 .03 .15 b- NC NC NC NC 2.6 0.001 0.00012
Sr-91 .03 .15 b- NC NC NC NC 2.6 0.001 0.00012
Y-90 .002 .017 b- Y-89 Y2O3 100 1.26E-24 4.5 0.001 0.00012
Y-91 .002 .017 b- NC NC NC NC 4.5 0.001 0.00012
Y-91m .002 .017 IT NC NC NC NC 4.5 0.001 0.00012
Zr-93 .002 .017 b- NC NC NC NC 6.49 0.001 0.00012
Zr-95 .002 .017 b- Zr-94 ZrO2 17.40 0.076e-24 6.49 0.001 0.00012
Nb-94 .002 .017 b- NC NC NC NC 8.4 0.001 0.00012
Nb-95 .002 .017 b- Zr-94 ZrO2 17.40 0.076e-24 8.4 0.001 0.00012
Mo-99 .008 .012 b- Mo-98 MoO3 23.75 0.51e-24 10.2 0.001 0.00012
A1.24
Tc-99 .008 .012 b- Mo-98 MoO3,U 23.75 0.51e-24 11.5 0.001 0.00012
Tc-99m .008 .012 IT NC NC NC NC 11.5 0.001 0.00012
Ru-103 .008 .012 b- Ru-102 Ru,U 31.3 1.44e-24 12.2 0.001 0.00012
Ru-105 .008 .012 b- Ru-104 Ru 18.3 0.7e-24 12.2 0.001 0.00012
Rh-106 .008 .012 b- NC NC NC NC 12.0 0.001 0.00012
Ru-106 .008 .012 b- NC NC NC NC 12.2 0.001 0.00012
Ag-110m 0 0 IT,b- Ag-109 Ag 48.65 3.2e-24 10.49 0.001 0.00012
Cd-109 0 0 EC Ag-109 Ag 48.65 3.2e-24 8.65 0.001 0.00012
Cd-113m 0 0 b- NC NC NC NC 8.65 0.001 0.00012
In-114m 0 0 EC,IT In-113 In 4.23 56e-24 7.31 0.001 0.00012
Sn-113 0 0 EC Sn-112 Sn 0.95 1.3e-24 7.30 0.001 0.00012
Sn-123 0 0 b- NC NC NC NC 7.30 0.001 0.00012
Sn-126 0 0 b- NC NC NC NC 7.30 0.001 0.00012
Sb-124 .15 .44 b- Sb-123 Sb 42.75 2.5e-24 6.62 0.001 0.00012
Sb-126 .15 .44 b- NC NC NC NC 6.62 0.001 0.00012
Sb-126m .15 .44 IT,b- NC NC NC NC 6.62 0.001 0.00012
Sb-127 .15 .44 b- NC NC NC NC 6.62 0.001 0.00012
Sb-129 .15 .44 b- NC NC NC NC 6.62 0.001 0.00012
Te-127 .15 .44 b- NC NC NC NC 6.24 0.001 0.00012
Te-127m .15 .44 IT,b- Te-126 Te,U 18.7 0.090e-24 6.24 0.001 0.00012
Te-129 .15 .44 b- NC NC NC NC 6.24 0.001 0.00012
Te-129m .15 .44 IT.b- NC NC NC NC 6.24 0.001 0.00012
Te-131 .15 .44 b- NC NC NC NC 6.24 0.001 0.00012
Te-131m .15 .44 IT,b- NC NC NC NC 6.24 0.001 0.00012
Te-132 .15 .44 b- NC NC NC NC 6.24 0.001 0.00012
I-125 .35 .64 EC NC NC NC NC 4.94 0.010 0.00008
I-129 .35 .64 b- NC NC NC NC 4.94 0.010 0.00008
I-131 .35 .64 b- Te-130 TeO2,U 34.49 0.22e-24 4.94 0.010 0.00008
I-132 .35 .64 b- NC NC NC NC 4.94 0.010 0.00008
I-133 .35 .64 b- NC NC NC NC 4.94 0.010 0.00008
I-134 .35 .64 b- NC NC NC NC 4.94 0.010 0.00008
I-135 .35 .64 b- NC NC NC NC 4.94 0.010 0.00008
Xe-131m .95 0 IT NC NC NC NC 5.89 0.001 0.00012
Xe-133 .95 .95 b- NC NC NC NC 5.89 0.001 0.00012
Xe-133m .95 .95 IT Xe-132 Xe,U 26.89 5e-24 5.89 0.001 0.00012
Xe-135 .95 .95 b- NC NC NC NC 5.89 0.001 0.00012
Xe-135m .95 .95 IT NC NC NC NC 5.89 0.001 0.00012
Xe-138 .95 .95 b- NC NC NC NC 5.89 0.001 0.00012
Cs-134 .25 .64 EC,b- Cs-133 Cs2CO3 100.00 33e-24 1.90 0.001 0.00012
Cs-135 .25 .64 b- NC NC NC NC 1.90 0.001 0.00012
Cs-136 .25 .64 b- NC NC NC NC 1.90 0.001 0.00012
Cs-137 .25 .64 b- NC NC NC NC 1.90 0.001 0.00012
Cs-138 .25 .64 b- NC NC NC NC 1.90 0.001 0.00012
Ba-133 .04 .14 EC Ba-132 Ba(NO3)2 0.097 7e-24 3.5 0.001 0.00012
Ba-137m .04 .14 IT NC NC NC NC 3.5 0.001 0.00012
Ba-140 .04 .14 b- NC NC NC NC 3.5 0.001 0.00012
La-140 .002 .017 b- La-139 La2O3 99.91 8.4e-24 6.17 0.001 0.00012
Ce-141 .01 .03 b- Ce-140 Ce,CeO2 88.48 0.31e-24 7.14 0.001 0.00012
Ce-144 .01 .03 b- NC NC NC NC 7.14 0.001 0.00012
Pr-144 .002 .017 b- NC NC NC NC 6.77 0.001 0.00012
Pr-144m .002 .017 IT,b- NC NC NC NC 6.77 0.001 0.00012
Pm-145 .002 .017 b- NC NC NC NC 6.47 0.001 0.00012
Pm-147 .002 .017 b- Nd-146 Nd2O3 17.18 1.8e-24 6.47 0.001 0.00012
Sm-147 .002 .017 a NC NC NC NC 7.54 0.001 0.00012
Sm-151 .002 .017 b- NC NC NC NC 7.54 0.001 0.00012
Eu-152 .002 .017 b-,EC,b+ Eu-151 Eu2O3 47.77 7000e-24 5.26 0.001 0.00012
Eu-154 .002 .017 EC,b- Eu-153 Eu2O3 52.53 420e-24 5.26 0.001 0.00012
Eu-155 .002 .017 b- Sm-154 Sm2O3 22.53 5.5e-24 5.26 0.001 0.00012
Gd-153 0 0 EC Gd-152 Gd2O3 0.200 125e-24 7.87 0.001 0.00012
Tb-160 0 0 b- Tb-159 Tb4O7,Tb2O3 100.00 22e-24 8.27 0.001 0.00012
Ho-166m 0 0 b- NC NC NC NC 8.80 0.001 0.00012
Tm-170 0 0 EC,b- Tm-169 Tm2O3 100.00 130e-24 9.33 0.001 0.00012
Yb-169 0 0 EC Yb-168 Yb2O3 0.140 11000e-24 6.98 0.001 0.00012
A1.25
Hf-172 0 0 EC NC NC NC NC 13.1 0.001 0.00012
Hf-181 0 0 b- Hf-180 HfO2 35.44 10e-24 13.1 0.001 0.00012
Ta-182 0 0 b- Ta-181 Ta,Ta2O5 100.00 19e-24 16.6 0.001 0.00012
W-187 0 0 b- W-186 W,WO3 30.6 34e-24 19.3 0.001 0.00012
Ir-192 0 0 b-,EC Ir-191 Ir 38.5 960e-24 22.5 0.001 0.00012
Au-198 0 0 b- Au-197 Au 100.00 96e-24 19.3 0.001 0.00012
Hg-203 0 0 b- Hg-202 Hg,HgO 29.80 3.8e-24 13.6 0.001 0.00012
Tl-204 0 0 EC,b- Tl-203 TlNO3 29.50 8e-24 11.85 0.001 0.00012
Pb-210 0 0 b- NC NC NC NC 11.34 0.001 0.00012
Bi-207 0 0 EC,b+ NC NC NC NC 9.8 0.001 0.00012
Bi-210 0 0 b- Bi-209 Bi2O3 100.00 0.019e-24 9.8 0.001 0.00012
Po-210 0 0 a Bi-209 Bi2O3 100.00 0.019e-24 9.2 0.001 0.00012
Ra-226 0 0 a NC NC NC NC 5.0 0.001 0.00012
Ac-227 0 0 b-,a NC NC NC NC NC 0.001 0.00012
Ac-228 0 0 b- NC NC NC NC NC 0.001 0.00012
Th-227 0 0 a NC NC NC NC 11.7 0.001 0.00012
Th-228 0 0 a NC NC NC NC 11.7 0.001 0.00012
Th-230 0 0 a NC NC NC NC 11.7 0.001 0.00012
Th-231 0 0 b- NC NC NC NC 11.7 0.001 0.00012
Th-232 0 0 a NC NC NC NC 11.7 0.001 0.00012
Pa-231 .008 .012 a NC NC NC NC 15.4 0.001 0.00012
Pa-233 .008 .012 b- Th-232 ThO2 100.00 7.3e-24 15.4 0.001 0.00012
U-232 0 0 a NC NC NC NC 18.90 0.001 0.00012
U-233 0 0 a NC NC NC NC 18.90 0.001 0.00012
U-234 0 0 a NC NC NC NC 18.90 0.001 0.00012
U-235 0 0 a NC NC NC NC 18.90 0.001 0.00012
U-236 0 0 a NC NC NC NC 18.90 0.001 0.00012
U-238 0 0 SF,a NC NC NC NC 18.90 0.001 0.00012
U-Depleted-Nat 0 0 SF,a NC NC NC NC 18.90 0.001 0.00012
U-Enriched 0 0 a NC NC NC NC 18.90 0.001 0.00012
UF6 0 0 0 0 0 0 0 0 0 0
Np-237 .01 .03 a NC NC NC NC NC 0.001 0.00012
Np-239 .01 .03 b- NC NC NC NC NC 0.001 0.00012
Pu-236 .01 .03 SF,a NC NC NC NC 19.84 0.001 0.00012
Pu-238 .01 .03 SF,a NC NC NC NC 19.84 0.001 0.00012
Pu-239 .01 .03 a NC NC NC NC 19.84 0.001 0.00012
Pu-240 .01 .03 SF,a NC NC NC NC 19.84 0.001 0.00012
Pu-241 .01 .03 a,b- NC NC NC NC 19.84 0.001 0.00012
Pu-242 .01 .03 SF,a NC NC NC NC 19.84 0.001 0.00012
Am-241 0 0 a NC NC NC NC 11.87 0.001 0.00012
Am-242m 0 0 a,IT NC NC NC NC 11.87 0.001 0.00012
Am-243 0 0 a NC NC NC NC 11.87 0.001 0.00012
Cm-242 0 0 SF,a NC NC NC NC NC 0.001 0.00012
Cm-243 0 0 a,EC NC NC NC NC NC 0.001 0.00012
Cm-244 0 0 SF,a NC NC NC NC NC 0.001 0.00012
Cm-245 0 0 a NC NC NC NC NC 0.001 0.00012
Cf-252 0 0 SF,a NC NC NC NC 15.04 0.001 0.00012
A.1.4. Source term specific data A. SOURCE TERM-RELEVANT DATA
____________________________
1 - Nuclide
2 - Halflife(d
3 - Reactore Core Inventory (Ci/MWe)
4 - BWR Coolant Inventory (Ci)
5 - PWR Coolant Inventory (Ci)
6 - Core Release Fraction 650 C
7 - Core Release Fraction 1250 C
A1.26
8 - Core Release Fraction 1650 C
9 - Fire Release Fraction
10 - Isotope/Cs-137 ratios for reactor core damage accidents,
for the following hours since shutdown: 1,6,12,24,72,168,360,720
_____________________________________________________________________
1 2 3 4 5 6 7 8 9 10
______________________________________________________________________________________________________
H-3 4.5e03 0 1.00e-8 1.00e-6 0 0 0 5.0e-1 NC,NC,NC,NC,NC,NC,NC,NC !
C-14 2.1e06 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Na-22 9.5e02 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Na-24 6.3e-01 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
P-32 1.4e01 0 0 0 0 0 0 5.0e-1 NC,NC,NC,NC,NC,NC,NC,NC !
P-33 2.5e01 0 0 0 0 0 0 5.0e-1 NC,NC,NC,NC,NC,NC,NC,NC !
S-35 8.7e01 0 0 0 0 0 0 5.0e-1 NC,NC,NC,NC,NC,NC,NC,NC !
Cl-36 1.1e08 0 0 0 0 0 0 5.0e-1 NC,NC,NC,NC,NC,NC,NC,NC !
K-40 4.7e11 0 0 0 0 0 0 5.0e-1 NC,NC,NC,NC,NC,NC,NC,NC !
K-42 5.2e-01 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Ca-45 1.6e02 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Sc-46 8.4e01 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Ti-44 1.7e04 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
V-48 1.6e01 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Cr-51 2.8e01 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Mn-54 3.1e02 0 0.70e-10 0.16e-8 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Mn-56 1.1e-01 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Fe-55 9.9e02 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Co-58 7.1e01 0 0.20e-9 0.46e-8 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Fe-59 4.5e01 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Co-60 1.9e03 0 0.40e-9 0.53e-9 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Ni-63 3.5e04 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Cu-64 5.3e-01 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Zn-65 2.4e02 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Ga-68 4.7e-02 0 0 0 0 0 0 NC NC,NC,NC,NC,NC,NC,NC,NC !
Ge-68 2.9e02 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Se-75 1.2e02 0 0 0 0 .15 .44 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Kr-85 3.9e03 559.45933 0 0.43e-6 .05 .95 .95 1.0e0 NC,NC,NC,NC,NC,NC,NC,NC !
Kr-85m 1.9e-01 24000 0 0.16e-6 .05 .95 .95 1.0e0 NC,NC,NC,NC,NC,NC,NC,NC !
Kr-87 5.3e-02 47027.016 0 0.15e-6 .05 .95 .95 1.0e0 NC,NC,NC,NC,NC,NC,NC,NC !
Kr-88 1.2e-01 68108.1 0 0.28e-6 .05 .95 .95 1.0e0 NC,NC,NC,NC,NC,NC,NC,NC !
Rb-86 1.9e01 26 0 0 0 .25 .64 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Rb-87 1.7e13 0 0 0 0 .25 .64 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Rb-88 1.2e-02 0 0 0 0 .25 .64 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Sr-89 5.1e01 94054.043 1.00e-10 0.14e-9 0 .03 .15 1.0e-2 2.4e00,2.4e00,2.4e00,2.4e00,2.3e00,2.2e00,2.0e00,1.6e-01 !
Sr-90 1.1e04 3702.7017 0.70e-11 0.12e-10 0 .03 .15 1.0e-2 1.0e-01,1.0e-01,1.0e-01,1.0e-01,1.0e-01,1.0e-01,1.0e-01,1.0e-01 !
Sr-91 4.0e-01 110000 0.40e-8 0.96e-9 0 .03 .15 1.0e-2 2.6e00,1.8e00,1.2e00,5.0e-01,0.0,0.0,0.0,0.0 !
Y-90 2.7e00 3891.8908 0 0 0 .002 .017 1.0e-2 0.0,0.0,0.0,0.0,1.0e-01,1.0e-01,1.0e-01,1.0e-01 !
Y-91 5.9e01 120000 0.40e-10 0.52e-11 0 .002 .017 1.0e-2 2.0e-01,2.0e-01,2.0e-01,2.0e-01,2.0e-01,2.0e-01,2.0e-01,2.0e-01 !
Y-91m 3.5e-02 0 0 0 0 .002 .017 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Zr-93 5.6e08 0 0 0 0 .002 .017 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Zr-95 6.4e01 150000 0 0 0 .002 .017 1.0e-2 3.0e-01,3.0e-01,3.0e-01,3.0e-01,3.0e-01,2.0e-01,2.0e-01,2.0e-01 !
Nb-94 7.4e06 0 0 0 0 .002 .017 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Nb-95 3.5e01 150000 0 0 0 .002 .017 1.0e-2 3.0e-01,3.0e-01,3.0e-01,3.0e-01,3.0e-01,3.0e-01,3.0e-01,2.0e-01 !
Mo-99 2.8e00 160000 0.20e-8 0.64e-8 0 .008 .012 1.0e-2 1.1e00,1.0e00,1.0e00,8.0e-01,5.0e-01,2.0e-01,0.0,0.0 !
Tc-99 7.8e07 0 0.20e-8 0.47e-8 0 .008 .012 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Tc-99m 2.5e-01 140000 0 0 0 .008 .012 1.0e-2 1.0e00,9.0e-01,9.0e-01,8.0e-01,5.0e-01,2.0e-01,0.0,0.0 !
Ru-103 3.9e01 110000 0.20e-10 0.75e-8 0 .008 .012 1.0e-2 7.0e-01,7.0e-01,7.0e-01,7.0e-01,7.0e-01,7.0e-01,6.0e-01,4.0e-01 !
Ru-105 1.9e-01 71891.883 0 0 0 .008 .012 1.0e-2 4.0e-01,2.0e-01,1.0e-01,0.0,0.0,0.0,0.0,0.0 !
Rh-106 3.5e-04 0 0 0 0 .008 .012 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Ru-106 3.7e02 25000 0.30e-11 0.96e-7 0 .008 .012 1.0e-2 2.0e-01,2.0e-01,2.0e-01,2.0e-01,2.0e-01,2.0e-01,2.0e00,2.0e-01 !
Ag-110m 2.5e02 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,0.0,NC !
Cd-109 4.6e02 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Cd-113m 5.0e03 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
A1.27
In-114m 5.0e01 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Sn-113 1.2e02 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Sn-123 1.3e02 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Sn-126 3.7e07 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Sb-124 6.0e01 0 0 0 0 .15 .44 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Sb-126 1.2e01 0 0 0 0 .15 .44 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Sb-126m 1.3e-02 0 0 0 0 .15 .44 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Sb-127 3.9e00 6108.1072 0 0 0 .15 .44 1.0e-2 8.0e-01,7.0e-01,7.0e-01,7.0e-01,5.0e-01,2.0e-01,1.0e-01,0.0 !
Sb-129 1.8e-01 32972.964 0 0 0 .15 .44 1.0e-2 3.6e00,1.6e00,6.0e-01,1.0e-01,0.0,0.0,0.0,0.0 !
Te-127 3.9e-01 5891.8909 0 0 0 .15 .44 1.0e-2 8.0e-01,8.0e-01,8.0e-01,7.0e-01,6.0e-01,3.0e-01,2.0e-01,1.0e-01 !
Te-127m 1.1e02 1100 0 0 0 .15 .44 1.0e-2 1.0e-01,1.0e-01,1.0e-01,1.0e-01,1.0e-01,1.0e-01,1.0e-01,1.0e-01 !
Te-129 4.8e-02 31081.072 0 0 0 .15 .44 1.0e-2 3.8e00,2.2e00,1.1e00,5.0e-01,4.0e-01,3.0e-01,3.0e-01,2.0e-01 !
Te-129m 3.4e01 5297.2964 0.40e-10 0.19e-9 0 .15 .44 1.0e-2 7.0e-01,7.0e-01,7.0e-01,7.0e-01,6.0e-01,6.0e-01,5.0e-01,4.0e-01 !
Te-131 1.7e-02 0 0 0 0 .15 .44 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Te-131m 1.3e00 13000 1.00e-10 0.15e-8 0 .15 .44 1.0e-2 1.6e00,1.4e00,1.3e00,1.0e00,3.0e-01,0.0,0.0,0.0 !
Te-132 3.3e00 120000 1.00e-11 0.17e-8 0 .15 .44 1.0e-2 14.2e00,14.5e00,13.8e00,12.4e00,8.1e00,3.5e00,6.0e-01,0.0 !
I-125 6.0e01 0 0 0 .05 .35 .64 5.0e-1 NC,NC,NC,NC,NC,NC,NC,NC !
I-129 5.7e09 0 0 0 .05 .35 .64 5.0e-1 NC,NC,NC,NC,NC,NC,NC,NC !
I-131 8.0e00 85135.126 0.22e-8 0.45e-7 .05 .35 .64 5.0e-1 24.2e00,24.8e00,24.3e00,23.2e00,19.6e00,13.9e00,7.0e00,1.9e00 !
I-132 9.6e-02 120000 0.22e-7 0.21e-6 .05 .35 .64 5.0e-1 30.4e00,18.2e00,14.7e00,12.8e00,8.3e00,3.6e00,7.0e-01,0.0 !
I-133 8.7e-01 170000 0.15e-7 0.14e-6 .05 .35 .64 5.0e-1 49.0e00,41.5e00,34.0e00,22.8e00,4.6e00,2.0e-01,0.0,0.0 !
I-134 3.7e-02 190000 0.43e-7 0.34e-6 .05 .35 .64 5.0e-1 25.7e00,5.0e-01,0.0,0.0,0.0,0.0,0.0,0.0 !
I-135 2.8e-01 150000 0.22e-7 0.26e-6 .05 .35 .64 5.0e-1 40.2e00,23.8e00,12.7e00,3.6e00,0.0,0.0,0.0,0.0 !
Xe-131m 1.2e01 1000 0 0.73e-6 .05 .95 0 1.0e0 NC,NC,NC,NC,NC,NC,NC,NC !
Xe-133 5.2e00 170000 0 0.26e-5 .05 .95 .95 1.0e0 NC,NC,NC,NC,NC,NC,NC,NC !
