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The physics design of EBR-II; Physique du reacteur EBR-II; Fizicheskij raschet ehksperimental'nogo reaktora - razmnozhitelya EVR-II; Aspectos fisicos del reactor EBR-II

Conference:

Abstract

The physics design oi EBR-II. Calculations of the static, dynamic and long-term reactivity behaviour of EBR-II are reported together with results and analysis of EBR-II dry critical and ZPR-III mock-up experiments. Particular emphasis is given to reactor-physics design problems which arise after the conceptual design is established and before the reactor is built or placed into operation. Reactor-safety analyses and hazards-evaluation considerations are described with their influence on the reactor design. The manner of utilizing the EBR-II mock-up on ZPR-III data and the EBR-II dry critical data is described. These experiments, their analysis and theoretical predictions are the basis for predetermining the physics behaviour of the reactor system. The limitations inherent in applying the experimental data to the performance of the power-reactor system are explored in some detail. This includes the specification of reactor core size and/or fuel-alloy enrichment, provisions for adequate operating and shut-down reactivity, determination of operative temperature and power coefficients of reactivity, and details of power- and flux-distribution as a function of position within the reactor structure. The overall problem of transferring information from simple idealized analytical or experimental geometry to actual hexagonal reactor geometry is described. Nuclear performance, including breeding, of the actual reactor system is  More>>
Authors:
Loewenstein, W. B. [1] 
  1. Argonne National Laboratory, Argonne, IL (United States)
Publication Date:
Mar 15, 1962
Product Type:
Conference
Report Number:
IAEA-SM-18/39
Resource Relation:
Conference: Seminar on Physics of Fast and Intermediate Reactors, Vienna (Austria), 3-11 Aug 1961; Other Information: 33 refs, 16 figs, 20 tabs; Related Information: In: Physics of Fast and Intermediate Reactors. V. III. Proceedings of the Seminar on the Physics of Fast and Intermediate Reactors. V. III| 633 p.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BREEDING; DESIGN; EBR-2 REACTOR; ENRICHMENT; POWER COEFFICIENT; REACTIVITY; REACTIVITY INSERTIONS; REACTOR CORES; REACTOR OPERATION; REACTOR PHYSICS; REACTOR SAFETY; SAFETY ANALYSIS
OSTI ID:
22092517
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Other: ISSN 0074-1884; TRN: XA13S0035050783
Submitting Site:
INIS
Size:
page(s) 263-314
Announcement Date:
May 06, 2013

Conference:

