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Study of the {rho}-bar, {beta}-bar and {lambda} parameters of a light-water reactor; Etude des parametres {rho}-bar, {beta}-bar et {lambda} d'une pile a eau legere

Abstract

The kinetic and perturbation equations are derived from the time-dependent transport equation. Kinetic equations depend only on the ratios a = {rho}-bar/{beta}-bar and b = {beta}-bar/{lambda}, which are definite, while the reactivity {rho}-bar, the delayed neutron fraction ({beta}-bar and the generation time {lambda} are expressed in terms of an arbitrary function I. The 'static' definitions of these parameters, which reduce kinetic problems to a set of purely term dependent equations, introduce the effective fraction {beta}-bar. One way of determining experimentally the ratio b is presented; it consists in analysing the power transient after a rapid variation of the reactivity, caused by the implosion of an empty glass-bull. A simple interpretation is proposed. The apparatus can be transformed easily into a reactimeter. The value of the effective delayed neutron fraction {beta}-bar has been determined by averaging the reactivity effects of a copper sheet through out the reactor core. Experimental results: b = {beta}-bar/{lambda} = 129 s{sup -1} and {beta}-bar 795.10{sup -5}, have been determined on a light-water moderated, enriched-uranium fuelled reactor. The calculated values of the effectiveness of delayed neutrons {gamma} {beta}-bar/{beta} 1.23 and the generation time {lambda} 59.10{sup -6}s agrees fairly well with the experimental results. (author) [French] Les equations  More>>
Authors:
Riche, R [1] 
  1. Commissariat a l'Energie Atomique, Grenoble (France). Centre d'Etudes Nucleaires
Publication Date:
Sep 01, 1965
Product Type:
Thesis/Dissertation
Report Number:
CEA-R-2883
Resource Relation:
Other Information: TH: These sciences; 48 refs
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ACCURACY; BOLTZMANN EQUATION; CROSS SECTIONS; DELAYED NEUTRON FRACTION; ENRICHED URANIUM; IMPLOSIONS; KINETIC EQUATIONS; REACTOR CORES; WATER MODERATED REACTORS
OSTI ID:
20680288
Research Organizations:
CEA Grenoble, 38 (France); Faculte des Sciences de l'Universite de Grenoble, 38 (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
TRN: FR05R2883115178
Availability:
Available from INIS in electronic form
Submitting Site:
FRN
Size:
92 pages
Announcement Date:
Jan 09, 2006

Citation Formats

Riche, R. Study of the {rho}-bar, {beta}-bar and {lambda} parameters of a light-water reactor; Etude des parametres {rho}-bar, {beta}-bar et {lambda} d'une pile a eau legere. France: N. p., 1965. Web.
Riche, R. Study of the {rho}-bar, {beta}-bar and {lambda} parameters of a light-water reactor; Etude des parametres {rho}-bar, {beta}-bar et {lambda} d'une pile a eau legere. France.
Riche, R. 1965. "Study of the {rho}-bar, {beta}-bar and {lambda} parameters of a light-water reactor; Etude des parametres {rho}-bar, {beta}-bar et {lambda} d'une pile a eau legere." France.
@misc{etde_20680288,
title = {Study of the {rho}-bar, {beta}-bar and {lambda} parameters of a light-water reactor; Etude des parametres {rho}-bar, {beta}-bar et {lambda} d'une pile a eau legere}
author = {Riche, R}
abstractNote = {The kinetic and perturbation equations are derived from the time-dependent transport equation. Kinetic equations depend only on the ratios a = {rho}-bar/{beta}-bar and b = {beta}-bar/{lambda}, which are definite, while the reactivity {rho}-bar, the delayed neutron fraction ({beta}-bar and the generation time {lambda} are expressed in terms of an arbitrary function I. The 'static' definitions of these parameters, which reduce kinetic problems to a set of purely term dependent equations, introduce the effective fraction {beta}-bar. One way of determining experimentally the ratio b is presented; it consists in analysing the power transient after a rapid variation of the reactivity, caused by the implosion of an empty glass-bull. A simple interpretation is proposed. The apparatus can be transformed easily into a reactimeter. The value of the effective delayed neutron fraction {beta}-bar has been determined by averaging the reactivity effects of a copper sheet through out the reactor core. Experimental results: b = {beta}-bar/{lambda} = 129 s{sup -1} and {beta}-bar 795.10{sup -5}, have been determined on a light-water moderated, enriched-uranium fuelled reactor. The calculated values of the effectiveness of delayed neutrons {gamma} {beta}-bar/{beta} 1.23 and the generation time {lambda} 59.10{sup -6}s agrees fairly well with the experimental results. (author) [French] Les equations de la cinetique et de la perturbation sont deduites de la theorie du transport, par l'intermediaire de la 'notion' d'importance des neutrons. La cinetique ne depend que des rapports a = {rho}-bar/{beta}-bar et b = {beta}-bar/{lambda}, qui sont parfaitement definis; par contre, la reactivite {rho}-bar, la proportion de neutrons retardes {beta}-bar et le temps de generation des neutrons prompts {lambda} s'expriment a l'aide d'une meme fonction arbitraire I. Les definitions 'statiques' de ces parametres, qui permettent de rendre compte de la cinetique par des equations dependant purement du temps, font apparaitre la valeur effective {beta}-bar. A partir de la cinetique, nous determinons le rapport b par analyse de transitoire de puissance consecutif a l'injection d'une variation rapide de reactivite realisee par l'implosion d'une boule de verre vide. Un depouillement relativement simple est propose. L'appareillage est reduit et se transforme aisement en reactimetre. De la theorie de la perturbation, nous deduisons une mesure de {beta}-bar, qui consiste a ponderer les effets en reactivite d'une feuille de cuivre, mesures en differents emplacements du coeur. Les valeurs calculees de l'efficacite des neutrons retardes {gamma} = {beta}-bar/{beta} 1.23 et du temps de generation des neutrons prompts {lambda} = 59 {mu}s sont en bon accord avec les resultats experimentaux: {beta}-bar = 795 pcm et {beta}-bar/{lambda} 129 s{sup -1}, les nombres precites etant relatifs a un reacteur a eau legere et a uranium enrichi (90 pour cent U-235), le coeur presentant des trous d'eau. (auteur)}
place = {France}
year = {1965}
month = {Sep}
}