Xe-133m 2.2e00 6000 0 0.70e-7 .05 .95 .95 1.0e0 NC,NC,NC,NC,NC,NC,NC,NC !
Xe-135 3.8e-01 34054.044 0 0.85e-6 .05 .95 .95 1.0e0 NC,NC,NC,NC,NC,NC,NC,NC !
Xe-135m 1.1e-02 0 0 0 .05 .95 .95 1.0e0 NC,NC,NC,NC,NC,NC,NC,NC !
Xe-138 9.8e-03 170000 0 0.12e-6 .05 .95 .95 1.0e0 NC,NC,NC,NC,NC,NC,NC,NC !
Cs-134 7.5e02 7513.5126 0.30e-10 0.71e-8 .05 .25 .64 1.0e-2 1.6e00,1.6e00,1.6e00,1.6e00,1.6e00,1.6e00,1.6e00,1.6e00 !
Cs-135 8.4e08 0 0 0 .05 .25 .64 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Cs-136 1.3e01 3000 0.20e-10 0.87e-9 .05 .25 .64 1.0e-2 6.0e-01,6.0e-01,6.0e-01,6.0e-01,5.0e-01,4.0e-01,3.0e-01,1.0e-01 !
Cs-137 1.1e04 4702.7016 0.80e-10 0.94e-8 .05 .25 .64 1.0e-2 1.0e00,1.0e00,1.0e00,1.0e00,1.0e00,1.0e00,1.0e00,1.0e00 !
Cs-138 2.2e-02 0 0 0 .05 .25 .64 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Ba-133 3.9e03 0 0 0 0 .04 .14 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Ba-137m 1.8e-03 0 0 0 0 .04 .14 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Ba-140 1.3e01 160000 0.40e-10 0.13e-7 0 .04 .14 1.0e-2 5.4e00,5.4e00,5.3e00,4.2e00,4.6e00,3.7e00,2.4e00,1.1e00 !
La-140 1.7e00 160000 0.40e-9 0.25e-7 0 .002 .017 1.0e-2 4.0e-01,8.0e-01,1.2e00,2.0e00,3.6e00,4.0e00,2.8e00,1.2e00 !
Ce-141 3.3e01 150000 0 0 0 .01 .03 1.0e-2 1.3e00,1.3e00,1.3e00,1.2e00,1.2e00,1.1e00,9.0e-01,7.0e-01 !
Ce-144 2.8e02 85135.126 0.30e-11 0.40e-8 0 .01 .03 1.0e-2 7.0e-01,7.0e-01,7.0e-01,7.0e-01,7.0e-01,7.0e-01,7.0e-01,7.0e-01 !
Pr-144 1.2e-02 0 0 0 0 .002 .017 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Pr-144m 5.0e-03 0 0 0 0 .002 .017 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Pm-145 6.5e03 0 0 0 0 .002 .017 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Pm-147 9.6e02 0 0 0 0 .002 .017 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Sm-147 3.9e13 0 0 0 0 .002 .017 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Sm-151 3.3e04 0 0 0 0 .002 .017 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Eu-152 4.9e03 0 0 0 0 .002 .017 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Eu-154 3.2e03 0 0 0 0 .002 .017 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Eu-155 1.8e03 0 0 0 0 .002 .017 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Gd-153 2.4e02 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Tb-160 7.2e01 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Ho-166m 4.4e05 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Tm-170 1.3e02 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Yb-169 3.2e01 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Hf-172 6.8e02 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Hf-181 4.2e01 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Ta-182 1.1e02 0 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
W-187 1.0e00 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Ir-192 7.4e01 0 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Au-198 2.7e00 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Hg-203 4.7e01 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Tl-204 1.4e03 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Pb-210 8.1e03 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
A1.28
Bi-207 1.4e04 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Bi-210 5.0e00 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Po-210 1.4e02 0 0 0 0 0 0 1.0e-2 NC,NC,NC,NC,NC,NC,NC,NC !
Ra-226 5.8e05 0 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Ac-227 7.9e03 0 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Ac-228 2.6e-01 0 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Th-227 1.9e01 0 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Th-228 7.0e02 0 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Th-230 2.8e07 0 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Th-231 1.1e00 0 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Th-232 5.1e12 0 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Pa-231 1.2e07 0 0 0 0 .008 .012 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Pa-233 2.7e01 0 0 0 0 .008 .012 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
U-232 2.6e04 0 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
U-233 5.8e07 0 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
U-234 8.9e07 0 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
U-235 2.6e11 0 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
U-236 8.5e09 0 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
U-238 1.6e12 0 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
U-Depleted 1.6e12 0 0 0 0 0 0 NC NC,NC,NC,NC,NC,NC,NC,NC !
U-Natural 1.6e12 0 0 0 0 0 0 NC NC,NC,NC,NC,NC,NC,NC,NC !
U-Enriched 8.9e07 0 0 0 0 0 0 NC NC,NC,NC,NC,NC,NC,NC,NC !
Np-237 7.8e08 0 0 0 0 .01 .03 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Np-239 2.4e00 1600000 0.80e-8 0.22e-8 0 .01 .03 1.0e-3 13.8e00,13.0e00,12.0e00,10.4e00,5.8e00,1.8,2.0e-01,0.0 !
Pu-236 1.0e03 0 0 0 0 .01 .03 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Pu-238 3.2e04 57.027017 0 0 0 .01 .03 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Pu-239 8.8e06 21 0 0 0 .01 .03 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Pu-240 2.4e06 21 0 0 0 .01 .03 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Pu-241 5.3e03 3405.4045 0 0 0 .01 .03 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Pu-242 1.4e08 0 0 0 0 .01 .03 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Am-241 1.6e05 1.6999998 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Am-242m 5.5e04 0 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Am-243 2.7e06 0 0 0 0 0 0 1.0e-3 NC,NC,NC,NC,NC,NC,NC,NC !
Cm-242 1.6e02 500 0 0 0 0 0 NC NC,NC,NC,NC,NC,NC,NC,NC !
Cm-243 1.0e04 0 0 0 0 0 0 NC NC,NC,NC,NC,NC,NC,NC,NC !
Cm-244 6.6e03 23 0 0 0 0 0 NC NC,NC,NC,NC,NC,NC,NC,NC !
Cm-245 3.1e06 0 0 0 0 0 0 NC NC,NC,NC,NC,NC,NC,NC,NC !
Cf-252 9.6e02 0 0 0 0 0 0 NC NC,NC,NC,NC,NC,NC,NC,NC !
B. PARTICULATE/AEROSOL RELEASE REDUCTION FACTORS
_________________________________________________
Standby Gas Treatment System Filters:
- Dry-low pressure flow: 0.01
- Wet-high pressure flow (blowout): 1
Other Filters:
- Other dry-low pressure: 1
- Other wet-high pressure flow (blowout): 1
Suppression Pool Scrubbing:
- Pool sub-cooled 0.5-1.0 m: 0.5
- Pool sub-cooled 1.0-2.0 m: 0.1
- Pool sub-cooled >2.0 m: 0.05
- Pool saturated: 1
- Pool bypass: 1
Removal of Suspended Aerosols and Particulate:
- Natural processes, no sprays, <1 hour holdup time: 0.75
- Natural processes, no sprays, 1 to 12 hour holdup time: 0.36
- Natural processes, no sprays, >12 hour holdup time: 0.03
- Sprays on, <1 hour holdup time: 0.03
- Sprays on, 1 to 12 hour holdup time: 0.02
A1.29
- Sprays on, >12 hour holdup time: 0.01
Ice Condenser:
- One pass through condenser: 0.5
- Continual recirculation through condenser: 0.25
- Ice bed exhausted before core damage: 1
Primary System Retention (plate-out):
- Plate-out in bypass accidents: 0.2
Steam generator partitioning, liquid release from reactor cooling system:
- Steam generator partitioned: 0.02
- Steam generator not partitioned: 0.5
- Air ejector: 0.02
C. ESCAPE FRACTIONS
___________________
Primary containment failure leakage:
- PWR large dry or subatmospheric containment, design leakage: 0.00004
- PWR ice condenser, design leakage: 0.0001
- BWR, at 0.5%/day, design leakage: 0.0002
- Failure to isolate, 100%/day - via compromised isolation valve seal: 0.04
- Catastrophic failure, 100%/hour puff: 1
Steam generator tube rupture:
- SGTR 1 tube at full pressure, coolant leak 500 gpm (110 m3/h): 0.35
- SGTR 1 tube at low pressure single charging pump flow, coolant leak 50 gpm (11 m3/h): 0.03
A.1.5. Reference data in N-WATCHDOG dosimetry The User-interface format
THE MIX
_______
Build mix by
(i) discarding unnecessary lines,
(ii) entering the appropriate values for nuclide 'Activity'; and, if appropriate,
(iii) adjusting the dose conversion factors.
__________________________________________________________________________________
NUCLIDE ACTIVITY Halflife DCFe,50 DCFbone DCFlung DCFthyd DCFgi DCFai
. (mSv/h)/ (mSv/h)/ (mSv/h)/ (mSv/h)/ (mSv/h)/ (mSv/h)/
. (kBq) (d) (kBq/m3) (kBq/m3) (kBq/m3) (kBq/m3) (kBq/m2) (kBq/m3)
_______________________________________________________________________________________________________
H-3 1.0 4.5e03 5.40e-05 2.58e-06 2.58e-06 0.00e00 0.00e00 0.00e00
C-14 1.0 2.1e06 2.40e-03 2.27e-05 2.27e-05 0.00e00 4.57e-11 9.36e-09
Na-22 1.0 9.5e02 1.56e-03 0.00e00 0.00e00 0.00e00 7.38e-06 3.67e-04
Na-24 1.0 6.3e-01 3.24e-04 1.72e-04 1.34e-03 0.00e00 1.29e-05 7.49e-04
P-32 1.0 1.4e01 4.08e-03 4.50e-04 4.30e-03 0.00e00 3.07e-07 1.93e-06
P-33 1.0 2.5e01 1.80e-03 0.00e00 0.00e00 0.00e00 1.31e-10 5.22e-08
S-35 1.0 8.7e01 1.68e-03 7.50e-06 3.28e-04 0.00e00 4.79e-11 1.12e-08
Cl-36 1.0 1.1e08 8.76e-03 0.00e00 0.00e00 0.00e00 4.03e-08 5.98e-07
A1.30
K-40 1.0 4.7e11 2.52e-03 0.00e00 0.00e00 0.00e00 7.34e-07 2.85e-05
K-42 1.0 5.2e-01 1.44e-04 0.00e00 0.00e00 0.00e00 1.43e-06 5.33e-05
Ca-45 1.0 1.6e02 3.24e-03 0.00e00 0.00e00 0.00e00 1.36e-10 5.51e-08
Sc-46 1.0 8.4e01 8.16e-03 0.00e00 0.00e00 0.00e00 6.77e-06 3.37e-04
Ti-44 1.0 1.7e04 1.44e-01 0.00e00 0.00e00 0.00e00 4.25e-07 1.69e-05
V-48 1.0 1.6e01 2.88e-03 0.00e00 0.00e00 0.00e00 9.79e-06 4.90e-04
Cr-51 1.0 2.8e01 4.44e-05 3.56e-06 4.30e-05 0.00e00 1.07e-07 4.97e-06
Mn-54 1.0 3.1e02 1.02e-03 9.20e-05 3.00e-04 0.00e00 2.85e-06 1.38e-04
Mn-56 1.0 1.1e-01 1.44e-04 0.00e00 0.00e00 0.00e00 5.83e-06 2.94e-04
Fe-55 1.0 9.9e02 4.56e-04 1.11e-06 3.76e-05 0.00e00 0.00e00 0.00e00
Co-58 1.0 7.1e01 1.92e-03 6.90e-05 5.70e-04 0.00e00 3.33e-06 1.60e-04
Fe-59 1.0 4.5e01 4.44e-03 1.29e-04 1.21e-03 0.00e00 3.96e-06 2.02e-04
Co-60 1.0 1.9e03 1.20e-02 1.66e-04 1.46e-03 0.00e00 8.28e-06 4.28e-04
Ni-63 1.0 3.5e04 1.56e-03 3.16e-06 1.14e-04 0.00e00 0.00e00 0.00e00
Cu-64 1.0 5.3e-01 1.44e-04 0.00e00 0.00e00 0.00e00 6.59e-07 3.06e-05
Zn-65 1.0 2.4e02 1.92e-03 4.80e-05 2.60e-04 0.00e00 1.95e-06 9.79e-05
Ga-68 1.0 4.7e-02 5.88e-05 2.50e-06 2.52e-04 0.00e00 3.60e-06 1.54e-04
Ge-68 1.0 2.9e02 1.68e-02 0.00e00 0.00e00 0.00e00 2.37e-6 1.65e-4
Se-75 1.0 1.2e02 1.56e-03 5.30e-05 2.80e-04 0.00e00 1.30e-06 6.05e-05
Kr-85 1.0 3.9e03 1.98e-07 0.00e00 0.00e00 0.00e00 0.00e00 9.17e-07
Kr-85m 1.0 1.9e-01 1.26e-07 0.00e00 0.00e00 0.00e00 0.00e00 2.46e-05
Kr-87 1.0 5.3e-02 4.22e-07 0.00e00 0.00e00 0.00e00 0.00e00 1.42e-04
Kr-88 1.0 1.2e-01 1.01e-06 0.00e00 0.00e00 0.00e00 0.00e00 3.50e-4
Rb-86 1.0 1.9e01 1.12e-03 2.17e-04 1.88e-03 0.00e00 6.01e-07 1.78e-05
Rb-87 1.0 1.7e13 6.00e-04 0.00e00 0.00e00 0.00e00 2.63e-10 1.19e-07
Rb-88 1.0 1.2e-02 1.92e-05 0.00e00 0.00e00 0.00e00 2.67e-06 1.20e-04
Sr-89 1.0 5.1e01 7.32e-03 2.20e-04 3.92e-03 0.00e00 2.47e-07 1.57e-06
Sr-90 1.0 1.1e04 4.32e-02 2.36e-04 3.30e-03 0.00e00 5.90e-09 3.54e-07
Sr-91 1.0 4.00e-01 4.92e-04 0.00e00 0.00e00 0.00e00 2.62e-06 1.18e-04
Y-90 1.0 2.70e00 1.80e-03 9.30e-05 4.52e-03 0.00e00 3.96e-07 2.85e-06
Y-91 1.0 5.90e01 1.07e-02 9.90e-05 4.10e-03 0.00e00 2.69e-07 2.24e-06
Y-91m 1.0 3.5e-02 1.32e-05 0.00e00 0.00e00 0.00e00 1.84e-06 8.53e-05
Zr-93 1.0 5.6e08 3.00e-02 0.00e00 0.00e00 0.00e00 0.00e00 0.00e00
Zr-95 1.0 6.4e01 5.76e-03 2.05e-04 1.06e-03 0.00e00 2.53e-06 1.21e-04
Nb-94 1.0 7.4e06 5.88e-02 0.00e00 0.00e00 0.00e00 5.36e-06 2.59e-04
Nb-95 1.0 3.5e01 1.80e-03 7.00e-05 5.40e-04 0.00e00 2.62e-06 1.26e-04
Mo-99 1.0 2.8e00 1.07e-03 1.24e-04 2.04e-03 0.00e00 6.41e-07 2.52e-05
Tc-99 1.0 7.8e07 4.80e-03 1.20e-05 6.80e-04 0.00e00 2.33e-10 1.03e-07
Tc-99m 1.0 2.5e-01 2.28e-05 3.62e-06 3.52e-05 0.00e00 4.10e-07 1.89e-05
Ru-103 1.0 3.9e01 2.88e-03 6.10e-05 9.10e-04 0.00e00 1.62e-06 7.49e-05
Ru-105 1.0 1.9e-01 2.04e-04 0.00e00 0.00e00 0.00e00 2.82e-06 1.28e-04
Rh-106 1.0 3.5e-04 0.00e00 0.00e00 0.00e00 0.00e00 1.24e-06 3.82e-05
Ru-106 1.0 3.7e02 3.36e-02 2.39e-04 9.80e-03 0.00e00 1.24e-6 3.82e-5
Ag-110m 1.0 2.5e02 9.12e-03 2.30e-04 1.51e-03 0.00e00 9.29e-06 4.57e-04
Cd-109 1.0 4.6e02 9.72e-03 0.00e00 0.00e00 0.00e00 8.11e-8 1.75e-6
Cd-113m 1.0 5.0e03 1.32e-01 0.00e00 0.00e00 0.00e00 6.37e-09 3.26e-07
In-114m 1.0 5.0e01 1.12e-02 0.00e00 0.00e00 0.00e00 3.11e-07 1.40e-05
Sn-113 1.0 1.2e02 3.24e-03 0.00e00 0.00e00 0.00e00 7.06e-7 4.49e-5
Sn-123 1.0 1.3e02 9.72e-03 0.00e00 0.00e00 0.00e00 2.34e-07 2.51e-06
Sb-124 1.0 6.0e01 7.68e-03 2.82e-04 3.10e-03 0.00e00 6.12e-06 3.10e-04
Sb-126 1.0 1.2e01 3.36e-03 0.00e00 0.00e00 0.00e00 9.79e-06 4.61e-04
Sb-126m 1.0 1.3e-02 2.28e-05 0.00e00 0.00e00 0.00e00 5.58e-06 2.52e-04
Sb-127 1.0 3.9e00 2.04e-03 0.00e00 0.00e00 0.00e00 2.43e-06 1.12e-04
Sb-129 1.0 1.8e-01 2.76e-04 0.00e00 0.00e00 0.00e00 4.93e-06 2.42e-04
Te-127 1.0 3.9e-01 1.56e-04 0.00e00 0.00e00 0.00e00 3.71e-08 1.20e-06
A1.31
Te-127m 1.0 1.1e02 8.88e-03 1.32e-04 1.57e-03 0.00e00 3.08e-08 4.03e-07
Te-129 1.0 4.8e-02 4.44e-05 0.00e00 0.00e00 0.00e00 4.10e-07 1.03e-05
Te-129m 1.0 3.4e01 7.92e-03 2.72e-04 3.92e-03 0.00e00 2.05e-07 5.62e-06
Te-131 1.0 1.7e-02 3.36e-05 0.00e00 0.00e00 3.16e-03 1.71e-06 6.91e-05
Te-131m 1.0 1.3e00 1.13e-03 1.26e-04 1.64e-03 4.33e-02 4.82e-06 2.36e-04
Te-132 1.0 3.3e00 2.40e-03 9.90e-05 6.40e-04 3.00e-02 8.89e-06 4.21e-04
I-125 1.0 6.0e01 6.12e-03 5.44e-06 8.50e-05 1.20e-01 1.13e-07 1.34e-06
I-129 1.0 5.7e09 4.32e-02 5.66e-06 1.92e-04 8.52e-01 7.02e-08 1.01e-06
I-131 1.0 8.0e00 8.88e-03 2.38e-05 5.66e-04 1.80e-01 1.31e-06 6.08e-05
I-132 1.0 9.6e-02 1.13e-04 1.68e-05 3.24e-04 1.68e-03 7.92e-06 3.78e-04
I-133 1.0 8.7e-01 1.80e-03 2.74e-05 8.64e-04 3.36e-02 2.22e-06 9.94e-05
I-134 1.0 3.7e-02 5.40e-05 7.32e-06 1.68e-04 3.12e-04 9.11e-06 4.39e-04
I-135 1.0 2.8e-01 3.84e-04 2.64e-05 5.18e-04 6.84e-03 5.29e-6 2.71e-4
Xe-131m 1.0 1.2e01 0.00e00 0.00e00 0.00e00 0.00e00 0.00e00 1.33e-06
Xe-133 1.0 5.2e00 5.19e-07 0.00e00 0.00e00 0.00e00 0.00e00 5.00e-06
Xe-133m 1.0 2.2e00 0.00e00 0.00e00 0.00e00 0.00e00 0.00e00 4.58e-06
Xe-135 1.0 3.8e-01 6.81e-07 0.00e00 0.00e00 0.00e00 0.00e00 4.00e-05
Xe-135m 1.0 1.1e-02 0.00e00 0.00e00 0.00e00 0.00e00 0.00e00 6.67e-05
Xe-138 1.0 9.8e-03 0.00e00 0.00e00 0.00e00 0.00e00 0.00e00 1.96e-04
Cs-134 1.0 7.5e02 7.92e-03 2.01e-04 8.20e-04 0.00e00 5.33e-06 2.54e-04
Cs-135 1.0 8.4e08 8.28e-04 1.66e-05 2.02e-04 0.00e00 9.68e-11 3.42e-08
Cs-136 1.0 1.3e01 1.44e-03 2.26e-04 8.10e-04 0.00e00 7.31e-06 3.58e-04
Cs-137 1.0 1.1e04 5.52e-03 1.20e-04 8.60e-04 0.00e00 1.98e-06 9.18e-05
Cs-138 1.0 2.2e-02 2.88e-05 0.00e00 0.00e00 0.00e00 8.14e-06 4.14e-04
Ba-133 1.0 3.9e03 3.72e-03 0.00e00 0.00e00 0.00e00 1.34e-06 5.83e-05
Ba-137m 1.0 1.8e-03 0.00e00 0.00e00 0.00e00 0.00e00 2.08e-06 9.68e-05
Ba-140 1.0 1.3e01 6.12e-03 1.54e-04 1.18e-03 0.00e00 6.84e-07 2.91e-05
La-140 1.0 1.7e00 1.32e-03 2.16e-04 2.60e-03 0.00e00 7.78e-06 4.00e-04
Ce-141 1.0 3.3e01 3.84e-03 2.21e-05 1.17e-03 0.00e00 2.49e-07 1.12e-05
Ce-144 1.0 2.8e02 4.32e-02 1.02e-04 8.90e-03 0.00e00 6.55e-7 1.23e-5
Pr-144 1.0 1.2e-02 2.16e-05 0.00e00 0.00e00 0.00e00 5.87e-07 9.54e-06
Pr-144m 1.0 5.0e-03 0.00e00 0.00e00 0.00e00 0.00e00 3.78e-08 7.92e-07
Pm-145 1.0 6.5e03 4.32e-03 0.00e00 0.00e00 0.00e00 9.40e-08 1.98e-06
Pm-147 1.0 9.6e02 6.00e-03 9.40e-06 4.40e-04 0.00e00 1.01e-10 3.12e-08
Sm-147 1.0 3.9e13 1.15e01 0.00e00 0.00e00 0.00e00 0.00e00 0.00e00
Sm-151 1.0 3.3e04 4.80e-03 2.98e-06 1.33e-04 0.00e00 1.27e-11 8.86e-11
Eu-152 1.0 4.9e03 5.04e-02 1.13e-04 1.31e-03 0.00e00 3.89e-06 1.90e-04
Eu-154 1.0 3.2e03 6.36e-02 1.38e-04 2.36e-03 0.00e00 4.21e-06 2.07e-04
Eu-155 1.0 1.8e03 8.28e-03 2.04e-05 4.50e-04 0.00e00 1.93e-07 7.70e-06
Gd-153 1.0 2.4e02 2.52e-03 0.00e00 0.00e00 0.00e00 3.32e-07 1.12e-05
Tb-160 1.0 7.2e01 8.40e-03 0.00e00 0.00e00 0.00e00 3.82e-06 1.87e-04
Ho-166m 1.0 4.4e05 1.44e-01 0.00e00 0.00e00 0.00e00 5.94e-06 2.82e-04
Tm-170 1.0 1.3e02 8.40e-03 0.00e00 0.00e00 0.00e00 9.50e-08 1.32e-06
Yb-169 1.0 3.2e01 3.00e-03 7.10e-05 9.90e-04 0.00e00 1.00e-06 4.07e-05
Hf-172 1.0 6.8e02 3.84e-02 0.00e00 0.00e00 0.00e00 3.57e-07 1.22e-05
Hf-181 1.0 4.2e01 6.00e-03 0.00e00 0.00e00 0.00e00 1.89e-06 8.71e-05
Ta-182 1.0 1.1e02 1.20e-02 0.00e00 0.00e00 0.00e00 4.32e-06 2.16e-04
W-187 1.0 1.0e00 2.28e-04 0.00e00 0.00e00 0.00e00 1.68e-06 7.67e-05
Ir-192 1.0 7.4e01 7.92e-03 1.02e-04 1.77e-03 0.00e00 2.80e-06 1.30e-04
Au-198 1.0 2.7e00 1.03e-03 0.00e00 0.00e00 0.00e00 1.47e-06 6.52e-05
Hg-203 1.0 4.7e01 2.88e-03 0.00e00 0.00e00 0.00e00 7.99e-07 3.74e-05
Tl-204 1.0 1.4e03 4.68e-04 0.00e00 0.00e00 0.00e00 3.89e-08 6.16e-07
Pb-210 1.0 8.1e03 6.72e00 6.32e-05 1.93e-02 0.00e00 7.67e-09 1.61e-07
Bi-207 1.0 1.4e04 6.72e-03 0.00e00 0.00e00 0.00e00 5.22e-06 2.53e-04
Bi-210 1.0 5.0e00 1.12e-01 0.00e00 0.00e00 0.00e00 1.26e-07 9.29e-07
A1.32
Po-210 1.0 1.4e02 3.96e00 7.70e-03 3.54e-01 0.00e00 2.91e-11 1.40e-09