Citation Formats

Loewenstein, W. B. The physics design of EBR-II; Physique du reacteur EBR-II; Fizicheskij raschet ehksperimental'nogo reaktora - razmnozhitelya EVR-II; Aspectos fisicos del reactor EBR-II. IAEA: N. p., 1962. Web.
Loewenstein, W. B. The physics design of EBR-II; Physique du reacteur EBR-II; Fizicheskij raschet ehksperimental'nogo reaktora - razmnozhitelya EVR-II; Aspectos fisicos del reactor EBR-II. IAEA.
Loewenstein, W. B. 1962. "The physics design of EBR-II; Physique du reacteur EBR-II; Fizicheskij raschet ehksperimental'nogo reaktora - razmnozhitelya EVR-II; Aspectos fisicos del reactor EBR-II." IAEA.
@misc{etde_22092517,
title = {The physics design of EBR-II; Physique du reacteur EBR-II; Fizicheskij raschet ehksperimental'nogo reaktora - razmnozhitelya EVR-II; Aspectos fisicos del reactor EBR-II}
author = {Loewenstein, W. B.}
abstractNote = {The physics design oi EBR-II. Calculations of the static, dynamic and long-term reactivity behaviour of EBR-II are reported together with results and analysis of EBR-II dry critical and ZPR-III mock-up experiments. Particular emphasis is given to reactor-physics design problems which arise after the conceptual design is established and before the reactor is built or placed into operation. Reactor-safety analyses and hazards-evaluation considerations are described with their influence on the reactor design. The manner of utilizing the EBR-II mock-up on ZPR-III data and the EBR-II dry critical data is described. These experiments, their analysis and theoretical predictions are the basis for predetermining the physics behaviour of the reactor system. The limitations inherent in applying the experimental data to the performance of the power-reactor system are explored in some detail. This includes the specification of reactor core size and/or fuel-alloy enrichment, provisions for adequate operating and shut-down reactivity, determination of operative temperature and power coefficients of reactivity, and details of power- and flux-distribution as a function of position within the reactor structure. The overall problem of transferring information from simple idealized analytical or experimental geometry to actual hexagonal reactor geometry is described. Nuclear performance, including breeding, of the actual reactor system is compared with that of the idealized conceptual system. The long-term reactivity and power behaviour of the reactor blanket is described within the framework of the proposed cycling of the fuel and blanket alloy. Safety considerations, including normal and abnormal rates of reactivity-insertion, the implication of postulated reactivity effects based on the physical behaviour of the fuel alloy and reactor structure as well as extrapolation of TREAT experiments to the EBR-II system are analysed. The EBR-II core melt-down problem is reviewed. (author) [French] L'auteur presente les calculs du comportement d'EBR-II statique, dynamique et sous evolution a long terme de la reactivite ainsi que les resultats et l'analyse des experiences critiques seches faites sur EBR-II et en simulation sur ZPR-III. Il insiste particulieremen t sur les problemes de physique des reacteurs qui, dans l'elaboration du projet, suivent le choix du modele theorique et precedent la construction ou la mise en exploitation. L'auteur presente des analyses de la securite des reacteurs ainsi que diverses considerations sur l'evaluation des risques sous l'angle de leur influence sur le projet de reacteur. Il decrit la simulation d'EBR-II, a partir des renseignements fournis par le ZPR-III ainsi que les mesures critiques seches sur EBR-II. Ces experiences, leur analyse et les previsions des calculs servent de bases pour predire le comportement physique du reacteur. L'auteur approfondit quelque peu la validite intrinseque de l'application des donnees experimentales au fonctionnement du reacteur de puissance. Ceci comprend les donnees precises des dimensions du coeur et/ou de l'enrichissement de l'alliagne combustible, le choix convenable des valeurs de la reactivite prevues en exploitation et pendant l'arret, la determination des coefficients de reactivite a la temperature et a la puissance de fonctionnement, et la distribution precise de la puissance et du flux en fonction de la position dans l'ensemble du reacteur. L'auteur decrit le probleme de l'application des renseignements obtenus a partir d'une geometrie simple, ideale, analytique ou experimentale, a la geometrie reelle hexagonale du reacteur. Il compare le rendement nucleaire, y compris la surgeneration, du reacteur reel par rapport a celui du modele theorique. Il decrit la reactivite a long terme et le comportement energetique de la couche fertile du reacteur dans le cadre de l'etude du cyclage propose du combustible et de l'alliage fertile. L'auteur etudie les questions de securite considerant notamment l'introduction de taux de reactivite normaux et anormaux, les consequences des effets supposes de reactivite, a partir du comportement physique de l'alliage combustible et de la structure du reacteur, ainsi que par extrapolation des experiences