Ra-226 1.0 5.8e05 4.20e00 1.55e-03 3.18e-01 0.00e00 2.20e-08 1.02e-06
Ac-227 1.0 7.9e03 2.64e02 0.00e00 0.00e00 0.00e00 5.08e-10 1.84e-08
Ac-228 1.0 2.6e-01 3.00e-02 0.00e00 0.00e00 0.00e00 3.38e-06 1.62e-04
Th-227 1.0 1.9e01 1.02e01 1.91e-02 5.51e-01 0.00e00 3.53e-07 1.59e-05
Th-228 1.0 7.0e02 4.80e01 3.07e-02 7.91e-01 0.00e00 7.67e-09 2.92e-07
Th-230 1.0 2.8e07 1.20e02 9.80e-03 3.30e-01 0.00e00 2.29e-09 5.33e-08
Th-231 1.0 1.1e00 3.72e-04 0.00e00 0.00e00 0.00e00 5.58e-08 1.65e-06
Th-232 1.0 5.1e12 1.32e02 8.40e-03 2.78e-01 0.00e00 1.64e-09 2.61e-08
Pa-231 1.0 1.2e07 1.68e02 6.71e-03 3.51e-01 0.00e00 1.36e-07 5.65e-06
Pa-233 1.0 2.7e01 4.68e-03 0.00e00 0.00e00 0.00e00 6.70e-07 3.08e-05
U-232 1.0 2.6e04 9.36e00 3.34e-03 3.74e-01 0.00e00 2.91e-09 4.21e-08
U-233 1.0 5.8e07 4.32e00 0.00e00 0.00e00 0.00e00 2.16e-09 5.11e-08
U-234 1.0 8.9e07 4.20e00 2.96e-03 3.34e-01 0.00e00 2.11e-09 2.20e-08
U-235 1.0 2.6e11 3.72e00 2.80e-03 3.08e-01 0.00e00 5.04e-07 2.33e-05
U-236 1.0 8.5e09 3.84e00 2.80e-03 3.14e-01 0.00e00 1.81e-09 1.39e-08
U-238 1.0 1.6e12 3.48e00 2.61e-03 2.94e-01 0.00e00 1.52e-09 9.00e-09
Udepleted/na 1.0 1.6e12 3.84e01 2.61e-03 2.94e-01 0.00e00 1.39e-09 1.23e-08
Uenriched 1.0 8.9e07 4.30e01 2.96e-03 3.34e-01 0.00e00 1.88e-09 2.74e-08
UF6 1.0 8.9e07 8.65e-04 2.96e-03 0.00e00 0.00e00 1.88e-09 2.74e-08
NP-237 1.0 7.8e08 2.76e01 7.32e-03 3.19e-01 0.00e00 9.07e-08 3.19e-06
NP-239 1.0 2.4e00 1.12e-03 3.70e-05 1.23e-03 0.00e00 5.54e-07 2.50e-05
Pu-236 1.0 1.0e03 4.80e01 0.00e00 0.00e00 0.00e00 2.65e-09 1.68e-08
Pu-238 1.0 3.2e04 5.52e01 8.30e-03 3.78e-01 0.00e00 2.25e-09 1.26e-08
Pu-239 1.0 8.8e06 6.00e01 7.90e-03 3.56e-01 0.00e00 1.02e-09 1.25e-08
Pu-240 1.0 2.4e06 6.00e01 7.90e-03 3.58e-01 0.00e00 2.16e-09 1.23e-08
Pu-241 1.0 5.3e03 1.08e00 1.06e-06 4.84e-05 0.00e00 6.19e-12 2.28e-10
Pu-242 1.0 1.4e08 5.76e01 7.30e-03 3.38e-01 0.00e00 1.79e-09 1.04e-08
Am-241 1.0 1.6e05 5.04e01 8.22e-03 3.70e-01 0.00e00 8.39e-08 2.43e-06
Am-242m 1.0 5.5e04 4.44e01 0.00e00 0.00e00 0.00e00 8.14e-09 8.96e-08
Am-243 1.0 2.7e06 4.92e01 7.94e-03 3.55e-01 0.00e00 1.72e-07 6.66e-06
Cm-242 1.0 1.6e02 6.24e00 9.20e-03 4.08e-01 0.00e00 2.53e-09 1.45e-08
Cm-243 1.0 1.0e04 3.72e01 8.84e-03 3.93e-01 0.00e00 4.25e-07 1.91e-05
Cm-244 1.0 6.6e03 3.24e01 8.80e-03 3.92e-01 0.00e00 2.32e-09 1.22e-08
Cm-245 1.0 3.1e06 5.04e01 0.00e00 0.00e00 0.00e00 2.90e-07 1.26e-05
Cf-252 1.0 9.6e02 2.40e01 0.00e00 0.00e00 0.00e00 1.89e-09 1.31e-08
A.1.6. Nuclear emergency-oriented knowledge elements and guides Primary source: U.S. NRC, DOE, EPA, FRMAC
1. EVENT DIAGNOSE GUIDES
_________________________________________________________________________
IDENTIFY WHERE Color BASIS - DRLs CAUTION-NOTES
_________________________________________________________________________
Emergency Worker Exposure rate and Limits based on expo
Limits are inhalation dose rates - valid only
Exceeded estimates (Manual's for releases with
Method 2.1) substantial gamma
emitters.
__________________________________________________________________________
A1.33
Early Health Effects Red Exposure rate Based on expo rates
Possible > 1000 R/h only and valid only
(Method 3.1 & 3.2) for accidents where
inhalation is not
important. Area may
expand once addi-
tional data becomes
available.
Isotopic analysis This may change as
considering external additional analysis
exposure and inhala- is performed
lation (Method 3.1 &
3.2)
Early Phase PAG Red Exposure rate Based on expo rates
exceeded > 10 mR/h only expo rates only
(Method 3.1 & 3.2) and valid only for
accidents where
inhalation is not
important. Area may
expand as additional
information becomes
available.
Isotopic analysis
considering external
exposure and inhalation
(Method 3.1 & 3.2)
_________________________________________________________________________
Intermediate Phase Blue Exposure rate Based on expo rates
Relocation PAGs > 0.2 mR/h or LWR only and valid only
Exceeded curves for accidents where
( Restricted Zone) (Method 4.1) resuspension is not
important. This may
change as additional
analysis performed.
Isotopic analysis This may change as
considering external additional analysis
exposure and inhala- is performed.
tion. (Method 4.2)
Short term Blue Exposure rate Areas identified
consumption of food > background or LWR based on expo rates.
produced in these curves Most likely to be
areas may exceed (Method 5.1) expanded as additio-
Ingestion PAGs. nal analysis availbl.
Isotopic analysis of Areas may change
ground contamination based on food & water
(Method 5.2 & 5.3) sample analysis.
Food & water samples This may change as
(Method 5.4 & 5.5) additional analysis
A1.34
is performed.
_________________________________________________________________________
Detectable contamina- Green Isotopic analysis. No person exceeding
tion but no identi- All concentrations any of the Federal
fiable short term below DRLs indicating or State PAG. May
concern PAGs exceeded change on more info.
_________________________________________________________________________
Monitored -- no iden- Black May change on more
tifiable contamination information.
__________________________________________________________________________
2. GUIDANCE ON DOSE LIMITS FOR WORKERS PERFORMING EMERGENCY SERVICES
_________________________________________________________________________
TEDE EYE Other Organ
Dose Limit(a) Dose Limit Thyroid Activity Condition
(mrem) (mrem) Skin Limit (mrem)
_________________________________________________________________________
5,000 15,000 50,000 All
10,000 30,000 100,000 Protecting Lower dose
valuable not practicable
property
25,000 75,000 250,000 Life saving Lower dose
or protectn. not practicable
of large
populations
>25,000 >75,000 >250,000 Life saving Only on a
or protectn. voluntary basis
of large by persons
populations fully aware of
the risks
involved.
(Table 2.2, 2.3)
_________________________________________________________________________
a) Summ of External Effective Dose Equivalent and Committed Effective
Dose Equivalent to nonpregnant adults from exposure and intake
during an emergency situation. Workers performing services during
emergencies should limit dose to the lens of the eye to three times
the listed value and doses to any other organ (including skin and
body extremities) to ten times the listed value. Limits apply to all
doses from an incident, except those received in unrestricted areas
as members of the public during the Intermediate Phase (Chaptrs 3,4).
Source: EPA92
A1.35
3. HEALTH EFFECTS ASSOCIATED WITH WHOLE BODY ABSORBED DOSES OVER A FEW HOURS
________________________________________________________________________
Whole Body Early Whole Body Prodromal
Absorbed Dose Fatalities (a) Absorbed Dose Effects (b)
(rad) (percent) (rad) (percent affected)
_________________________________________________________________________
140 5 50 2
200 15 100 15
300 50 150 50
400 85 200 85
460 95 250 98
_________________________________________________________________________
N.B. Risks will be lower for protracted exposure periods.
a) Supportive medical treatment may increase the dose at which these
frequencies occur by approximately 50%.
b) Forwarning symptoms of more serious health effects associated with
large doses of radiation.
Source: EPA92
4. APPX.CANCER RISK TO AVERAGE INDIVIDUAL FROM 25 REM EDE DELIVERED PROMPTLY
_________________________________________________________________________
Age at Appropriate risk Average Years of Life Lost
Exposure of premature death if premature death occurs
(years) (deaths per 1,000 (years)
persons exposed)
_________________________________________________________________________
20 to 30 9.1 24
30 to 40 7.2 19
40 to 50 5.3 15
50 to 60 3.5 11
_________________________________________________________________________
Source: EPA92
5. LWR ACCIDENT INTEGRATED EXPOSURE EMERGENCY WORKER TURN BACK LIMITS
__________________________________________________________________________
Turn Back Limit
___________________________________________
Integrated Exposure Reading on Self Reading
Dosimeter That Must Not Be Exceeded
Emergency Activity -------------------------------------------
KI not taken KI taken Certified
(a) before respiratory pro-
exposure tection used or
(b) confirmation of
no inhalation dose
A1.36
possible (c)
_________________________________________________________________________
mR mR mR
_________________________________________________________________________
All 250 - 500 1000 5000
Protecting valuable 500 - 1000 2000 10000
property
Life saving or 1250 - 2500 5000 25000
protecting large
populations
Life saving or >1250 - 2500 >5000 >25000
protecting large
populations
Voluntary (d)
_________________________________________________________________________
Note: These are the readings on a self-reading dosimeter (integrated
exposure) that indicate that the Emergency Worker Limits for TEDE
listed in Manual's Table 2.1 may be exceeded from external exposure
and inhalation. The limits only apply to LWR accidents involving
core damage.
-------------------------
a) Based on the thyroid dose and limit; use the lower limit if core
damage and a substantial release of iodine is confirmed.
b) Based on TEDE limit.
c) Assume no inhalation dose.
d) On a voluntary basis by persons fully aware of the risks. Use
Manual's Tables 2.3, 2.4, and 3.1 to illustrate risks.
6. EARLY PHASE PRIORITIZED TASKS I
_________________________________________________________________________
CRUCIAL TASKS NECESSARY INFORMATION METHOD
_________________________________________________________________________
Determine if Early Isotopic mix (relative abun- M.3.1 Calculate the
Effects Thresholds dance) based on in-situ mea- Early Phase Dose from
or Early Phase PAGs surements, references, or Exposure Rates, Air
may be exceeded. information provided by Concentrations or
operator Depositions.
AND
Maximum Exposure Rate (mR/h)
in the plume @ 1m AGL
AND/OR
Airborne concentrations &
Depositions
Project the distance Results from Method 3.1 M.3.4 Project Expo-
to which PAGs or sure, Dose or Con-
Early Phase Effects centrations downwind
A1.37
may be exceeded. from a measurement.
Early Phase PAG
exceeded
After plume passage, Isotopic mix (relative abun- M.3.2 Calculate Expo-
evaluate deposition dance) based on in-situ mea- sure rate DRL or
and develop DRLs to surements, references or Marker Isotope Con-
determine if Early information provided by centration DRL for
Phase PAGs may be operator Deposition.
exceeded. AND
BASED ON ACCIDENT TYPE
CHOOSE ONE:
Accidents where exposure rate
measurements identify the
area of concern. Maximum
exposure rate (mR/h) in the
plume @ 1m AGL
OR
Accidents where resuspension
is a concern and exposure
rates are insufficient to
identify the area of concern.
* Deposition of a gamma-
emitting 'Marker Isotope'
easily identified in the
field or lab
OR
* When no gamma emitter is
detectable, comprehensive
isotopic analysis of depo-
sition.
_________________________________________________________________________
7. EARLY PHASE PRIORITIZED TASKS II (CONTINUED)
_________________________________________________________________________
CRUCIAL TASKS NECESSARY INFORMATION METHOD
_________________________________________________________________________
--- continued ---
Recalculate or con- Resuspension air concentra- M.3.7 Estimate re-
firm resuspension tions relative to deposition suspension factors
factors based on (uCi/m3)/(uCi/m2) based on samples.
actual data to ad-
just DRL or dose.
Estimate or confirm Airborne Concentrations M.3.8 Estimate release
reelease rates for rates based on Air-
input into model borne Concentrations.
calculations or to
characterize an
unmonitored release.
Estimate release M.3.9 Project release
mixture or doses and environmental
A1.38
before field concentrations for
measurements are reactors, facilities
available and point sources.
Estimate future Maximum Exposure Rate M.3.6 Estimate future
dose rates to the (mR/h) @ 1m AGL. Exposure (or Dose)
public or emergency Rates from Deposition
workers remaining
on deposition.
Consideration of Comprehensive isotopic M.3.3 Calculate Early
isotopes not con- analysis of deposition. Phase Deposition DCF
tained in Table Resuspension air concen- for unlisted isotopes
3.4 or to consider trations relative to or different resuspen-
different resus- deposition sion factors.
pension factors. (uCi/m3)/(uCi/m2)
Estimate dose reduc- Maximum exposure rate M.3.5 Calculate Dose
tion due to shiel- (mR/h) in the plume or @ reduction due to
ding from the plume 1m AGL. Sheltering.
and ground contami-
nation.
Consideration of M.3.10 Calculate air
isotopes not con- Submersion, Ground
tained in Tables Shine and Inhalation
3.3 or 3.4 or to DCF for unlisted iso-
consider different topes or to adjust
assumptions. assumptions.
_________________________________________________________________________
8. HEALTH EFFECTS OF EXPOSURE TO RADIATION
_________________________________________________________________________
Dose Dose
Organ Rate Threshold (e) Acute Health Effects
(rem/h) (rem)
_________________________________________________________________________
External >6 50 Vomiting might occur
Effective (c) 100 Diarrhea might occur
External >6 150 50% vomiting occurs
Effective (c) 300 50% diarrhea occurs
(high dose rates - in 1-3 hrs (a)
Thyroid >6 >3,000 Hypothyroidism (within 6 months)
Lung 1,000 700 Deaths might occur
Lung 100 2,000 Deaths might occur
Lung 50 4,000 Deaths might occur
Lung 10 16,000 Deaths might occur
A1.39
Marrow/WB(c) 1,000 150 Deaths might occur (d,e)
Marrow/WB(c) 5 220 Deaths might occur (d,e)
Marrow/WB(c) 5 440 50% deaths (d)
Marrow/WB(c) 1 500 Deaths might occur (d,e)
Marrow/WB(c) 1 1,000 50% deaths (d)
Skin short,one 300-1,000 Erythema (in approximately 18 d)
exposure
Skin short,one 2,000-3,000 Erythema (in approximately 2-6 d)
exposure
Skin 200 rem/d 2,000-4,000 Erythema (in approx. 12-17 d)
Tissue short,one 3,000 rem + Tissue killed,
exposure must be surgically removed (b)
_________________________________________________________________________
N.B. Source: NRC89 except where noted: (a) IAEA74; (b) NRC82
(c) EDE from external sources (cloud and ground shine) is approximately
equal to Bone Marrow and Whole Body (WB) dose.
(d) For minimal treatment which involves no medical treatment beyond basic
first aid. Thresholds will be about 50% higher for supportive treat-
ment which involves the maximum medical treatment available in a nor-
mal hospital, but does not include bone marrow transplants.
(e) This is a threshold. Actual occurences at this level are unlikely.
(f) Thresholds are dose rate dependent.
9. EARLY PHASE PAGS
_________________________________________________________________________
Protective PAG (Pep) Comments
Action Projected Dose
_________________________________________________________________________
Evacuation (a) 1-5 rem TEDE (b) Evacuation (or for some situations
or Sheltering 5-25 rem thyroid sheltering (a)) should normally be
50-500 rem skin initiated at 1 rem.
Administration 25 rem (c) Requires approval of State Medical
of stable iodine (25,000 mrem) Officials.
_________________________________________________________________________
N.B. Source: EPA92
a) Sheltering may be the preferred protective action when it will
provide protection equal to or greater than evacuation, based on
consideration of factors such as source term characteristics, and
temporal or other site-specific conditions.
b) The sum of the Effective Dose Equivalent (EDE) from exposure to
external sources and the Commited Effective Dose Equivalent (CEDE)
A1.40
incurred from all significant inhalation pathways during the early
phase. Committed dose equivalents (CDE) to the thyroid and skin
may be 5 and 50 times larger, respectively.
c) Committed Dose Equivalent (CDE) to the Thyroid from radioiodine.
10. STABILITY CLASSES & RELATIONSHIP TO STANDARD DEVIATION OF WIND DIRECTION
_________________________________________________________________________
Standard deviation Delta T
Class Description of horizontal wind (Lapse Rate)
direction (degrees) deg.C/100m
(sigma-theta)
_________________________________________________________________________
A Extremely unstable conditions 25 < -0.19
B Moderately unstable conditions 20 -1.9 to -1.7
C Slightly unstable conditions 15 -1.7 to -1.5
D Neutral conditions 10 -1.5 to -0.5
E Slightly stable Conditions 5 -0.5 to 1.5
F Moderately stable conditions 2.5 1.5 to 4.0
_________________________________________________________________________
Source: DOE84, page 591.
11. RELATIONSHIP OF STABILITY TO WEATHER CONDITIONS
________________________________________________________________________
Daytime insolation Nighttime
Surface (Solar radiation) conditions Day or night
winds ---------------------- -------------------------- Heavy
(m/s) Strong Moderate Slight Thin overcast <3/8 clouds overcast
or >4/8 clouds
_________________________________________________________________________
<2 A A-B B - - D
2 A-B B C E F D
4 B B-C C D E D
6 C C-D D D D D
>6 C D D D D D
________________________________________________________________________
Source: DOE84, page 221.
12. DILUTION FACTORS (DF XU/Q 1/M2)
_________________________________________________________________________
A1.41
STABILITY
-------------------------------------------------------------------------
Miles class A class B class C class D class E class F
_________________________________________________________________________
<=.25 1.0E-03 1.0E-03 1.0E-03 1.0E-03 1.0E-03 1.0E-03
1.0 1.0E-06 6.0E-06 1.7E-05 5.4E-05 1.1E-04 2.5E-04
2.0 7.0E-07 1.5E-06 5.0E-06 2.0E-05 4.0E-05 1.0E-04
3.0 4.5E-07 6.5E-07 2.2E-06 1.2E-05 2.5E-05 6.0E-05
4.0 3.5E-07 4.5E-07 1.2E-06 8.0E-06 1.6E-05 4.0E-05
5.0 3.0E-07 4.0E-07 9.5E-07 5.0E-06 1.1E-05 3.0E-05
10.0 1.7E-07 2.2E-07 3.0E-07 2.0E-06 5.0E-06 1.2E-05
15.0 1.2E-07 1.5E-07 2.0E-07 1.0E-06 2.6E-06 7.0E-06
20.0 9.5E-08 1.1E-07 1.7E-07 7.0E-07 2.0E-06 5.0E-06
25.0 8.0E-08 9.0E-08 1.3E-07 4.5E-07 1.4E-06 4.0E-06
_________________________________________________________________________
Source: EPA70, Figures 3-5a through 3-5f
at a vertical dispersion limit of 1000 m
and a ground level release.
a) These factors are dominated by building wake. They are based on
an interpretation of NRC88, Figures 5, 6 and 7, pp 25-27.
13. REPRESENTATIVE SHIELDING FACTORS FROM GAMMA CLOUD SOURCE
_______________________________________________
Structure or location Shielding factor(a)
_______________________________________________
Outside 1.0
Vehicles 1.0
Wood-frame house (b) 0.9
(no basement)
Basement of wood house 0.6
Masonry house 0.6
(no basement)
Basement of masonry house 0.4
Large office 0.2
of industrial building
a) The ratio of the interior dose
to the exterior dose.
b) A wood frame house with brick or stone
veneer is approximately equivalent to a
masonry house, for shielding purposes.
_______________________________________________
A1.42
Source: EGG75
14. REPRESENTATIVE SHIELDING FACTORS FROM SURFACE DEPOSITION
_________________________________________________________________________
Structure or location Representative shielding factor (a)
_________________________________________________________________________
Cars on fully contaminated road 0.50
Cars on fully decontaminated 50-ft road 0.25
Trains 0.40
One- and two-story wood frame house 0.40 (b)
(no basement) 0.20 (b)
One- and two-story block and brick 0.1 (b)
house (no basement)
House basement, one or two walls
fully exposed:
- One story, less than 2 ft of basement, 0.05 (b)
wall exposed
- Two stories, less than 2 ft of basement, 0.03 (b)
wall exposed
Three- or four-story structures,
5,000 to 10,000 sq.ft. per floor:
- First and second floors 0.05 (b)
- Basement 0.01 (b)
Multi-story structures,
> 10,000 sq.ft. per floor:
- Upper floors 0.01 (b)
- Basement 0.005 (b)
_________________________________________________________________________
a) The ratio of the interior dose to the exterior dose.
b) Away from doors and windows.
Source: EGG75
15. PRINCIPAL DOSE CONTRIBUTORS (90%) FROM SEVERE CORE DAMAGE ACCIDENTS
_________________________________________________________________________
Principal Dose-Contributing Isotopes
for a LWR Core Damage Accident
A1.43
-------------------------------------------------------------------------
External (a) External (a) Bone (a) Ingestion (b) 1st yr from
exposure Exposure Marrow @ Day 7 Deposition
from plume from Plume External &
Deposition Inhalation Resuspension
(1st day) (c)
_________________________________________________________________________
I-132 Te-132 Te-132 I-131 Cs-134
I-135 I-133 Sr-89 Ba-140 Cs-137
I-133 I-135 Ba-140 Te-132 Ba-140
Kr-88 I-132 Cs-134 La-140 I-131
Te-132 I-131 I-131 Sr-89 Te-132
I-131 Te-131m I-133 Ce-144 Zr-95
Sb-129 Ba-140 Cs-137 Sr-90 La-140
Xe-135 La-140 I-135 I-133 Cs-136
Te-131m Sb-129 Cs-136 Te-129m Ru-103
I-134 Np-239 I-132 Np-239 Nb-95
Xe-133 Ru-103 I-132 Ru-106
Sr-90 Cs-134 Ce-144
Te-131m Ru-106 Pu-241
Y-91 Ce-141 Pu-238
Te-129m Y-91 Ce-141
_________________________________________________________________________
a) Source: WASH1400
b) Principal isotopes contributing to ingestion dose from those remaining
on Day 7 after shutdown.
c) Principal isotopes contributing to the 1st year dose from external
exposure and resuspension.
Listed are the isotopes that are projected to be the principal
contributors (>90%) to dose resulting from a severe core damage accident
and a major release.
16. ICRP-RECOMMENDED BREATHING RATES FOR THE REFERENCE MAN
_________________________________________________________________________
Minute Volume for Reference Man
----------------------------------------------------------
Adult man Adult woman Child(10 y) Infant(1 y) Newborn
_________________________________________________________________________
Resting 7.5 6.0 4.8 1.5 0.5
(L/min)
Light 20.0 19.0 13.0 4.2 1.5
Activity
(L/min)
Liters of air breathed for Reference Man
----------------------------------------
8 hr light 9600 9100 6240 2500 (10h) 90 (1h)
activity (L)
A1.44
8 hr resting 3600 2900 2300 1300 (14) 690 (23h)
(L)
24 hr (L) (a) 23000 21000 15000 3800 800
_________________________________________________________________________
Source: ICRP74 (ICRP-23)
a) Includes 16 hr light activity and 8 hr resting except where noted.
17. RELOCATION ASSESSMENT PRIORITIZED TASKS I
_________________________________________________________________________
CRUCIAL TASKS NECESSARY INFORMATION METHOD
_________________________________________________________________________
For LWR and other Exposure Rates (mR/h) M.4.1 Evaluate depo-
accidents where in- @ 1m AGL sition exposure rates.
halation is not im-
portant, identify
where are relocation
concerns.
For accidents where Isotopic mix (relative M.4.2 Calculate expo-
inhalation may be abundance) based on in- sure rate DRLs for
important & with situ measurements, refe- deposition.
gamma emitters, rences or information
identify where there provided by operator
are relocation AND
concerns. BASED ON ACCIDENT TYPE
CHOOSE ONE
Accidents where exposure
rates identify the area
of concern - maximum expo-
sure rates (mR/h) @ 1 m AGL
OR
Accidents where resuspension
is a concern and exposure
rates are insufficient to
identify the area of concern -
deposition of a gamma-emitting
'Marker Isotope' easily iden-
tified in the field or lab.
For accidents where Resuspension air concentra- M.4.8 Estimate Inter-
resuspension is cri- tions relative to deposi- mediate Phase Resus-
tical, recalculate tions (uCi/m3)/(uCi/m2) pension Factors based
or confirm DRLs or on samples.
dose based on mea-
sured (vs assumed)
resuspension factors.
For accidents where Air concentrations in M.4.6 Calculate
inhalation is impor- populated areas Intermediate Phase
tant & with no dis- AND (Relocation) Dose
A1.45
cernable gamma emit- Comprehensive isotopic from deposition.
ter in deposition, analysis of deposition.
identify where there
are relocation
concerns.
_________________________________________________________________________
18. RELOCATION ASSESSMENT PRIORITIZED TASKS II (CONTINUED)
_________________________________________________________________________
CRUCIAL TASKS NECESSARY INFORMATION METHOD
_________________________________________________________________________
--- continued ---
Consider isotopes Rsuspension air concentra- M.4.3 Calculate DCFs
not listed in the tions relative to ground for deposition for un-
Tables or consider concentrations listed isotopes or
different resuspen- (uCi/m3)/(uCi/m2). different resuspension
sion factors. Deposition. factors.
Estimate future Isotopic concentration M.4.4 Calculate future
deposition mix to (relative abundance) based isotopic activity.
calculate DRL curves on in-situ measurements,
as a function of references or information
time. provided by operator.
Estimate dose reduc- Maximum exposure rates M.4.5 Calculate dose
tion due to partial (mR/h @ 1m AGL) reduction due to par-
occupancy and decon- tial occupancy and
tamination. decontamination.
Calculate Inter- Isotopic concentration M.4.6 Calculate the
mediate Phase dose (relative abundance) based Intermediate Phase
from deposited on in-situ measurements, (Relocation) dose
material. references or information from deposition.
provided by operator
This method should AND
not be used for ge- BASED ON ACCIDENT TYPE
neral assessment of CHOOSE ONE
environmental data; Accidents where exposure
DRLs should be used rates identify the area of
(Method 4.2). concern - maximum exposure
rates (mR/h @ 1m AGL)
For accidents where OR
resuspension is cri- Accidents where resuspen-
tical, recalculate sion is a concern and
or confirm DRLs or exposure rates are insuf-
dose based on mea- ficient to identify the
sured (vs assumed) area of concern.
resuspension factors. * Deposition of a gamma
emitting 'Marker Iso-
For accidents where tope' easily identi-
inhalation is impor- fied in the field or
tant & with no dis- lab
A1.46
cernable gamma emit- OR
ter in deposition, * When no gamma emitter
identify where there is detectable perform
are relocation comprehensive isotopic
concerns. analysis of deposition.
Y and Sr accidents: Deposition isotopic con- M.4.7 Calculate the
estimate skin dose centration based on in-situ skin dose from depo-
and see if Relocation measurements, references or sition resuspension.
PAGs are exceeded. information by operator.
_________________________________________________________________________
19. PAG & LTO FOR EXP.TO DEPOSITED RADIOACTIVE MATERIAL INTERMEDIATE PHASE
_________________________________________________________________________
Protective Action PAG (Pr) Comments
(Projected 1st year dose)
_________________________________________________________________________
Relocate the >= 2000 mrem EDE (a)
general population. (b)
> 100,000 mrem beta skin dose
Apply simple dose < 2000 mrem These protective
reduction techniques (c) actions should
be taken to re-
duce doses to as
low as practica-
ble levels.
_________________________________________________________________________
Source: EPA92
a) The projected sum of effective dose equivalent from external gamma
radiation and committed effective dose equivalent from inhalation of
resuspended materials, from exposure or intake during the first year.
Projected dose refers to the dose that would be received in the ab-
sence of shielding from structures or the application of dose reduc-
tion techniques. These PAG may not provide adequate protection from
some long-lived radionuclides; therefore, 1) doses in any single year
after the first will not exceed 0.5 rem, and 2) the cumulative dose
over 50 years (including the 1st and 2nd years) will not exceed 5 rem.
b) Persons previously evacuated from areas outside the relocation zone
defined by this PAG may return to occupy their residences. Cases in-
volving relocation of persons at high risk from such action (e.g.
patients under intensive care) should be evaluated individually.
c) Simple dose reduction techniques include scrubbing and/or flushing
hard surfaces, soaking or plowing soil, minor removal of soil from
spots where radioactive materials have concentrated, and spending
more time than usual indoors or in other low exposure rate areas.
_________________________________________________________________________
A1.47
LONG TERM OBJECTIVES
-------------------------------------------------------------------------
Period Objective (b)
2nd year (a) ............................. 500 mrem
50 years ................................. 5000 mrem
_________________________________________________________________________
Source: EPA92
a) Any single year after the first year.
b) The projected sum of Effective Dose Equivalent from external gamma
radiation and Committed Effective Dose Equivalent from inhalation
of resuspended materials.
20. REDUCTION IN CS-137 EXTERNAL GAMMA DOSES FROM DECONTAMINATION
_________________________________________________________________________
Technique Time applied % Dose reduction (a)
1 year 50 years
_________________________________________________________________________
LOW IMPACT
Washing/vacuuming indoor 7 d neg neg
surfaces
Ammonium nitrate on buildings 30 d - 1 yr 1 1
Firehosing on buildings 1 - 7 d
MED IMPACT
Sweeping roads 7 d 10 5
Sandblasting buildings 30 d - 1 yr 5 5
Roof replacement 30 d - 1 yr 5 5
Grass cutting 7 d 10 10
Road planning 1 yr -- 10
HIGH IMPACT
Vacuum-sweeping roads 7 d 25 15
Firehosing roads 1 - 7 d 25 15
Soil removal to 10 cm 30 d - 1 yr 30 55
Ploughing soil to 30 cm 30 d - 1 yr 35 55
Road planning 30 d 45 25
_________________________________________________________________________
a) The dose reduction indicates the amount by which the total dose from
urban surfaces is reduced by the technique indicated.
Source: IAEA93, based on Chernobyl experience.
21. DECON EFFECTIVENESS - WEAPONS - TEMPERATE WEATHER
_________________________________________________________________________
Method Rate DF
A1.48
(100 ft2/h)
_________________________________________________________________________
1. Roofs
a. Firehosing
1. Composition shingle 12 - 60 10 - 35
2. Tar and gravel 7 - 35 8 - 100
b. Firehosing and scrubbing
1. Tar and gravel 5 50
2. Composition shingle 5 50
3. Wood shingle 5 10
4. Corrugated sheet metal 5 100
2. Paved areas
a. Motorized flushers 100 - 300 25 - 50
b. Street sweepers 25 - 100 6 - 25
c. Vacuumized sweepers 25 - 100 4 - 50
d. Firehosing 5 - 25 15 - 50
3. Unpaved land areas
a. Grading (few inch.) 60 15
b. Ploughing 25 5
c. Scraping (several in.) 9 50
d. Bulldozing (several in.) 8.5 15
e. Filling
1. 6-in. fill 4 7
2. 12-in. fill 2 50
_________________________________________________________________________
Source: IAEA74
22. TYPICAL DECON EFFECTIVENESS - WEAPONS
_________________________________________________________________________
Material 1 2 3 4 5
_________________________________________________________________________
Glass 98 98 100 100 97
Painted wood 99 98 99 100 91
Asphalt 72 92 98 92 22
Concrete 74 98 96 100 21
Unpainted wood 36 85 99 99 85
_________________________________________________________________________
Notes:
1 = Vacuum method
2 = High pressure water
3 = High pressure water plus detergent
4 = Sandblasting
5 = Steam cleaning
Source: IAEA74
23. DECON EFFECTIVENESS - WEAPONS - COLD WEATHER
A1.49
_________________________________________________________________________
Method Rate DF
(100 ft2/h)
_________________________________________________________________________
1. Bared sloped asphalt shingles
fireshosing (lobbing)
25 deg.F 8 3
0 deg.F 8 2
2. Undisturbed snow
a. Snow plough (blade) 330 10 - 35
b. Grading 125 2 - 20
c. Scraping 72 5 - 7
d. Snow plough (rotary) 53 7 - 50
3. Packed snow
a. Grading (0 - 30 deg.F) 70 5 - 6
b. Mechanical sweeping 60 15
(below 20 deg.F)
c. Vacuum sweeping 30 6
(10 - 30 deg.F)
d. Firehosing 30 deg.F 13 10
15 deg.F 13 5
0 deg.F 13 4
4. Paved areas
a. Mechanical sweeping 65 15
b. Firehosing (0 deg.F) 20 10 - 15
5. Bare frozen ground
a. Mechanical sweeping 70 10 - 35
b. Vacuum sweeping 70 8
c. Firehosing 20 2
_________________________________________________________________________
Source: IAEA74
24. 0.5 POWERS
_____________________________________________________________
0.5**M.N
-------------------------------------------------------------
M.Nes M.0 M.2 M.4 M.6 M.8
_____________________________________________________________
0.N 1.000 0.871 0.758 0.660 0.574
1.N 0.500 0.435 0.379 0.330 0.287
2.N 0.250 >>> 0.218 0.189 0.165 0.144
3.N 0.125 0.109 0.095 0.082 0.072
4.N 0.063 0.054 0.047 0.041 0.036
5.N 0.031 0.027 0.024 0.021 0.018
6.N 0.016 0.014 0.012 0.010 0.009
A1.50
7.N 0.008 0.007 0.006 0.005 0.004
8.N 0.004 0.003 0.003 0.003 0.002
9.N 0.002 0.002 0.001 0.001 0.001
_____________________________________________________________
As an example:
0.5**2.2 = 0.218
25. ISOTOPIC RATIOS FOR PU ACCIDENTS
_________________________________________________________________________
Weapons Grade Plutonium
15 yr
Plutonium
------------------------------------------------------------------------
Isotope Initial Fraction Ci/g of Pu Fraction of
by Weight Total Activity
_________________________________________________________________________
Pu-238 4.0E-04 6.09E-03 1.61E-02
Pu-239 9.3E-01 5.80E-02 1.53E-01
Pu-240 6.0E-02 1.37E-02 3.61E-02
Pu-241 5.8E-03 2.91E-01 7.68E-01
Pu-242 4.0E-04 1.57E-06 4.15E-06
_________________________________________________________________________
Americium
------------------------------------------------------------------------
Isotope Initial Fraction Ci/g of Pu Fraction of
by Weight Total Activity
_________________________________________________________________________
Am-241 0.0 1.01E-02 2.67E-02
_________________________________________________________________________
TOTAL 1.0 3.79E-01
Total alpha activity in one gram of Pu = 0.088
Pu/Am ratio = 7.686
Total alpha activity/Am ratio = 8.686
26. INGESTION ASSESSMENT PRIORITIZED TASKS I
_________________________________________________________________________
CRUCIAL TASKS NECESSARY INFORMATION METHOD
_________________________________________________________________________
For a LWR accident, Exposure Rates (mR/h) M.5.1 Evaluate expo-
evaluate exposure @ 1m AGL sure rates for LWR
rate to determine accidents.
where the Ingestion
PAGs may be exceeded.
For accidents with Isotopic mix (relative M.5.2 Evaluate depo-
A1.51
gamma emitters, abundance) based on in- sition marker isotope
develop DRLs for situ measurements, refe- concentration.
a deposition marker rences or information
isotope concentration provided by operator
to determine where AND
the Ingestion PAGs Deposition of marker
may be exceeded. isotope.
For accidents with no Isotopic concentration M.5.3 Evaluate depo-
gamma emitters, eva- (relative abundance) based sition comprehensive
luate entire isotopic on in-situ measurements, isotopic concentration
mix of the deposition references or information
to determine where provided by operator
the Ingestion PAGs AND
may be exceeded. Comprehensive isotopic
analysis of deposition
Assess food concen- Isotopic analysis of meat, M.5.4 Evaluate Food
trations to confirm eggs, fish, and fresh and drinking water
where the PAGs are produce. samples.
exceeded.
Assess milk concen- Isotopic analysis of milk. M.5.5 Evaluate Milk
trations to confirm samples.
where the PAGs are
exceeded.
Estimate the dose Isotopic concentration M.5.13 Calculate
from ingestion of of deposition. Ingestion dose from
surface contamina- dirt (surface conta-
tion (dirt). mination).
Assess forage & water Isotopic analysis of M.5.6 Evaluate Cow &
being feed to milk- cow forage and drinking Goat Forage or Water
producing animals to water. for Milk Pathway.
determine if milk may
exceed the PAGs.
_________________________________________________________________________
27. INGESTION ASSESSMENT PRIORITIZED TASKS II (CONTINUED)
_________________________________________________________________________
CRUCIAL TASKS NECESSARY INFORMATION METHOD
_________________________________________________________________________
Assess milk of ani- Isotopic analysis of M.5.7 Evaluate Milk
mals on stored feed milk samples. contamination for cows
in areas where other or goats on stored
pathways may result feed.
in milk contamination.
Develop food, water M.5.8 Calculate food
and milk concentra- concentration DRLs for
tion DRLs for iso- unlisted isotopes or
topes not listed in different assumptions.
A1.52
Table 5.4 or to use
different assump-
tions (e.g. consider
processes to reduce
contamination or dif-
ferent PAG levels.
Develop DRLs for cow M.5.9 Calculate Cow &
forage and water for Goat Forage & Water
isotopes not listed concentration DRLs for
in Table 5.9 or to unlisted isotopes or
use different assump- different assumptions.
tions.
Develop DRL for depo- M.5.10 Calculate depo-
sitions that may be sition DRLs for unlis-
an ingestion concern ted isotopes or dif-
for isotopes not lis- ferent assumptions.
ted in Table 5.3 or
to use different
assumptions.
Estimate potential Isotopic analysis of M.5.11 Estimate the
peak concentration cow's milk samples. concentration in cow's
in milk. milk after cow's in-
take.
Calculate the dose Isotopic analysis of food, M.5.12 Calculate in-
from ingestion of milk and water samples. gestion dose for food,
contaminated food. milk or water concen-
exceeded. trations.
Develop DCFs for M.5.14 Calculate
isotopes not lis- Ingestion DCF for iso-
ted in Table 5.7 or topes not listed or
to use different to use different
assumptions. assumptions.
_________________________________________________________________________
28. INGESTION PHASE PAGs
_________________________________________________________________________
PAG Organ of interest Projected dose commitment
(mrem)
_________________________________________________________________________
Preventive (a) Whole Body, Bone Marrow, 500
(Lower impact) or any other organ
Thyroid 1,500
Emergency (b) Whole Body, Bone Marrow, 5,000
or any other organ
Thyroid 15,000
A1.53
_________________________________________________________________________
Source: EPA92
a) Preventive PAGs are applicable to situations where protective actions
causing minimal impact on the food supply are appropriate. A preven-
tive PAG establishes a level at which responsible officials should
take protective actions having minimal impact to prevent or reduce
the radioactive contamination of food or animal feed.
b) Emergency PAGs are applicable to incidents where protective actions of
greater impact on the food supply are justified because of the projec-
ted health hazards. An Emergency PAG establishes a level at which res-
ponsible officials should isolate food containing radioactivity to
prevent its introduction into commerce, and at which responsible offi-
cials must determine whether condemnation or other disposition
is appropriate.