faites sur TREAT au systeme EBR-II. Il examine le probleme de la fusion du coeur de EBR-II. (author) [Spanish] La memoria informa sobre los calculos del comportamiento estatico, dinamico y a largo plazo de la reactividad del reactor reproductor experimental EBR-II, asi como sobre los resultados y analisis de los experimentos criticos en seco del EBR-II y de los experimentos simulados en el reactor de potencia cero ZPR-III. Insiste particularmente en los problemas de fisica del reactor que, en la elaboracion del proyecto, siguen a la eleccion del modelo, pero preceden a la construccion y puesta en marcha del reactor. Presenta diversos analisis del reactor desde el punto de vista de la seguridad y formula consideraciones sobre la evaluacion de los riesgos y su influencia sobre el diseno del reactor. El trabajo explica tambien la manera de emplear los datos obtenidos en los experimentos arriba citados. Estos experimentos, su analisis y sus predicciones teoricas constituyen la base para determinar el comportamiento fisico del reactor. La memoria estudia detalladamente las limitaciones inherentes a la aplicacion de los datos experimentales al funcionamiento del reactor de potencia. Ello incluye datos precisos sobre as dimensiones del cuerpo, el enriquecimiento de la aleacion combustible, o de ambos factores; el establecimiento de una reactividad adecuada para el reactor funcionando o detenido, la determinacion de la variacion de los coeficientes de reactividad en funcion de la temperatura de funcionamiento y de la potencia generadora y detalles de la distribucion de la potencia y del flujo en diversos puntos de la estructura del reactor. La memoria expone tambien el problema general que supone transferir a la verdadera geometria hexagonal del reactor los datos obtenidos en geometrias simples idealizadas, analiticas o experimentales. Se compara el rendimiento nuclear, incluso el de reproduccion, del reactor real con el del modelo teorico y se describen las variaciones a largo plazo de la reactividad y de la generacion de energia en la envoltura fertil, refiriendolas a los ciclos propuestos para el combustible y la envoltura fertil. La memoria formula consideraciones sobre la seguridad estudiando en particular la introduccion de indices de reactividad normales y anormales y la consecuencia de supuestos efectos de reactividad, que se basan en el comportamiento fisico de la aleacion combustible y de la estructura del reactor, asi como en la extrapolacion al sistema del EBR-II de los experimentos realizados con el conjunto TREAT. Por ultimo, examina el problema de la fusion del cuerpo del reactor EBR-II. (author) [Russian] Vychisleniya statisticheskogo, dinamicheskogo i dlitel'nogo rezhima reaktivnosti ehksperimental'nog o reaktora-razmnozhitel ya EBR-II dayutsya sovmestno s rezul'tatami i analizom ehksperimentov na reaktore EBR-II po dostizheniyu kritichnosti v sukhom sostoyanii i otdel'nykh ehksperimentov na reaktore ZPR-III. Osoboe vnimanie udelyaetsya problemam fizicheskogo rascheta reaktora, kotorye voznikayut posle opredeleniya printsipial'noj skhemy i do sooruzheniya ili vvoda reaktora v ehkspluatatsiyu. Opisyvayutsya analiz bezopasnosti reaktora i soobrazheniya po otsenke opasnostej, a takzheikh vliyanie na raschet reaktora. V doklade opisyvaetsya sposob ispol'zovaniya modeli EBR-II na osnovanii poluchennykh na reaktore ZPR-III dannykh, a takzhe dannykh sukhoj kritichnosti reaktora EBR-II. EHti ehksperimenty, ikh analiz i teoreticheskie vykladki yavlyayutsya osnovoj dlya opredeleniya fizicheskogo povedeniya reaktornoj sistemy. Bolee podrobno issleduyutsya ogranicheniya, prisushchie primeneniyu ehksperimental'nykh dannykh k rassmatrivaemo j ehnergeticheskoj reaktornoj sisteme. Syuda otnosyatsya spetsifikatsiya razmerov aktivnoj zony reaktora i/ili obogashchenie topliva, znacheniya reaktivnosti dlya normal'nogo rezhima raboty i ostanovki reaktora, opredelenie rabochej temperatury i ehnergeticheskikh koehffitsientov reaktivnosti i raspredelenie ehnergii i potoka kak funktsii polozheniya v reaktore. Opisyvaetsya obshchaya problema ehkstrapolyatsii ot prostoj ideal'noj analiticheskoj ili ehksperimental'no j geometrii k fakticheskoj geksagonal'noj geometrii reaktora. YAdernye kharakteristiki, vklyuchaya vosproizvodstvo , fakticheskoj reaktornoj sistemy sravnivayutsya s yadernymi kharakteristikam i ideal'noj printsipial'noj reaktornoj sistemy. Povedenie reaktivnosti v techenie dlitel'nogo vremeni raboty i ehnergeticheskij rezhim zony vosproizvodstva reaktora opisyvayutsya v ramkakh predpolagaemogo toplivnogo tsikla i materiala zony vosproizvodstva. V doklade analiziruyutsya soobrazheniya po bezopasnosti, vklyuchaya normal'nye i anormal'nye skorosti prirosta reaktivnosti, posledstviya ozhidaemykh ehffektov reaktivnosti, osnovannye na fizicheskom povedenii splava topliva i struktury reaktora, a takzhe ehkstrapolyatsiya ehksperimentov, provedennykh na opytnom reaktore dlya izucheniya perekhodnykh protsessov TREAT, na reaktore EBR-II. Izuchaetsya problema rasplavleniya v aktivnoj zone reaktora EBR-II. (author)}
place = {IAEA}
year = {1962}
month = {Mar}
}