29. INGESTION PROTECTIVE ACTIONS
HHS has published guidance (EPA92) on the protective actions that should
be considered if the ingestion of contaminated food may exceed the PAGs.
This guidance is summarized below.
PREVENTIVE PAG
Pasture:
- Removal of lactating (milk-producing) dairy animals from pasture and
substitution of uncontaminated feed.
- Substitute uncontaminated water.
Milk:
- Withhold contaminated milk from market to allow decay.
- Diversion of fluid milk for production of dry whole milk, non-fat dry
milk, butter, cheese or evaporated milk.
Fruits and vegetables:
- Wash, brush, scrub or peal to remove surface contamination.
- Preserve by canning, freezing, dehydration or storage to permit decay.
Grains:
- Milling
- Polishing
Other foods:
- Processing to remove surface contamination.
EMERGENCY PAG
All food:
Isolate food to prevent introduction into commerce and determine whether
condemnation or other disposition is appropriate.
Before taking action consider the following factors:
- Availability of other protective actions.
A1.54
- Relative proportion of contaminated food in total diet.
- Importance of the food and availability of uncontaminated substitutes.
- Contribution of radioisotopes in other foods to total dose.
- Time and effect required to implement corrective action.
- Exposure likely to be received by food processing workers.
_______________________
Source: EPA92
30. HUMAN CONSUMPTION - UF
_________________________________________________________________________
Average consumption Other
Food General population consumption
(kg/day) (a) rates used
_________________________________________________________________________
Milk, cream, cheese, ice cream ----------- .570
Milk - Infant (< 1 yr old) ------------------------------- 0.7 L/d (a,e)
Water - Adult and Child ---------------------------------- 1.4 L/d (d,e)
Fats, oils ------------------------------- .055
Flour, cereal ---------------------------- .091
Bakery products -------------------------- .150
Meat ------------------------------------- .220 (e)
Poultry ---------------------------------- .055
Fish and shellfish ----------------------- .023 (e)
Eggs ------------------------------------- .055 (e)
Sugar, syrup, honey, molasses ------------ .073
Potatoes, sweet potatoes ----------------- .105
Fresh produce (not potatoes) (b) --------- .310 (e)
Fresh vegetables (0.145) +
Fresh Fruit (0.165)
Canned vegetables ------------------------ .077
Vegetable juice (single strength) -------- .009
Canned,frozen fruit ---------------------- .036
Fruit juice ------------------------------ .045
Other beverages (coffee etc.) ------------ .180
Soup and gravies ------------------------- .036
Nuts and peanut butter ------------------- .009
_________________________________________________________________________
TOTAL ----------------------------------- 2.099
a) Source: EPA92, Section 6, p.15.
b) Fresh produce (used in calculations) = Fresh fruit + Fresh vegetables
c) Milk category is expressed as calcium equivalent, i.e. the quantity of
whole fluid milk to which dairy products are equal to calcium content.
d) Source: NRC77
e) Used in Manual
31. RETENTION -- PRODUCTIVITY -- COW CONSUMPTION
_________________________________________________________________________
Parameter Description Value
_________________________________________________________________________
A1.55
Ucow Cow fresh forage consumption 56 kg/d (a,f)
(Lower impact) Cow water consumption 60 L/d (b,f)
r (e) Produce retention factor .05 (c)
Pasture retention factor .50 (a,f)
Leafy vegetable retention factor .20 (d,f)
Y Growth productivity 2.0 kg/m2 (d,f)
_________________________________________________________________________
a) EPA92
b) NCRP84.
c) ORNL-5786 p-76
d) NRC77
e) Used a single retention factor, r, for all non-noble gases (Iodine and
other particulate) because the current understanding is that the vast
majority of the Iodine released during a severe reactor accident will
be part of a particle.
32. REFERENCES
REFERENCE Title
_________________________________________________________________________
10CFR20 US Code of Federal Regulation. Part 20. January 1, 1994
An75 Anspaugh, L.R., et al. 'Resuspension and Redistribution of
Plutonium on Soils'. Health Phys. 29, pp 571-582, 1975.
Be91 Beres, D.A. and Hull, A.P. 'DEPDOSE: An Interactive Micro-
Computer Based Program to Calculate Doses from Exposure to
Radionuclides Deposited on the Ground'. Nol 1. Users Manual.
Brookhaven National Laboratory Report. BNL-47069, December
1991.
DOE84 US Department of Energy - Atmospheric Science and Power
Production, DOE. DOE/TIC-27601, 1984.
EGG75 Structures Shielding from Cloud and Fallout Gamma-Ray
Sources for Assessing the Consequence of Reactor Accidents.
E.G., EGG-1183-1670, December 1975.
EPA70 Turner. Workbook of Atmospheric Dispersion Estimates. EPA,
January 1970.
EPA88 Limiting Values of Radionuclide Intake and Air Concentration
and Dose Converion Factors for Inhalation. Submersion and
Ingestion. Federal Guidance Report No.11. US EPA, EPA 520/1-
88-020, September 1988.
EPA89 Evaluation of skin and Ingestion Exposure Pathways. US EPA.
EPA 520/1-89-016. June 1989.
EPA92 Manual of Protective Action Guides and Protective Actions for
A1.56
Nuclear Incidents. US EPA. EPA 400-R-92-001. May 1992.
EPA93 External Exposure to Radionuclides in Air, Water and Soil.
Federal Guidance Report No.12. US EPA. EPA-402-R-93-081.
September 1993.
EPA94 US EPA, PAG Subcommittee Report on Implementation of EPA's
Dose Limits for Emergency Workers. July 12, 1994.
FEMA87 Guidance on Offsite Emergency Radiation Measurement Systems
Phase 2 - The Milk Pathway. FEMA, FEMA Rep-12. September 1987.
Ho94 Homann, S.G. 'HOTSPOT Health Physics Codes for the PC'.
Lawrence Livermore National Laboratory Report. UCRL-MA-106315.
Available from NTIS. Version 6.5. March 1994.
IAEA74 Evaluation of Radiation Emergency and Accidents. Selected
Criteria and Data. Technical Reports Series No.152. IAEA
Vienna, 1974.
IAEA86 Derived Intervention Levels for Application in Controlling
Radiation Doses to the Public in the Event of a Nuclear
Accident or Radiological Emergency. IAEA Safety Series No.81,
1986.
IAEA93 Modeling of Weathering, Decontamination and Activity Movement
in Sewage System. Working Draft. IAEA 1993.
ICRP74 Report of the Task Group on Reference Man. ICRP-23. Inter-
national Commission on Radiological Protection. October 1974.
ICRP89 Age Dependent Dose to Members of the Public from Intake of
Radionuclides: Part 1. ICRP-56, The International Commission
on Radiological Protection. April 1989.
NCRP84 National Council on Radiation Protection and Measurements.
'Radiological Assessment: Predicting the Transport, Bio-
accumulation and Uptake of Radionuclides Released to the
Environment'. NCRP Report No.76, 1984.
NRC77 US NRC Regulatory Guide 1.109. Calculation of Annual Doses
to Man from Routine Releases of Reactor Effluent for the
Purpose of Evaluating Compliance with 10CFR Part 50,
Appendix I, October 1977.
NRC82 McGuire, A.S. Working Safely in Gamma Radiography, A Training
Manual for Industrial Radiographer. US NRC NUREG/BR-0024,
September 1982.
NRC83 Till, J.E. and Meyer, R.H. Radiological Assessment: A Textbook
on Environmental Dose Analysis. NRC NUREG/CR-3332,
September 1983.
NRC88 Ramsdell, J.V. Atmospheric Diffusion for Control Room
Habiltability Assessments. US NRC NUREG/CR-5005, May 1988.
A1.57
NRC88a McGuire, A.S. A Regulatory Analysis on Emergency Preparedness
for Fuel Cycle and other Radiological Materials Licencees.
US NRC NUREG-1140, January 1988.
NRC89 Health Effects Models for Nuclear Power Plants Accident
Consequence Analysis. US NRC NUREG/CR-4214 Rev.1, May 1989.
NRC92 Soffer, L. Accident Source Terms for Light Water Nuclear Power
Plants. US NRC NUREG-1465, June 1992, Draft for Comments.
NRC93 Response Technical Manual, RTM-93. US NRC NUREG/BR-0150,
Volume 1, November 1993.
NRC94 RASCAL 2.1. Users Manual. US NRC NUREG/CR-5257, Rev.2, 1994.
NRPB85 Doses from Intakes of Radionuclides by Adult and Young People.
National Radiological Protection Board. NRPB-R162, April 1985.
NRPB87 Committed Dose to Selected Organs and Committed Effective
Dose for Intake of Radionuclides. National Radiological
Protection Board. NRPB-GS7. August 1987.
PHS70 Radiological Health Handbook. US Public Health Service,
January 1970. PB-230 846.
SU93 Sullivan, T.S., Ellis, J.S. et al. Atmospheric Release
Advisory Capability: Real-Time Modeling of Airborne Hazardous
Materials. Bull.Amer.Meteor.Soc. 74:2343-2361, December 1993.
WASH-1400 Reactor Safety Study. US NRC, October 1975.
REQUIRED REFERENCES AND CODES
Be91(Code) Beres, D.A., and Hull, A.P. 'DEPOSE: An Intercative Micro-
computer Based Program to Calculate Doses from Exposure to
Radionuclides Deposited on the Ground'. Nol.1. Users Manual.
Brookhave National Laboratory Report. BNL-47069. December 1991.
EPA88 Limiting Values of Radionuclide Intake and Air Concentration
and Dose Conversion Factors for Inhalation. Submersion and
Ingestion. Federal Guidance Report No.11. US EPA. EPA 520/1-
88-020, September 1988.
EPA92 Manual of Protective Action Guides and Protective Actions for
Nuclear Incidents. US EPA. EPA 400-R-92-001. May 1992.
EPA93 External Exposure to Radionuclides in Air, Water and Soil.
Federal Guidance Report No.12. US EPA. EPA-402-R-93-081.
September 1993.
Ho94(Code) Homann, S.G. 'HOTSPOT Health Physics Codes for the PC'.
Lawrence Livermore National Laboratory Report. UCRL-MA-106315.
Available from NTIS. Version 6.5. March 1994.
A1.58
IAEA74 Evaluation of Radiation Emergency and Accidents. Selected
Criteria and Data. Technical Reports Series No.152. IAEA
Vienna, 1974.
ICRP89 Age Dependent Dose to Members of the Public from Intake of
Radionuclides: Part 1. ICRP-56, The International Commission
on Radiological Protection. April 1989.
NCRP84 National Council on Radiation Protection and Measurements.
'Radiological Assessment: Predicting the Transport, Bio-
accumulation and Uptake of Radionuclides Released to the
Environment'. NCRP Report No.76, 1984.
NRC77 US NRC Regulatory Guide 1.109. Calculation of Annual Doses
to Man from Routine Releases of Reactor Effluent for the
Purpose of Evaluating Compliance with 10CFR Part 50,
Appendix I, October 1977.
NRC83 Till, J.E. and Meyer, R.H. Radiological Assessment: A Textbook
on Environmental Dose Analysis. NRC NUREG/CR-3332,
September 1983.
NRC93 Response Technical Manual, RTM-93. US NRC NUREG/BR-0150,
Volume 1, November 1993.
NRC94 RASCAL 2.1. Users Manual. US NRC NUREG/CR-5257,
(Code) Rev.2, 1994.
NRPB85 Doses from Intakes of Radionuclides by Adult and Young People.
National Radiological Protection Board. NRPB-R162, April 1985.
NRPB87 Committed Dose to Selected Organs and Committed Effective
Dose for Intake of Radionuclides. National Radiological
Protection Board. NRPB-GS7. August 1987.
PHS70 Radiological Health Handbook. US Public Health Service,
January 1970. PB-230 846.
36. TERMS AND ABBREVIATIONS I
GLOSSARY: TERMS AND ABBREVIATIONS
_________________________________________________________________________
ACUTE HEALTH EFFECTS
See EARLY HEALTH EFFECTS.
AGL
Above ground level.
ARAC
Atmospheric Release Advisory Capability.
CHILD
A 10 years old.
A1.59
COMMITTED DOSE EQUIVALENT (CDE)
The dose equivalent to a specific organ for 50 years following intake.
COMMITTED EFFECTIVE DOSE EQUIVALENT (CEDE)
The sum of the dose equivalent for 50 years following intake (inhalation
or ingestion) of radionuclide to each organ multiplied by a weighing
factor. Used to estimate the risk of delayed health effects.
CONCENTRATION
The total activity of each radioisotope in a sample or surface area.
CRITICAL
Most important source of dose, the most organ, or the most important
group of (potentially) exposed population. That is, effects will be
dominated by this source of dose, or effects (e.g. deaths) will occur
first as a result of exposure to this organ or population (e.g. infants)
when exposed to radiation via a certain pathway.
DELAYED HEALTH EFFECTS
A wide range of cancers and hereditary effects which usually occur many
years after exposure. In contrast to early health effects, it is assumed
there are no dose thresholds below which these effects do not occur.
DEPOSITION
The contamination found on or within a few cm of the surface of the
ground.
DERIVED RESPONSE LEVEL (DRL)
A calculated value (e.g. exposure rate or radionuclide concentration)
that corresponds to an early health effect threshold or PAG. DRLs can be
used to relate environmental measurements or laboratory analysis to the
potential for early health effects or need for protective actions. Used
to allow prompt assessments.
DOE
US Department of Energy
DOSE CONVERSION FACTOR (DCF)
The dose equivalent per unit intake of a radionuclide (mrem/uCi).
EARLY HEALTH EFFECTS
Health effects that will be seen shortly after exposure (hours, weeks)
resulting from high doses over a short period (acute doses) to specific
organs and involving thresholds below which these health effects are not
expected.
EARLY PHASE
Extends from the time the threat of a major release is identified (before
the release) until the release or the threat of a major release has ended
and areas of major contamination have been identified.
EFFECTIVE DOSE EQUIVALENT (EDE)
The sum of the dose equivalent from external exposure to each organ
multiplied by a weighing factor. Used to estimate the risk from delayed
health effects. EDE from air submersion and ground shine is assumed to
A1.60
(numerically) equal 0.7 times the exposure rate.
EMERGENCY WORKER LIMIT
Guidance on limits of the external and CEDE dose incurred to non-pregnant
adult while performing emergency services.
EPA
US Environmental Protection Agency.
EXTERNAL EXPOSURE
The dose of radiation received by an individual from a source of ionizing
radiation outside the body.
FACILITY OPERATOR
The organization that operates the facilty.
FDA
US Food and Drug Administration.
FRMAC
US Federal Radiological Monitoring and Assessment Center.
GROUNDSHINE
Gamma radiation from radioactive materials deposited on the ground.
HHS
US Department of Health and Human Services.
IMMERSION
To be surrounded or engulfed by the radioactive cloud.
INFANT
A child one year of age.
INTERMEDIATE PHASE
The period beginning after the release and potential for further major
release is over and reliable environmental data is available for use as
a basis for relocation and ingestion protective actions.
LFA
Lead Federal Agency (US).
LIGHT WATER REACTOR (LWR)
A nuclear reactor that uses natural water as a coolant and moderator.
All US commercial power reactors are LWRs as are the VVERs.
MARKER ISOTOPE
An isotope contained in deposition or samples that is easily identified
in the field or laboratory. It is used to determine areas of concern
before performing a comprehensive isotopic analysis.
MIX
The isotopic ratio of the radionuclides in a sample or surface deposition.
NRC
A1.61
US Nuclear Regulatory Commission.
PATHWAYS
The path radionuclides follow from the source though the environment
including vegetation and animals to reach an individual or a population.
PROTECTIVE ACTION GUIDE (PAG)
The projected dose, from an accidental release of radioactive material,
at which specific actions to reduce or avoid dose are warranted.
QUALITY FACTOR (QF)
The principal modifying factor employed in deriving dose equivalent (H)
from absorbed dose, chosen to account for the relative biological
effectiveness (RBE) of the radiation in question, but to be independent
of the tissue or organ under consideration and of the biological endpoint.
For radiation protection purposes, the Quality Factor is determined by
the linear energy transfer (LET) of the radiation.
RESUSPENSION
Reintroduction to the atmosphere of material originally deposited onto
surfaces.
RTM
Response Technical Manual.
STABILITY CLASS
A class which describes an atmospheric turbulence condition. Generally
there are six classes ranging from Class A - very unstable, through
Class F - very stable.
TOTAL ACUTE BONE (MARROW) DOSE (TABD)
Dose estimates used to determine if Early Health Effects are possible
from exposure of the bone marrow. Bone marrow is a critical organ when
considering deaths from LWR accidents. TABD projections in the Manual
include: (1) EDE from air submersion; (2) 4-days of EDE from ground
deposition; (3) acute inhalation dose from the plume (dose to the organ
for 30 days after inhalation of radioactive material); and (4) acute
inhalation from 4-days of resuspension.
TOTAL ACUTE LUNG DOSE (TALD)
Dose estimates used to determine if Early Health Effects are possible
from exposure of the lung. Lung is a critical organ when considering
deaths from accidents involving transuranics. TALD projections in the
Manual include: (1) EDE from air submersion; (2) 4-days of EDE from
ground deposition; (3) acute inhalation dose from the plume (dose to the
organ for 30 days after inhalation of radioactive material); and (4)
acute inhalation from 4-days of resuspension.
TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE)
Dose estimates used for comparison with EPA Early Phase PAG (EPA92).
TEDE projections include: (1) the EDE from air submersion; (2) 4-days of
EDE from ground deposition; (3) the inhalation CEDE from the plume; and
(4) CEDE from inhalation of 4-days of resuspension.
TOTAL EFFECTIVE EXPOSURE PERIOD
A1.62
The time span, considering decay, that will approximate the integrated
dose over a period of time when multiplied by the dose rate at the
beginning.
TURN BACK LIMIT
An integrated dose reading on a self-reading dosimeter indicating that an
emergency worker limit has been exceeded and that the emergency worker
should leave the area where further exposure is possible.
WEATHERING
Reduction of dose from deposited material on the ground, over time, due
to rain etc.
WEIGHTING FACTORS
Used in the calculation of CEDE and EDE. They are an estimate of the
mortality risk from delayed health effects arising from irradiation of
a particular organ. Weighting factors (EPA88) are: gonads - 0.25;
breasts - 0.15; red bone marrow - 0.12; lungs - 0.12; thyroid - 0.03;
bone surface - 0.03; remainder - 0.30.
ABOUT THE FRMAC MANUAL
______________________
The present code package (ROBOT – Rule-Oriented Basic Operational Tools)
is an application of the
FRMAC ASSESSMENT MANUAL
THE FEDERAL MANUAL FOR ASSESSING ENVIRONMETAL DATA
DURING A RADIOLOGICAL EMERGENCY
Version July 1995
Manual's version as indicated is the first printing of the document for
wide distribution and use. It is labeled 'FOR INTERIM USE AND COMMENT'
with the understanding that it has undergone limited review, while the
reviewing process continues in view of fully qualifying the Manual for
use in a radiological emergency. Manual's Preface encourages readers
to provide comments and suggestions for improvement.
To assure consistency, completeness and the highest quality of assessed
data produced by the FRMAC, an attempt was made to compile into the
Manual the most appropriate assessment methods and values available.
The criteria were for these to be (1) scientifically defensible;
(2) simple; (3) applicable to a FRMAC deployment; and (4) most likely to
be adopted by others.
The primary purpose of the Manual is to provide the users a sound
scientific basis in technical, transfer and conversion values and
assessment processes, agreed upon ahead of time, in view of assuring the
users that the correct values are being used and that results will be
consistent among users from shift to shift.
DOE/NV has responsibility for maintaining the master Manual, from which
control copies can be obtained. Readers and users are kindly requested to
direct comments on the Manual to: FRMAC Program Manager, Emergency
Management and Nonproliferation Division, US Department of Energy,
A1.63
Nevada Operations Office, P.O.Box 98518, Las Vegas, NV 89193-8518.
LIST OF PREPARERS
-----------------
R.L.Blanchard, S.Cohen & Associates, Inc., Montgomery, AL.
T.E.Buhl, Los Alamos National Laboratory, University of California,
Los Alamos, NM.
A.P.Hull, Brookhaven National Laboratory, Upton, NY.
T.J.McKenna, U.S. Nuclear Rgulatory Commission (HQ), Washington, D.C.
J.M.Smith, National Air and Radiation Environmental Laboratory,
US Environmental Protection Agency, Montgomery, AL.
J.A.Trefethen, U.S. Nuclear Regulatory Commission (HQ), Washington, D.C.
R.Bores, Region 1, U.S. Nuclear Regulatory Commission, King of Prussia,PA
Tom McKenna and Jean Trefethen are acknowledged as being the primary
author and technical editors of the FRMAC Manual. They were assisted by
Dan Vamanu (IAEA Fellow), and Zhiguang Li (IAEA Fellow). The FRMAC
Assessment Working Group Members, chaired by Zolin G. Burson, EG&G/EM are
acknowledged as additional contributors. They also have reviewed in
detail all aspects of the Manual.
ROBOT concept and application were developed by Dan Vamanu.
A2.1
ANEXA 2
Datele Meteorologice Cuprins
A.2.1. Sistemele de dispersie în N-WATCHDOG ...................................................... A2.2 A.2.1.1. Descriere .................................................................................................. A2.2 A.2.1.2. Parametrii ................................................................................................. A2.4 A.2.1.3. Soluţia de implemetare ............................................................................. A2.8
A.2.2. Maşina de achiziţie şi prelucrare a datelor .................................................... A2.11
A2.2
A.2.1. Sistemele de dispersie în N-WATCHDOG In context, un sistem de dispersie este o clasa de referinta acreditata in literatura continand specificatii pentru:
Legea de variatie a abaterilor standard, numite ‘coeficienti de dispersie’ si notate, de
obicei cu simbolul sigma, ale concentratiei de marime dispersata cu (a) distanta punctului de observatie fata de sursa (modelul Puff Trails), sau distantele pe axa vantului mediu si transversal pe aceasta (modelul Plumes); sau (b) timpul scurs de la emisie pana la momentul observatiei, pentru fiecare puff in cazul Puff Trails, sau in mod absolut in cazul Plumes.
Legea de variatie a vitezei vantului cu inaltimea pufului, sau a axei penei de efluent (wind shear law); si
Dependenta postulata a nivelelor de inversie, fata de clasa de stabilitate atmosferica.
Alegerea sistemului de dispersie depinde de judecata experta (expert judgement) a utilizatorului. Practic, clientii versiunii finale a N-WATCHDOG (Modelul experimental, 2016) vor negocia cu furnizorul de coduri sau de servicii acest aspect, impreuna cu altele aflate in aceeasi situatie – mentionate in sesiunile anterioare (particularitati ale termenului sursa considerat reprezentativ, caracterizarea rugozitatii terenului din zona de influenta a obiectivului nuclear, preferinta pentru raza de evaluare – in zona apropiata sau la mare distanta de sursa, tipul de model etc.), convenind protocoale de pre-setare a codurilor. Abordarea aspectelor definitorii mentionate, ale unui sistem de dispersie se prezinta in continuare. A.2.1.1. Descriere
DISPERSION SYSTEMS
__________________
This facility offers a way to update sets of referenced diffusion
parameters of use with atmospheric dispersion models, or to create
custom sets of such parameters.
The following chief sources were compiled:
[1] U.S. Nuclear Regulatory Commission (1983). Radiological Assessment -
A Textbook on Environmental Dose Analysis. Till J.E. and Meyer H.R.,
Editors, Washington, D.C., U.S.A.
[2] Doury A.(1976). Une methode de calcul pratique et generale
pour la prevision numerique des pollutions vehiculee par
l'atmosphere. CEA, Saclay, Rapport CEA-R-4280 (Rev.1),
as quoted in:
IAEA (1986). Atmospheric Dispersion Models for Application
in Relation to Radionuclide Releases. IAEA-TECDOC-379.
Two categories of parameters are reviewed, namely
(i) distance-dependent, and (ii) time-dependent, parameters.
I. DISTANCE-DEPENDENT DIFFUSION PARAMETERS
_______________________________________
To give the subject a uniform treatment, the following assumptions
were made:
> Distance-dependent diffusion parameters are power functions of the
distance X (m) travelled from the source, by the release:
SIGMAx = e x (X^f)
SIGMAy = a x (X^b)
SIGMAz = c x (X^d) x R
A2.3
with R as a ground roughness correction factor.
> Diffusion parameters vary with plume centerline height above ground.
Their coefficients and exponents are given for three reference
levels: 0, 100, and 180m. Since, however, for some of the sets no
such distinction was operated by the proponents, the sets will
appear identical at all heights.
> All sets are assumed to vary over six atmospheric stability
classes: A, B, C, D, E, F. When a certain set would not
originally cover all classes, missing classes will be assigned
the values of the previous/next neighbour-class in the A-F series.
Enlisted with this code are the following distance-dependent
Dispersion Systems:
1. KARLSRUHE-JULICH
Applicable to sites with medium to higher surface roughness,
which is due to settlements, vegetation, and other ground
obstacles (cf.[2]). Assumed: equal downwind and crosswind
diffusion. No roughness correction (R = 1).
2. KLUG
Suited for application to short-term ground level releases over
terrains with a low surface roughness (cf.[2]). No roughness
correction (R = 1).
3. BROOKHAVEN
Applicable under conditions typical for the release of pollutants
from industrial plants (cf.[2]). No roughness correction (R = 1).
4. St.LOUIS
Applicable to releases in metropolitan areas and, possibly,
other sites of extreme surface roughness (cf.[1]). No roughness
correction (R = 1).
5. BRIGGS CNCAN
6. BRIGGS Lawrence Livermore (HotSpot)
>> Use main menu's 'Open a Distance-Dependent Dispersion System File'
to access the data pertaining to the varieties 1 through 5.
II. TIME-DEPENDENT DIFFUSION PARAMETERS
___________________________________
> Time-dependent diffusion parameters are power functions of the time
spent by the release to travel out from the source. The formulation
given by Doury [3] is:
SIGMAx = (Ah x t)^Kh
SIGMAy = (Ah x t)^Kh
SIGMAz = (Av x t)^Kv
assuming equal downwind and crosswind diffusion.
> Diffusion parameters are given for two atmospheric stability
categories: strong diffusion, and weak diffusion. Roughly, the
strong diffusion category may be assimilated with standard classes
A, B, and C, while the weak diffusion may be associated with
classes D, E, and F.
> The coefficients and exponents involved are given, in a stepwise
manner, for six time intervals.
Enlisted with this code is the following time-dependent
Dispersion System:
6. DOURY
Compiled from a variety of field measurement data to suit a generic
situation in accidental releases.
>> Use main menu's 'Open a Time-Dependent Dispersion System File'
A2.4
to access the data pertaining to the variety 6.
SHARED FEATURES
_______________
> Distance-dependent diffusion parameters may be treated as time-
dependent, to the extent that the law of motion of the release
(e.g. of puff centers in puff models) is known.
> A vertical wind shear power law operates:
W(z) = W10 x ((z/10)^pw)
with exponent pw depending on atmospheric category.
> The vertical temperature gradient dT/dz (K/m) affecting plume rise
is also atmospheric category-dependent.
> To maximize code flexibility, all data on Dispersion Systems may be
user-edited (updated etc.) directly in the displaying windows.
Once edited, data sets may be saved under alternative file-names,
for further use. An indefinite variety of dispersion systems matching
different field situations, field data bases, or user beliefs, may
thus be provided.
A.2.1.2. Parametrii In descrierea din sectiunea precedenta se folosesc urmatorii parametri
DISPERSION SYSTEM: KARLSRUHE-JULICH (COSYMA, U.S.NRC)
___________________________________________________
Level(mAG): 50 @1
_______________
. Py Qy Pz Qz hInv pH
__________________________________________________
Stability-A: 1.503 0.833 0.151 1.219 1600 0.07 [C11]
Stability-B: 0.876 0.823 0.127 1.108 1200 0.13 [C12]
Stability-C: 0.659 0.807 0.165 0.996 800 0.21 [C13]
Stability-D: 0.64 0.784 0.215 0.885 560 0.34 [C14]
Stability-E: 0.801 0.754 0.264 0.774 320 0.44 [C15]
Stability-F: 1.294 0.718 0.241 0.662 200 0.44 [C16]
__________________________________________________
Level(mAG): 100 @2
_______________
. Py Qy Pz Qz hInv pH
____________________________________________________
Stability-A: 0.17 1.296 0.051 1.317 1600 0.07 [C21]
Stability-B: 0.324 1.025 0.070 1.151 1200 0.13 [C22]
Stability-C: 0.466 0.866 0.137 0.985 800 0.21 [C23]
Stability-D: 0.504 0.818 0.265 0.818 560 0.34 [C24]
Stability-E: 0.411 0.882 0.487 0.652 320 0.44 [C25]
Stability-F: 0.253 1.057 0.717 0.486 200 0.44 [C26]
____________________________________________________
Level(mAG): 180 @3
_______________
. Py Qy Pz Qz hInv pH
____________________________________________________
Stability-A: 0.671 0.903 0.025 1.500 1600 0.07 [C31]
Stability-B: 0.415 0.903 0.033 1.320 1200 0.13 [C32]
Stability-C: 0.232 0.903 0.104 0.997 800 0.21 [C33]
Stability-D: 0.208 0.903 0.307 0.734 560 0.34 [C34]
Stability-E: 0.345 0.903 0.546 0.557 320 0.44 [C35]
A2.5
Stability-F: 0.671 0.903 0.485 0.500 200 0.44 [C36]
____________________________________________________
DISPERSION SYSTEM: BROOKHAVEN (U.S.NRC)
_____________________________
Level(mAG): 50 @1
_______________
. Py Qy Pz Qz hInv pH
____________________________________________________
Stability-A: 0.400 0.910 0.411 0.907 1600 0.07 [B11]
Stability-B: 0.400 0.910 0.411 0.907 1200 0.13 [B12]
Stability-C: 0.360 0.860 0.326 0.859 800 0.21 [B13]
Stability-D: 0.320 0.780 0.223 0.776 560 0.34 [B14]
Stability-E: 0.320 0.780 0.223 0.776 320 0.44 [B15]
Stability-F: 0.310 0.710 0.062 0.709 200 0.44 [B16]
____________________________________________________
Level(mAG): 100 @2
_______________
. Py Qy Pz Qz
____________________________________________________
Stability-A: 0.400 0.910 0.411 0.907 1600 0.07 [B21]
Stability-B: 0.400 0.910 0.411 0.907 1200 0.13 [B22]
Stability-C: 0.360 0.860 0.326 0.859 800 0.21 [B23]
Stability-D: 0.320 0.780 0.223 0.776 560 0.34 [B24]
Stability-E: 0.320 0.780 0.223 0.776 320 0.44 [B25]
Stability-F: 0.310 0.710 0.062 0.709 200 0.44 [B26]
____________________________________________________
Level(mAG): 180 @3
_______________
. Py Qy Pz Qz
___________________________________________________
Stability-A: 0.400 0.910 0.411 0.907 1600 0.07 [B31]
Stability-B: 0.400 0.910 0.411 0.907 1200 0.13 [B32]
Stability-C: 0.360 0.860 0.326 0.859 800 0.21 [B33]
Stability-D: 0.320 0.780 0.223 0.776 560 0.34 [B34]
Stability-E: 0.320 0.780 0.223 0.776 320 0.44 [B35]
Stability-F: 0.310 0.710 0.062 0.709 200 0.44 [B36]
___________________________________________________
DISPERSION SYSTEM: KLUG
_______________________
Level(mAG): 50 @1
_______________
. Py Qy Pz Qz hInv pH
___________________________________________________
Stability-A: 0.469 0.903 0.017 1.380 1600 0.07 [K11]
Stability-B: 0.306 0.885 0.072 1.021 1200 0.13 [K12]
Stability-C: 0.230 0.855 0.076 0.879 800 0.21 [K13]
Stability-D: 0.219 0.764 0.140 0.727 560 0.34 [K14]
Stability-E: 0.237 0.691 0.217 0.610 320 0.44 [K15]
Stability-F: 0.273 0.594 0.262 0.500 200 0.44 [K16]
___________________________________________________
Level(mAG): 100 @2
_______________
. Py Qy Pz Qz hInv pH
___________________________________________________
Stability-A: 0.469 0.903 0.017 1.380 1600 0.07 [K21]
Stability-B: 0.306 0.885 0.072 1.021 1200 0.13 [K22]
A2.6
Stability-C: 0.230 0.855 0.076 0.879 800 0.21 [K23]
Stability-D: 0.219 0.764 0.140 0.727 560 0.34 [K24]
Stability-E: 0.237 0.691 0.217 0.610 320 0.44 [K25]
Stability-F: 0.273 0.594 0.262 0.500 200 0.44 [K26]
___________________________________________________
Level(mAG): 180 @3
_______________
. Py Qy Pz Qz hInv pH
___________________________________________________
Stability-A: 0.469 0.903 0.017 1.380 1600 0.07 [K31]
Stability-B: 0.306 0.885 0.072 1.021 1200 0.13 [K32]
Stability-C: 0.230 0.855 0.076 0.879 800 0.21 [K33]
Stability-D: 0.219 0.764 0.140 0.727 560 0.34 [K34]
Stability-E: 0.237 0.691 0.217 0.610 320 0.44 [K35]
Stability-F: 0.273 0.594 0.262 0.500 200 0.44 [K36]
___________________________________________________
DISPERSION SYSTEM: St-LOUIS
___________________________
Level(mAG): 50 @1
_______________
. Py Qy Pz Qz hInv pH
___________________________________________________
Stability-A: 1.700 0.717 0.079 1.200 1600 0.07 [S11]
Stability-B: 1.700 0.717 0.079 1.200 1200 0.13 [S12]
Stability-C: 1.440 0.710 0.131 1.046 800 0.21 [S13]
Stability-D: 0.910 0.729 0.910 0.702 560 0.34 [S14]
Stability-E: 1.020 0.648 0.930 0.465 320 0.44 [S15]
Stability-F: 1.020 0.648 0.930 0.465 200 0.44 [S16]
___________________________________________________
Level(mAG): 100 @2
_______________
. Py Qy Pz Qz hInv pH
___________________________________________________
Stability-A: 1.700 0.717 0.079 1.200 1600 0.07 [S21]
Stability-B: 1.700 0.717 0.079 1.200 1200 0.13 [S22]
Stability-C: 1.440 0.710 0.131 1.046 800 0.21 [S23]
Stability-D: 0.910 0.729 0.910 0.702 560 0.34 [S24]
Stability-E: 1.020 0.648 0.930 0.465 320 0.44 [S25]
Stability-F: 1.020 0.648 0.930 0.465 200 0.44 [S26]
___________________________________________________
Level(mAG): 180 @3
_______________
. Py Qy Pz Qz hInv pH
___________________________________________________
Stability-A: 1.700 0.717 0.079 1.200 1600 0.07 [S31]
Stability-B: 1.700 0.717 0.079 1.200 1200 0.13 [S32]
Stability-C: 1.440 0.710 0.131 1.046 800 0.21 [S33]
Stability-D: 0.910 0.729 0.910 0.702 560 0.34 [S34]
Stability-E: 1.020 0.648 0.930 0.465 320 0.44 [S35]
Stability-F: 1.020 0.648 0.930 0.465 200 0.44 [S36]
___________________________________________________
DISPERSION SYSTEM: Briggs-Romania
(CNCAN-360-2004)
________________________________________
Meadow, reservoir, Briggs-Romania
_________________________________
Meteorology a1 b1 a2 b2 c3 c1 d1 c2 d2 z0 hInv pH
A2.7
______________________________________________________________________________________________
Stability-A: 0.1120 1.060 0.000538 0.815 0.22 1.58 0.0480 0.000625 0.45 0.01 1600 0.07 [M01]
Stability-B: 0.1300 0.950 0.000652 0.750 0.16 1.58 0.0480 0.000625 0.45 0.01 1200 0.13 [M02]
Stability-C: 0.1120 0.920 0.000905 0.718 0.11 1.58 0.0480 0.000625 0.45 0.01 800 0.21 [M03]
Stability-D: 0.0980 0.889 0.001350 0.688 0.08 1.58 0.0480 0.000625 0.45 0.01 560 0.34 [M04]
Stability-E: 0.0609 0.895 0.001960 0.684 0.06 1.58 0.0480 0.000625 0.45 0.01 320 0.44 [M05]
Stability-F: 0.0638 0.783 0.001360 0.672 0.04 1.58 0.0480 0.000625 0.45 0.01 200 0.44 [M06]
______________________________________________________________________________________________
Farm land, Briggs-Romania
_________________________
Meteorology a1 b1 a2 b2 c3 c1 d1 c2 d2 z0 hInv pH
_____________________________________________________________________________________________
Stability-A: 0.1120 1.060 0.000538 0.815 0.22 2.08 0.0269 0.000776 0.37 0.04 1600 0.07 [F01]
Stability-B: 0.1300 0.950 0.000652 0.750 0.16 2.08 0.0269 0.000776 0.37 0.04 1200 0.13 [F02]
Stability-C: 0.1120 0.920 0.000905 0.718 0.11 2.08 0.0269 0.000776 0.37 0.04 800 0.21 [F03]
Stability-D: 0.0980 0.889 0.001350 0.688 0.08 2.08 0.0269 0.000776 0.37 0.04 560 0.34 [F04]
Stability-E: 0.0609 0.895 0.001960 0.684 0.06 2.08 0.0269 0.000776 0.37 0.04 320 0.44 [F05]
Stability-F: 0.0638 0.783 0.001360 0.672 0.04 2.08 0.0269 0.000776 0.37 0.04 200 0.44 [F06]
_____________________________________________________________________________________________
Grazing field, Briggs-Romania
_____________________________
Meteorology a1 b1 a2 b2 c3 c1 d1 c2 d2 z0 hInv pH
______________________________________________________________________________________________
Stability-A: 0.1120 1.060 0.000538 0.815 0.22 2.72 0.0 0.0 0.0 0.10 1600 0.07 [G01]
Stability-B: 0.1300 0.950 0.000652 0.750 0.22 2.72 0.0 0.0 0.0 0.10 1200 0.13 [G02]
Stability-C: 0.1120 0.920 0.000905 0.718 0.11 2.72 0.0 0.0 0.0 0.10 800 0.21 [G03]
Stability-D: 0.0980 0.889 0.001350 0.688 0.08 2.72 0.0 0.0 0.0 0.10 560 0.34 [G04]
Stability-E: 0.0609 0.895 0.001960 0.684 0.06 2.72 0.0 0.0 0.0 0.10 320 0.44 [G05]
Stability-F: 0.0638 0.783 0.001360 0.672 0.04 2.72 0.0 0.0 0.0 0.10 200 0.44 [G06]
______________________________________________________________________________________________
Rural area, Briggs-Romania
__________________________
Meteorology a1 b1 a2 b2 c3 c1 d1 c2 d2 z0 hInv pH
_____________________________________________________________________________________________
Stability-A: 0.1120 1.060 0.000538 0.815 0.22 5.16 -0.0980 18.6 -0.225 0.40 1600 0.07 [R01]
Stability-B: 0.1300 0.950 0.000652 0.750 0.22 5.16 -0.0980 18.6 -0.225 0.40 1200 0.13 [R02]
Stability-C: 0.1120 0.920 0.000905 0.718 0.11 5.16 -0.0980 18.6 -0.225 0.40 800 0.21 [R03]
Stability-D: 0.0980 0.889 0.001350 0.688 0.08 5.16 -0.0980 18.6 -0.225 0.40 560 0.34 [R04]
Stability-E: 0.0609 0.895 0.001960 0.684 0.06 5.16 -0.0980 18.6 -0.225 0.40 320 0.44 [R05]
Stability-F: 0.0638 0.783 0.001360 0.672 0.04 5.16 -0.0980 18.6 -0.225 0.40 200 0.44 [R06]
_____________________________________________________________________________________________
Woods, town area, Briggs-Romania
________________________________
Meteorology a1 b1 a2 b2 c3 c1 d1 c2 d2 z0 hInv pH
____________________________________________________________________________________________
Stability-A: 0.1120 1.060 0.000538 0.815 0.22 7.37 -0.0957 4290 -0.600 1.00 1600 0.07 [W01]
Stability-B: 0.1300 0.950 0.000652 0.750 0.22 7.37 -0.0957 4290 -0.600 1.00 1200 0.13 [W02]
Stability-C: 0.1120 0.920 0.000905 0.718 0.11 7.37 -0.0957 4290 -0.600 1.00 800 0.21 [W03]
Stability-D: 0.0980 0.889 0.001350 0.688 0.08 7.37 -0.0957 4290 -0.600 1.00 560 0.34 [W04]
Stability-E: 0.0609 0.895 0.001960 0.684 0.06 7.37 -0.0957 4290 -0.600 1.00 320 0.44 [W05]
Stability-F: 0.0638 0.783 0.001360 0.672 0.04 7.37 -0.0957 4290 -0.600 1.00 200 0.44 [W06]
_____________________________________________________________________________________________
Tall buildings area, Briggs-Romania
___________________________________
Meteorology a1 b1 a2 b2 c3 c1 d1 c2 d2 z0 hInv pH
_____________________________________________________________________________________________
Stability-A: 0.1120 1.060 0.000538 0.815 0.22 11.7 -0.1280 45900 -0.780 4.00 1600 0.07 [T01]
Stability-B: 0.1300 0.950 0.000652 0.750 0.22 11.7 -0.1280 45900 -0.780 4.00 1200 0.13 [T02]
Stability-C: 0.1120 0.920 0.000905 0.718 0.11 11.7 -0.1280 45900 -0.780 4.00 800 0.21 [T03]
A2.8
Stability-D: 0.0980 0.889 0.001350 0.688 0.08 11.7 -0.1280 45900 -0.780 4.00 560 0.34 [T04]
Stability-E: 0.0609 0.895 0.001960 0.684 0.06 11.7 -0.1280 45900 -0.780 4.00 320 0.44 [T05]
Stability-F: 0.0638 0.783 0.001360 0.672 0.04 11.7 -0.1280 45900 -0.780 4.00 200 0.44 [T06]
_____________________________________________________________________________________________
DISPERSION SYSTEM: Briggs-HOTSPOT(Lawrence Livermore Labs., U.S.)
(Lawrence Livermore Labs., U.S.)
___________________________________________________
Normal Terrain, HOTSPOT
_______________________
Meteorology ay by az bz cz hInv pH
____________________________________________________________
Stability-A: 0.22 0.0001 0.200 0.0000 0.0 1600 0.07 [N01]
Stability-B: 0.16 0.0001 0.120 0.0000 0.0 1200 0.13 [N02]
Stability-C: 0.11 0.0001 0.080 0.0002 0.0 800 0.21 [N03]
Stability-D: 0.08 0.0001 0.060 0.0015 0.0 560 0.34 [N04]
Stability-E: 0.06 0.0001 0.030 0.0003 0.0 320 0.44 [N05]
Stability-F: 0.04 0.0001 0.016 0.0003 0.0 200 0.44 [N06]
____________________________________________________________
Urban Terrain, HOTSPOT
______________________
Meteorology ay by az bz cz hInv pH
_____________________________________________________________
Stability-A: 0.32 0.0004 0.24 0.0000 0.001 1600 0.07 [U01]
Stability-B: 0.32 0.0004 0.24 0.0000 0.001 1200 0.13 [U02]
Stability-C: 0.22 0.0004 0.20 0.0000 0.000 800 0.21 [U03]
Stability-D: 0.16 0.0004 0.14 0.0003 0.000 560 0.34 [U04]
Stability-E: 0.11 0.0004 0.08 0.0015 0.000 320 0.44 [U05]
Stability-F: 0.11 0.0004 0.08 0.0015 0.000 200 0.44 [U06]
_____________________________________________________________
DISPERSION SYSTEM: DOURY
time-dependent dispersion coefficients
_________________________________________________________
Time-range (s) Ah Kh Av Kv
_________________________________________________
Strongest Diffusion (A-Pasquill)
--------------------------------
0 0.405 0.859 0.420 0.814 s1
240 0.135 1.130 1.000 0.685 s2
3280 0.135 1.130 20.00 0.500 s3
97000 0.463 1.000 20.00 0.500 s4
508000 6.500 0.824 20.00 0.500 s5
1300000 200000 0.500 20.00 0.500 s6
Weakest Diffusion (F-Pasquill)
------------------------------
0 0.405 0.859 0.200 0.500 w1
240 0.135 1.130 0.200 0.500 w2
3280 0.135 1.130 0.200 0.500 w3
97000 0.463 1.000 0.200 0.500 w4
508000 6.500 0.824 0.200 0.500 w5
1300000 200000 0.500 0.200 0.500 w6
A.2.1.3. Soluţia de implemetare Tabelul A2.1 prezinta schita de concept a algoritmului de selectie a sistemelor si de calcul al coeficientilor de dispersie, inclusiv ecuatiile de sistem utilizate.
Tabelul A2.1. Selectia sistemelor, ecuatiile de sistem si calculul coeficientilor de dispersie
A2.9
Dispersion system code: C
Codes: D - Time-dependent Doury
C - COSYMA, Karlsruhe-Hulich - mild-hilly terrain (e.g. Central Europe)
B - BROOKHAVEN - industrial area
K - KLUG - plain field, water mirror
S - StLOUIS - tall building-featuring town area
M - Meadow, reservoir, Briggs-CNCAN, Romania
F - Farm land, Briggs-CNCAN, Romania
G - Grazing field, Briggs-CNCAN, Romania
R - Rural area, Briggs-CNCAN, Romania
W - Woods, town area, Briggs-CNCAN, Romania
T - Tall buildings area, Briggs-CNCAN, Romania
N - Normal Terrain, HOTSPOT, Lawrence Livermore NatLab, U.S.
U - Urban Terrain, HOTSPOT, Lawrence Livermore NatLab, U.S.
[sigma1]
valid$="CBKSMFGRWTNU"
warn$=""
k1$=upper$(left$(sys$,1))
if instr(valid$,k1$)=0 then
warn$="none"
return
end if
if k1$="C" then tip=0
if k1$="B" then tip=0
if k1$="K" then tip=0
if k1$="S" then tip=0
if hRel<=50 then k2$="1"
if hRel>50 and hRel<=180 then k2$="2"
if hRel>180 then k2$="3"
if k1$="M" then
tip=1
k2$="0"
end if
if k1$="F" then
tip=1
k2$="0"
end if
if k1$="G" then
tip=1
k2$="0"
end if
if k1$="R" then
tip=1
k2$="0"
end if
if k1$="W" then
tip=1
k2$="0"
end if
if k1$="T" then
tip=1
k2$="0"
end if
if k1$="N" then
tip=2
k2$="0"
end if
if k1$="U" then
tip=2
k2$="0"
end if
if k2$="X" then return
k3$=str$(class)
key$="["+k1$+k2$+k3$+"]"
open DefaultDir$+"\public\notepad\meteo\dis-sys.txt" for input as #1
while eof(#1)=0
line input #1,vo$
if instr(vo$,key$)>0 then
exit while
A2.10
end if
wend
close #1
return
[sigma2]
vo$=trim$(vo$)
if tip=0 then
'Py Qy Pz Qz hInv pH
Px=val(trim$(word$(vo$,2)))
Qx=val(trim$(word$(vo$,3)))
Pz=val(trim$(word$(vo$,4)))
Qz=val(trim$(word$(vo$,5)))
hInv=val(trim$(word$(vo$,6)))
pH=val(trim$(word$(vo$,7)))
sigy=Px*downwind^Qx
sigz=Pz*downwind^Qz
if sigz>0.8*hInv then sigz=0.8*hInv
if sigy=0 then sigy=sigy0
if sigz=0 then sigz=sigz0
return
end if
if tip=1 then
if downwind=0 then
sigy=sigy0
sigz=sigz0
return
end if
'a1 b1 a2 b2 c3 c1 d1 c2 d2 z0 hInv pH
a1=val(trim$(word$(vo$,2)))
b1=val(trim$(word$(vo$,3)))
a2=val(trim$(word$(vo$,4)))
b2=val(trim$(word$(vo$,5)))
c3=val(trim$(word$(vo$,6)))
c1=val(trim$(word$(vo$,7)))
d1=val(trim$(word$(vo$,8)))
c2=val(trim$(word$(vo$,9)))
d2=val(trim$(word$(vo$,10)))
z0=val(trim$(word$(vo$,11)))
hInv=val(trim$(word$(vo$,12)))
pH=val(trim$(word$(vo$,13)))
sigy=c3*downwind/((1+0.0001*downwind)^0.5)
gx=a1*(downwind^b1)/(1+a2*(downwind^b2))
if z0>0.1 then
Fx=log(c1*(downwind^d1)*(1+1/(c2*(downwind^d2))))
else
Fx=log(c1*(downwind^d1)/(1+(c2*(downwind^d2))))
end if
sigz=gx*Fx
if sigz>0.8*hInv then sigz=0.8*hInv
if sigy=0 then sigy=sigy0
if sigz=0 then sigz=sigz0
return
end if
if tip=2 then
if downwind=0 then
sigy=sigy0
sigz=sigz0
return
end if
'ay by az bz cz hInv pH
ay=val(trim$(word$(vo$,2)))
by=val(trim$(word$(vo$,3)))
az=val(trim$(word$(vo$,4)))
bz=val(trim$(word$(vo$,5)))
cz=val(trim$(word$(vo$,6)))
hInv=val(trim$(word$(vo$,7)))
pH=val(trim$(word$(vo$,8)))
A2.11
sigy=ay*downwind/((1+by*downwind)^0.5)
sigz=az*downwind/((1+bz*downwind)^cz)
if sigz>0.8*hInv then sigz=0.8*hInv
if sigy=0 then sigy=sigy0
if sigz=0 then sigz=sigz0
return
end if
return
A.2.2. Maşina de achiziţie şi prelucrare a datelor Demonstratorul de concept N-WATCHDOG (PoC) obtine datele de prognoza meteorologica din surse publice web – o tendinta in curs de conturare in Europa, unde platforma RODOS a deschis o directie de cercetare in acest sens. Tehnica utilizata in PoC recurge la urmatoarele:
(a) achizitia de date prin offline browsing facilitata de functii API ale sistemului de operare (Windows 7, 8);
(b) extractia datelor utile din fiserele de downolad prin HTML parsing; si (c) procesarea in runtime a datelor pentru aducerea lor in formatele necesare
codurilor. Schema operatiilor este redata in Figura A.2.1.
Fig. A.2.1. Schema de achizitie si prelucrare a datelor de prognoza meteorologica in N-WATCHDOG.
Alegerea furnizorilor de date publice primare a fost condusa de urmatoarele criterii:
Disponibilitatea de date suficiente necesitatilor de input ale codurilor, fie direct, fie prin inferare din alte date existente – cazul nebulozitatii si precipitatiilor;
Gradul de acoperire planetara cu statii meteorologice de furnizare a datelor pentru modelele de prognoza ale furnizorului web;
Frecventa de actualizare (refresh) a prognozelor; Stabilitatea formatului HTML/JS al paginiloror de web ale furnizorului;
A2.12
Stabilitatea serviciului web; Duratele de request-access cat mai indelungate, fara abandonarea clientului; Referintele utilizatorilor privind calitatea constatata a prognozelor.
Algoritmii si solutiile de implementare necesare sunt specifici fiecarui distribuitor web de date publice si vor forma obiectul unor transferuri interne de informatii in cadrul Proiecului, intre dezvoltatorii PoC si ai Modelului Experimental EM. Conform specificatiilor Proiectului PCCA aprobat, procedura este legal utilizabila in conditiile in care PoC ramane un produs intern de cercetare, fara finalitati comerciale in sine. In masura in care dezvoltatorul produsului final – N-WATCHDOG ME va contempla, ulterior Proiectului, derivarea din ME de produse distribuibile la beneficiari terti, se vor avea in vedere termenii de licentiere in utilizarea datelor de la site-urile de origine si aranjamente corespunzatoare cu organizatiile respective, sau apelul in conditii similare la alte surse.
A3.1
ANEXA 3.
Datele Geografice Cuprins
A.3.1. Termeni de referinţă ....................................................................................... A3.2 A.3.2. Resursele de date ........................................................................................... A3.2 A.3.3. Tipuri si versiuni .............................................................................................. A3.3 A.3.4. Soluţii de implementare .................................................................................. A3.6
A3.2
A.3.1. Termeni de referinţă Experienta autorilor in dezvoltarea de facilitati DSS de asistare a managementui urgentelor de mediu (v.e.g.[22, 30]) a determinat urmatoarea selectie a exigentelor impuse sistemului de informatii geografice (GIS – Geographical Infromation System) potrivit aplicatiilor N-WATCHDOG:
a) Hartile de situatie: Sa asigure o acoperire virtual completa a Planetei; Sa fie georeferentiate si redate intr-o proiectie simpla, cat mai apropiata de
perceptia vizuala comuna. Sa reveleze in moduri recognoscibile atat vizual cat si numeric topografia,
comunitatile, reteaua cailor de comunicatie si, in masura posibilului – intreprinderi, institutii de interes social si facilitati de servicii.
Sa fie generate dinamic in cadrul sesiunilor de lucru automate sau asistate ale platformei (in runtime), pe arii de cuprindere ce decurg din extensia spatiala a zonelor potential expuse.
Sa fie integrabile in Rapoartele de situatie, de arhiva desktop sau destinate publicarii pe Serverul N-WATCHDOG.
Sa fie interactive (interogabile on-click), atat la interfata runtime cat si in arhiva desktop si pe Server.
Sa fie permanent realizabile, indiferent de disponibiltatea www, asigurand necesitatile N-WATCHDOG.
b) Informatia geografica textuala: Sa cuprinda elemente primare suficiente pentru aprecierea Vulnerabilitatii
Statice a comunitatilor, conform programului de evaluare descris in sectiunea 4 a Raportului.
Sa fie formatabila in fisiere editabile pentru actualizare si imediat utilizabile in aplicatii.
A.3.2. Resursele de date
S-au au in vedere urmatoarele resurse (Tabelul A3.1):
Tabelul A.3.1. Aplicatia, sursele primare de date, stocul de date procesate
Tip aplicatie Resursa primara Procesarea
Harti topografice
desktop
SRTM90(NASA) – elevatii mase
continentale
SRTM30(NASA) – elevatii mase
continentale
NOAA ETOPO1 – zone costiere si
batimetrie
54 GB Random Access files
2.17 GB Random Access files
1.73 GB Random Access files
Harti multilayer
web
Google Maps
Google Earth
Google Maps API (JS)
Google Earth Plugin API (JS)
Informatie textuala Servicii web de localizare geografica 8.93 MB Sequencial I/O file
by manual acquisition
A3.3
A.3.3. Tipuri si versiuni
Figura A.3.1 prezinta tipurile de harta si versiunile de distributie avute in vedere.
Figura A.3.1. Hartile N-WATCHDOG: tipuri si versiuni de distributie.
Pentru distributia produsului se au vedere doua versiuni:
Versiunea ‘Gold’, ce ofera topografii recognoscibile precum si acuratete in calculul efectelor de teren asupra dispersiei atmosferice chiar si la raze de acoperire mici, de doar 3-5 km in jurul unei surse de emisii. ‘Gold’ foloseste ca sursa DEM SRTM-90 (NASA), cu o rezolutie de 90x90 m pe celula de grid la Ecuator.
Versiunea ‘Silver’, practicabila sub aspectul recunoasterii vizuale a terenului si a acuratetei de calcul, dar inferioara versiunii ‘Gold’. ‘Silver’ foloseste ca sursa DEM SRTM-30 (NASA), cu o rezolutie considerabil mai defavorabila, de cca 1000x1000 m pe celula de grid.
Ambele versiuni recurg, pentru reprezentarea vizuala a zonelor costiere si a ariei oceanice la sursa DEM NOAA-ETOPO1, cu o rezolutie inferioara resurselor SRTM 90 si 30 – fapt ce ramane insa fara consecinte de fond, deoarece modelele fizice sunt sensibile numai la elevatiile suprafetelor de reflexie (in cazul Oceanului/marilor, 0 m). Tranzitia de la masa continentala la aceste zone se asigura automat, de masina de harti (map engine) a codurilor. De asemenea, ambele versiuni ofera produsul vizual atat in mod-raster cat si in mod-contur de izoelevatii, in paleta de culori sau nuante de gris. Figurile A.3.2. – A.3.4 compileaza scurte descrieri ale resurselor DEM, din prezentarile originale ale site-urilor de origine, sau distribuitoare. Startegia de distributie a versiunilor (‘Gold’ – 55.73GByte si ‘Silver’ – 3.9Gbyte) in produsul final N-WATCHDOG EM se va stabili in faze ulterioare ale Proiectului.
A3.4
Fig. A.3.2. SRTM 90 (NASA)
A3.5
Fig. A.3.3. SRTM 30 (NASA)
Fig. A.3.4. ETOPO1 (NOAA)
A3.6
A.3.4. Soluţii de implementare Masinile de harta (map engines) ale N-WATCHDOG valorifica resursele de date primare. Tabelul A.3.2 prezinta un rezumat al modurilor de abordare.
Tabelul A.3.2. Tipuri de harta si ‘masini de harta’ (map engines).
Map Type Map Engine
Desktop Topografic, Raster Canvas scanner-plotter interpolating DEM grid at pixel level. QB64 Application
Desktop Topografic, Contours
Canvas 168 x 168 grid scanner-liner interpolating DEM grid via Paul Bourke’s CONREC algorithm. LB 4.03 Application
Web, 2-D Basic Map Google Maps™ Hybrid Application: LB 4.03 + HTML5 + Google Maps API (JavaScript)
Web, 2-D Hybrid Google Maps™ Hybrid Application: LB 4.03 + HTML5 + Google Maps API (JavaScript)
Web, 3-D Earth Google Earth™ Hybrid Application: LB 4.03 + HTML5 + Google Earth Plugin API (JavaScript)
Ca si in cazul datelor meteorologice (v. Anexa 2), algoritmii si solutiile de implementare necesare vor forma obiectul unor transferuri interne de informatii in cadrul Proiecului, ce vor fi convenite intre dezvoltatorii PoC si ai Modelului Experimental EM. Conform specificatiilor Proiectului PCCA aprobat, procedura de utilizare a datelor DEM din surse publice este legala in conditiile in care PoC ramane un produs intern de cercetare, fara finalitati comerciale in sine. In masura in care dezvoltatorul produsului final – N-WATCHDOG ME va contempla, ulterior Proiectului, derivarea din ME de produse distribuibile la beneficiari terti, se vor avea in vedere termenii de licentiere in utilizarea datelor de la site-urile de origine si aranjamente corespunzatoare cu organizatiile respective, sau apelul in conditii similare la alte surse.
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A4.1
ANEXA 4
Supliment bibliografic
A4.2
Vamanu D.V., Vamanu B.I., Acasandrei V.T., Maceika E. and Plukis A. EURISOL Desktop Assisstant Toolkit (EDAT): A Modeling, Simulation and Visualization Support to the Preliminary Radiological Assessment of RIB Projects. The European Physical Journal A – Hadrons and Nuclei, Volume 44, No.1, Springer Berlin/Heidelberg, ISSN: 1434-6001 (Print) 1434-601X (Online), DOI 10.1140/epja/i2010-10935-9, pp. 129–146, 2010. U.S.EPA (1993). External Exposure to Radionuclides in Air, Water, and Soil, FRG-12 EPA-402-R-93-081 (U.S.A.). U.S.EPA (1988). Limiting Values of Nuclide Intake and Air concentration, and Dose Conversion Factors for Inhalation, Submersion and Ingestion, FRG-11 EPA 520/1-88-020 (U.S.) IAEA (2000). Generic Procedures for Assessment and Response During a Radiological Emergency. IAEA-TECDOC-1162, ISSN 1011–4289. IAEA (2001). Generic Models for Use in Assessing the Impact of Discharges of Radioactive Substances to the Environment. Safety Reports Series No.19. International Atomic Energy Agency Vienna, 2001. Vamanu D.V., Acasandrei V.T., and Vamanu B.I. Safety risks in spent nuclear fuel road transportation: ‘black swans’ by malicious intent. Romanian Reports in Physics, Volume 66, No. 3, 2014.
Vamanu D.V., Slavnicu D.S., Vamanu B.I., V.T., Acasandrei and Gheorghiu D. Safety risks in spent nuclear fuel air transportation - a ‘black swan’ anatomy. Romanian Reports in Physics, Volume 66, No. 2, 2014.
Gheorghe A.V., Vamanu D.V. Resilience Governance through Serious Energy Gaming. EAI Endorsed Transactions on Energy Web. January-June 2013, Volume 13, Issues 01-06, e3. doi: 10.4108/trans.ew.2013.01-06.e3, 2013.
Vamanu B.I., Vamanu D.V. and Acasandrei V.T. (2012). Rationalizing disasters: the Standing Anticipation of Dynamic Vulnerabilities. Conference and partnering event on resilience against disasters - CONCERT Japan. Oral and poster presentation. Tokyo, Japan, 10-11 september 2012. Vamanu D.V., Slavnicu S.D, Galeriu D., Acasandrei V.T., Gheorghiu D. and Melintescu A. Decommissioning Research Reactors: A Case of a Reference Accident Scenario. Romanian Reports in Physics, Vol.63, No.1, pp. 50–66, 2011. Vamanu D., Gheorghe A. Situation Assessment Toolkit: the case of the Fukushima Accident. Second International Conference on Integrated Disaster Risk Management, IDRIM, Reframing Disasters and Reflecting on Risk Governance Deficits, University of Southern California, Los Angeles, California, July 14 -16, 2011. http://conference2011.idrim.org/IDRiM%202011%20Book%20of%20Abstracts%20With%20 Cover1.pdf. Vamanu D.V., Galeriu D., Slavnicu D.S., Stochioiu A., Acasandrei V.T., Melintescu A. and Gheorghiu D. Fukushima. Monitorizare IFIN-HH. IFIN-HH, Website IFIN-HH, martie-mai 2011. http://www.nipne.ro/fukushima_2011. Vamanu D.V., Vamanu B.I., Acasandrei V.T., Maceika E. and Plukis A. EURISOL Desktop Assisstant Toolkit (EDAT): A Modeling, Simulation and Visualization Support to the Preliminary Radiological Assessment of RIB Projects. The European Physical Journal A – Hadrons and Nuclei, Volume 44, No.1, Springer Berlin/Heidelberg, ISSN: 1434-6001 (Print) 1434-601X (Online), DOI 10.1140/epja/i2010-10935-9, pp. 129–146, 2010. Vamanu D.V., Slavnicu S.D, Gheorghiu D, Acasandrei V.T. and Slavnicu E. The Hydrological Impact Assessment in the Decision Support of Nuclear Emergency Response. Radiation Protection
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Dosimetry, Technical Note, doi:10.1093/rpd/ncq048, Online ISSN 1742-3406, Print ISSN 0144-8420, pp. 1-11, 2010. Vamanu D.V., Gheorghe A.V. and Acasandrei V.T. Urban vulnerabilities: think simple International Journal Critical Infrastructures, Vol. 6, No. 3, pp. 304-325, 2010. Slavnicu S.D, Vamanu D.V., Gheorghiu D., Acasandrei V.T. and Slavnicu E. Assessing the Hydrological Impact in Nuclear Emergencies. Proceedings of the Third European IRPA Congress, June 14 – 16, 2010, Helsinki, Finland. 2010. Gheorghe A.V., Vamanu D. Vulnerability of Critical Infrastructure Systems: A Physical Analogy for Modeling Complex Hysteresis Behavior. Proceedings of The 10th International Probabilistic Safety Assessment & Management Conference (PSAM 10). June 7-11, 2010, Seattle Washington.
Slavnicu S.D, Vamanu D.V., Gheorghiu D., Acasandrei V.T. and Slavnicu E. Nuclear Emergency Response Exercises and Decision Support Systems – Integrating Domestic Experince with International Reference Systems. Proceedings of the European Nuclear Conference, May 30 – June 2, 2010, Barcelona, Spain, , ISBN 978-92-95064-09-6, 2010. Slavnicu D.S., Vamanu D.V., D. Gheorghiu, V.T. Acasandrei and Vamanu B.I. Decision support systems and emergency response exercises – lessons and issues. Radioprotection, vol. 44, no. 5, pp 97–101, ISBN: 978-2-7598-0447-4, 2009. Gheorghiu D., Slavnicu D.S., Vamanu D.V., Acasandrei V.T. Rodos and Acolytes: Integrating Domestic Experience With International Reference Decision Support Systems. Final Meeting of the EURANOS Project, “Final Contractors Meeting” and “Users Groups Meetings”, CIEMAT, Madrid, Spain, 22-26 June 2009. Gheorghe A.V., Vamanu D.V. From Risk Governance to Resilience Governance National Science Foundation (NSF) Meeting on Resilience, Sustainability and Critical Infrastructures, Alexandria, Virginia, USA, December 6, 2009. Gheorghe A.V., Muresan L. Vamanu D.V. Threats and Vulnerability Assessment of Maritime Infrastructure Systems. USA Navy - GCC Meeting on Critical Maritime Infrastructure Protection, Bahrain, February 10, 2009. Gheorghe A.V., Vamanu D.V. International Activities on System of Systems Engineering: an European Perspective. Workshop on System of Systems Engineering - State of the Art, University of New Mexico, New Mexico, USA, March 16 2009. Gheorghe A.V., Vamanu D.V. Critical Infrastructure Protection at Regional Level: Development and Use of DSS. Workshop on Regional Assessment of Critical Infrastructures, Bucharest, November 13, 2009. Slavnicu D.S., Vamanu D.V., Gheorghiu D., Acasandrei V.T. and Vamanu B.I. Decision Support Systems and Emergency Response Exercises – Lessons and Issues. International Conference on Radioecology and Environmental Radioactivity in Bergen, Norway, 15 – 20 June 2008. Vamanu D.V., Slavnicu D.S., Gheorghiu D., Acasandrei V.T. and Vamanu B.I. Decision Support Systems and Health and Environmental Impact in a Radioactive Release. Sesiunea stiintifica “Stiinte aplicate in studiul mediului inconjurator si materialelor”, Targoviste, 4-6 iunie, 2008. Gheorghe A.V. and Vamanu D.V. Homeland Security Related Issues with ‘Minor League’ Nuclear Infrastructures: Critical Topics on the Decommissioning of Research Reactors. 2nd Annual Homeland Defense and Security Education Summit, University of Maryland University College, USA, Summit sponsored and organized by The Naval Postgraduate School Center for Homeland Defense and Security, The Homeland Security/Defense Education Consortium, The U. S. Department of Homeland Security, and The University of Maryland University College, Mar 18-19, 2008.
A4.4
Slavnicu D.S., Vamanu D.V., Gheorghiu D., Gheorghiu A., Acasandrei V.T., Vamanu B.I. Decision support systems. The evaluation of environmental impact in a radioactive release. National Conference of Physics, Magurele (Bucuresti), Romania, September 10 - 13, 2008 Slavnicu D.S., Vamanu D.V., Gheorghiu D., Vamanu B.I., Acasandrei V.T. and Gheorghiu A. Decission Support Systems – the Evaluation of Health and Environmental Impact in a Radioactive Release Romanian Reports in Physics, Volume 60, nr. 4, pp. 1115-1122, 2008 Gheorghe A.V. and Vamanu D.V. Quantitative Vulnerability Assessment of Critical Infrastructures: watching for hidden faults. International Journal of Critical Infrastructures, Vol. 4, Nos. 1/2, 2008, pp.144-152, 2008 Vamanu D.V., Gheorghe A.V., Acasandrei V.T. and Vamanu B.I. Critical Issues with ‘Minor League’ Nuclear Infrastructures: The Back End of the Life Cycle. International Journal of Critical Infrastructures, Volume 4, No. 4, ISSN (Print): 1475-3219, ISSN (Online): 1741-8038, pp. 368-391, 2008 Slavnicu D.S., Vamanu D.V., Gheorghiu D., Acasandrei V.T. and Vamanu B.I. Decision Support Systems and Emergency Response Exercises – Lessons and Issue. Proceedings of the International Conference on Radioecology and Environmental Radioactivity in Bergen, Norway, pp. 150-153, 15–20 June 2008. Gheorghe A.V., Vamanu D.V. Testing Critical Infrastructure Vulnerability: An Essay in Probabilistic Resilience Analysis. Published in NATO Science for Peace and Security Series: Information and Communication Security – Volume 13 ‘Computational Models of Risks to Infrastructure’, Editors: D. Skanata and D.M. Byrd August 2007, pp. 226-247, hardcover ISBN: 978-1-58603-766-6, IOS Press, The Netherlands, 2007. Gheorghe A.V. and Vamanu D.V. Risk and vulnerability games. The anti-satellite weaponery (ASAT). International Journal of Critical Infrastructures, Vol. 3, Nos. 3/4, pp. 457-470, 2007. Slavnicu D.S., Vamanu D.V., Gheorghiu D., Acasandrei V.T., Vamanu B.I. CONVEX-3: A Case for Flexible Strategies in Nuclear Emergency Assessment. Proceedings of the 11th International Conference on Harmonisation within Atmospheric Dispersion Modelling for Regulatory Purposes, London, U.K., pp. 91-95, July 2-6, 2007. Vamanu B.I, Acasandrei V.T. and Vamanu D.V. EURISOL – radioprotection tools – the Desktop Assistant. Joint EURISOL-EURONS Town Meeting, Helsinki, Finland, 17 – 20 September, 2007. Poster presentation. Vamanu D.V., Slavnicu D.S., Gheorghiu A., Vamanu B.I., Acasandrei V.T. Exerciţiul de alertă nucleară “OLTENIA-2007”. IFIN-HH Raport tehnic, octombrie 2007.
Gheorghe A.V., Vamanu D.V. Critical Electricity Infrastructure: Current Experience in Europe, in Critical Infrastructures at Risk. Securing the European Electric Power System, eds. A.V. Gheorghe, M. Masera, M. Weijnen, and L. De Vries (Springer, Netherlands), Topics in Safety, Risk, Reliability and Quality Series, ISBN-10 1-4020-4306-6 (HB), ISBN-13 978-1-4020-4306-2 (HB), ISBN-10 1-4020-4364-3 (e-book), ISBN-13 978-1-4020-4364-2 (e-book), Volume 9, pp.195-253, 2006. Gheorghe A.V., Vamanu D.V. Another Tool in the Business of Spatial Framing of Illicit / Lost from Account Radioactive Material: Helping the AT (Anti-Terrorism) Paraphernalia Thrive. International Journal of Critical Infrastructures, Vol.2, No.4, Pages 347-356, 2006. Vamanu D.V., Slavnicu D.S., Gheorghiu D., Acasandrei V.T., Vamanu B.I. Adaptive Strategies in Nuclear Emergency Assessment: The ConvEX-3 Case. Romanian Reports in Physics. Vol.58, No.4, Pages 539-558, 2006 Gheorghe A.V., Vamanu D.V. Vulnerability Assessment of Critical Infrastructures. International Conference on Complex Systems, June 25-30, 2006.
A4.5
Gheorghe A.V., Vamanu D.V. Vulnerability of Critical Infrastructures Exposed to Technical Failures or Natural Hazards. Chernobyl and Katrina: Two Names to Make History. Sixth Annual IIASA-DPRI Forum on Integrated Disaster Risk Management: Risks and Challenges for Business and Industry, , Istanbul, Turkey, 13 – 16 August, 2006. Gheorghe A.V., Vamanu D.V. Modeling Vulnerability of Interdependent CriticalInfrastructure: from Graphs to Models with Strange Attractors. NATO Meeting on Modeling Complex Systems, 15 – 18 May, Split, Croatia. Published in NATO Security through Science Series, IOS Press, Netherlands, 2006. Vamanu D.V., Slavnicu D.S., Gheorghiu A., Vamanu B.I., Acasandrei V.T. Evaluarea documentului “Revizia raportului final de securitate pentru DCNU”. IFIN-HH Raport tehnic intern, comanda nr.523/10.03.2006, martie 2006.
Gheorghe A.V., Birchmeier J., Vamanu D.V., Papazoglou I., Kroeger W. Comprehensive risk assessment for rail transportation of dangerous goods: a validated platform for decision support. Reliability Engineering & System Safety, Elsevier, 88, pp. 247-272, 2005 Gheorghe A.V., Vamanu D.V. On the Vulnerability of Critical Infrastructures: Seeing it Coming. International Journal of Critical Infrstructures, Vol. Nos 2-3, 2005. Gheorghe A.V., Vamanu D.V. Reading vulnerability in phase portraits: an exercise in probabilistic resilience assessment. International Journal of Critical Infrastructures, vol. 1, no. 4, pp. 312-330. Gheorghe A.V., Vamanu D.V. Risks in Business Design for Critical Infrastructures: the ‘DASHBOARD’ Concept. International Journal of Critical Infrstructures, Vol.2, No.1, Pages 70-82, 2005 Acasandrei V.T., Vamanu B.I. and Vamanu D.V. Cost assessment in nuclear decommissioning: a useful tool. Analele Universitatii Bucuresti, LIV, 2005, pp.19-31 (publicata octombrie 2007), 2005. Gheorghe A.V., Vamanu D.V. Critical Infrastructures Protection: From Systems Engineering to System of Systems Engineering. Use of Cellular Automata Modeling. International Conference on Resilient Infrastructures, Rotorua, New Zealand, September 2005. Gheorghe A.V., Vamanu D.V. Pixel as a Source of Input, Pixel as a Support of Output. Gulf Area International Workshop on the Use of GIS, Al Kuwait, 2005. Gheorghe A.V., Vamanu D.V. GIS: Pixels, Analytic Models Cellular Automata: A New Kind of Modeling. Gulf Area International Workshop on the Use of GIS, Al Kuwait, 2005. Gheorghe A.V., Vamanu D.V. Quantitative Vulnerability Assessment of Critical Infrastructures: Watching for Hidden Faults. Task Force G8 Meeting on Critical Energy Infrastructures, Brussels, November, 2005. Gheorghe A.V., Vamanu D.V. Quantitative Vulnerability Assessment for Critical Infrastructures: Bridging Risk Management and Safety. Proceedings of the International Conference on Risk and Safety Management, Hong Kong 2005. Gheorghe A.V., Vamanu D.V. Towards a Standard Model of Societal Vulnerability to Natural Disasters. The Katrina Paradigm OECD Workshop on Science and Technology for a Safer Society, Tokyo, Japan, December 5-6, 2005. Gheorghe A.V., Vamanu D.V. A cellular automaton approach to air flow dispersion in urban areas. Proceedings on Systems Analysis for a More Secure World: Application of System Analysis and REMS to Security of Complex Systems, Giacomo G.M. Cojazzi, Editor, EC JRC Ispra, pp. 369-383. 2005. Gheorghe A.V., Vamanu D.V. Daily Regional Vulnerability of Infrastructures to Obnoxious Agents. How vulnerable are you today? Proceedings of the Annual IIASA-DPRI Meeting on Integrated Disaster Risk Management, Beijing, September 2005.
A4.6
Gheorghe A.V., Vamanu D.V. GIS: Pixels, Analytic Models, Cellular Automata. Innovations in Science and Policy for Risk and Vulnerability Assessment of Critical Infrastructures Proceedings of the Annual IIASA-DPRI International Meeting on Integrated Disaster Risk Management, September, 2005. Vamanu D.V., Slavnicu D.S., Gheorghiu D., Acasandrei V.T., Vamanu B.I. Riscuri eco-sanitare şi limite derivate de eliberare a radioactivităţii din activităţile de dezafectare a reactorului VVR-S, IFIN-HH. IFIN-HH Raport tehnic intern, comanda nr.933/20.07.2005, iulie 2005. Vamanu D.V., Slavnicu D.S., Gheorghiu D., Acasandrei V.T., Vamanu B.I. ConvEX 3 International Emergency Management Exercise: IFIN-HH/NIPNE Decision Support. A Technical Report, mai 2005. Gheorghe A.V., Vamanu D.V. Decision support systems for risk mapping: viewing the risk from the hazards perspective. Journal of Hazardous Materials, Volume 111, Issues 1-3, pp.45-55, 2004 Gheorghe A.V., Vamanu D.V. Complexity-Induced Vulnerability. International Journal of Critical Infrastructures, Vol. 1, no. 1, 2004, pp.76-85, 2004 Vamanu D.V., Slavnicu D.S., Slavnicu E., Vamanu B.I. Decision Support Systems in Nuclear Emergencies: A Scenario-Based Comparison of Domestic and Reference Tools. Radiation Protection Dosimetry , 112, 209 – 218, December, 2004 Gheorghe A.V., Birchmeier J, Vamanu D.V., Papazoglou I, Kröger W. Integrated Risk Assessment for Rail Transportation of Dangerous Goods: Decision Support Platform and an SBB Case Study. Reliability Engineering and System Safety, Elsevier, 2004. Gheorghe A.V., Birchmeier J., Kroeger W., Vamanu D.V., Vamanu B.I. Advanced Spatial Modeling forRisk Analysis in the Transportation of Dangerous Goods. PSAM7 – ESREL’04 Proceedings of the 7th International Conference on Probabilistic Safety Assessment and Management, 14-18 June 2004, Berlin, Germany (Published by Springer Verlag: London, Berling, Heidelberg, 2004). Vamanu D.V., Slavnicu D.S., Acasandrei V.T., Vamanu B.I. Radiological Assessment Assistance to Decommissioning. International Atomic Energy Agency Technical Meeting, Vienna, 1-3 November, 2004. Poster presentation. Vamanu D.V., Acasandrei V.T., Vamanu B.I. Aplicaţia interjudeţeană “Muntenia-2004”. Exerciţiu de protecţie civilă în caz de accident radiologic la IFIN-HH. Raport tehnic intern, septembrie 2004. Vamanu D.V., Slavnicu D.S., Gheorghiu D., Acasandrei V.T., Vamanu B.I. IFIN-HH Limite derivate de emisie ale instalaţiilor nucleare. IFIN-HH Raport tehnic intern, comanda nr. 1590/30.04.2004, aprilie 2004. Vamanu D.V., Gheorghe A.V., Vamanu B.I. On a Generic Model in Quantitative Vulnerability Assessment. Romanian Journal of Physics Supplement, Vol.48, pp 229-237, 2003. Gheorghe A.V., Vamanu D.V. Risk'o Meter and Living Risk Assessment. Inteligent Monitoring Integration. Workshop on Advancements in Accident Management Investigation. Invited presentation, Winterthur Insurance Company, Winterthur, Switzerland, 18 March 2003. Gheorghe A.V., Vamanu D.V. Risk, Vulnerability, Sustainability and Governance. Invited paper presented at the Telecom DoCoMo Seminar, Tokyo, Japan, 24 March 2003. Gheorghe A.V., Vamanu D.V. Dealing with Integrated Risk and Vulnerability Management. A new Way in Corporate Governance. Workshop in Corporate Governance, Zürich, ETH, Switzerland, 10 May 2003. Gheorghe A.V., Doerig A., Vamanu D.V. Towards a new Horizon in Corporate Governance. Think Tank Paper, UBS, Wolfsberg, Switzerland, June 30, 2003.
A4.7
Gheorghe A.V., Vamanu D.V. Disaster Risk Management: Complexity Induced Vulnerability Management. International Workshop on Risk and Vulnerability Management, Kyoto, Japan, 27 July 2003. Gheorghe A.V., Vamanu D.V. Satellite Assisting Risk and Vulnerability Assessment for the Transportation of Dangerous Goods: Setting the Issues for Models and DSS. Joint Workshop ETH Zurich-Italian Space Agency on New Trends for Satellite Use in Risk Analysis, Zürich, Switzerland, 2 September 2003. Gheorghe A.V., Vamanu D.V. Decision Support System for Risk Management. European Commission, International Workshop on Severe Accident Management, Petten, Holland, 15 September 2003. Vamanu D.V., Isbasescu M., Berinde Al., Slavnicu D.S, Gheorghiu D., Acasandrei V.T, Vamanu B.I. Plan dezafectare Reactor VVR-S. Cap. 3.4. Evaluarea impactului asupra mediului. Raport tehnic intern, ianuarie 2003.
Vamanu D.V., Slavnicu D.S., Mateescu Ghe., Berinde Al., Acasandrei V.T. A Code Comparison Exercise within the European Project RODOS: Harmonizing Domestic and Reference Tools. International Journal of Risk Assessment and Management, vol.3, Nos 2/3/4, pp. 113-134, 2002 Gheorghe A.V., Vamanu D.V. Integrated Risk Assessment and Safety Management; Transportation of Dangerous Goods. International Journal of Risk Assessment and Management, Vol.3, Nos.2/3/4, 2002. Gheorghe A.V., Vamanu D.V. Vulnerability Assessment of Sustainable Energy Policies. Invited Presentation, ‘Technical Committee Meeting on Energy and Sustainable Development’, International Atomic Energy Agency, Vienna, Austria, 11 May 2002. Gheorghe A.V., Vamanu D.V. Emergency Management and Planning: Use of DSS and Knowledge Based Systems. Invited Presentation, the United Nations Office for Coordination of Humanitarian Affairs, Geneva, Switzerland, 18 June 2002. Gheorghe A.V., Vamanu D.V. Complexity Issues in Modelling of Vulnerability and Risk Management Processes. Invited Lecture, ‘The Future of Switzerland’ Foundation, Zürich, Switzerland, 27 August 2002. Gheorghe A.V., Vamanu D.V. The Risk’o Meter Concept. Proceedings of the 6th International Conference on Probabilistic Safety Assessment and Management, 23-28 June 2002, Vol. I, Elsevier, Amsterdam. Gheorghe A.V., Vamanu D.V. Quantitative Vulnerability Assessment for Critical Infrastructures. Proceedings of the 6th International Conference on Probabilistic Safety Assessment and Management, 23-28 June 2002, Vol. I, Elsevier, Amsterdam, 2002. Gheorghe A.V., Vamanu D.V. Vulnerability of Vital Systems: Impacts to Governance. Academia Europea Annual Meeting, ‘The Sciences and the Understanding of Risk: Policies for Public Trust and Well Being’, Lisbon, Portugal, 9-12 October 2002. Gheorghe A.V., Vamanu D.V. Disaster Risk and Vulnerability Management. Invited Presentation, Nazional Alarm Zentrale (NAZ), Zürich, Switzerland, 10 April 2002. Gheorghe A.V., Vamanu D.V. Sensors and Intelligent Monitoring Integration: Risk’o Meter. Workshop on Sciences and Technology within Societal Context, University of Tokyo, Japan, 25 January 2002. Gheorghe A.V., Vamanu D.V. Vulnerability Assessment in the Context of Sustainable Development. Annual Meeting of the Alliance for Global Sustainability (AGS), San Jose, Costa Rica, 21 March 2002.
A4.8
Gheorghe A.V. and Vamanu D.V. Adapting to new challenges: IDSS for emergency preparedness and management. International Journal of Risk Assessment and Management, Volume 2, Numbers 3-4 / 2001, pp.211 – 223, 2001. Gheorghe A.V., Vamanu D.V. Indicators for Vulnerability Assessment and Management of Critical Infrastructures. Proceedings of the 5 th International Conference on Technology, Policy and Innovation: Main Theme - Critical Infrastructures, The Hague, The Netherlands, June 26-29, 2001. Gheorghe A.V., Vamanu D.V. The Risk Cadastre from a Concept Outline to Effective Implementation. Proceedings of the Conference and Workshops on Risk Analysis and Safety Management of Technical Systems, Gdansk, Poland 25-26 June 2001. Vamanu D.V., Slavnicu D.S., Mateescu Ghe., Berinde Al. Harmonizing Domestic and Reference Software Tools for Nuclear Accident Consequence Assessment. 7th International Conference on Harmonising within Atmospheric Dispersion Modeling for Regulatory Purposes, JCR-EI Belgirate, Italy, May 28-31, 2001. Gheorghe A.V., Vamanu D.V. Decision-support software tools for integrated risk assessment of hazardous substances in complex terrain. International Journal of Environment and Pollution, (4) 352-370, 1998.
Gheorghe A.V., Vamanu D.V. Emergency Planning Knowledge. Series: Dokumente/Polyprojekt Risiko und Sicherheit Nr. 13, VDF Verlag der Fachvereine Zurich, ISBN-10 3-7281-2201-7, p.239, 1996
Vamanu D.V., Gheorghe A.V. A heuristic approach to particle flows in complex terrain. International Journal of Environment and Pollution, (4-6) 462-490, 1996 Gheorghe A.V., Vamanu D.V. Sophisticated and intelligent systems and approaches in emergency engineering and management. International Journal of Global Energy Issues, (1-2) 82-98, 1995 Gheorghe A.V., Vamanu D.V. A pilot decision support system for nuclear power emergency management. Safety Science-Elsevier, Volume 20, Issue 1, pp.13-26, ISSN: 0925-7535, 1995 Vamanu D.V., Sandru P., Gheorghe A.V. Risk Culture in Romania - How Bitter the Pill? Proceedings of the 3rd International Conference of the Society for Risk Analysis (SRA), Paris, December 1991 Ursu I., Vamanu D.V., Gheorghe A.V., Purica I.I. Socioeconomic risk in development of energy systems. Risk Analysis, Risk Analysis, Volume 5, Issue 4, pp.315–326, 1985 Ursu I., Purica I.I., Vamanu D.V. Towards More Safety: Observing Synergisms in Reactor Behaviour. In “Nuclear Power Experience”, vol.IV, paper IAEA-CN-42-139, pp.255-266. International Atomic Energy Agency, Vienna, 1983 Vamanu D.V. Energy Pattern, Options and their Articulation in Romania. In Papers of the 12th Congress of the World Energy Conference, New Delhi, 18-23 September 1983. Ursu I., Vamanu D.V. Motivations and Attitudes in the Long-Term Planning of Alternative Energy Systems. In Proc. UNITAR Conference on Long-Term Energy Resources, Montreal, 26 November-7 December 1979. Vol.II, paper CF7/XXI/2. UNITAR, New York. i.q. in “Long-Term Energy Resources”, vol.I. Pitman (Boston-London- Melbourne-Toronto), 1981.
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