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Experimental Determination of the Neutron Characteristics of UO{sub 2}-PuO{sub 2}-H{sub 2}O Lattices; Determination Experimentale Des Caracteristiques Neutroniques De Reseaux UO{sub 2}-PuO{sub 2}-H{sub 2}O

Conference:

Abstract

As part of the investigation, in the VENUS test facility, of the variably moderated core of the BR3/VULCAIN reactor, a fuel assembly consisting of 37 UO{sub 2}-PuO{sub 2} pins (94% natural UO{sub 2}, 6% PuO{sub 2} ) was substituted for one of the enriched (to 7% {sup 235}U) UO{sub 2} fuel assemblies constituting the reactor core. Experiments were carried out with the object of refining the mathematical models for calculating the performance of this special assembly; inter alia, the fission density distribution and the changing ratio of the effective cross-sections for fission in the {sup 233}Pu and {sup 235}U were measured. Using the same critical facility, the authors are carrying out a critical experiment related directly to the problems of plutonium recycling in pressurized light-water thermal reactors. Three types of fuel are being used: UO{sub 2}-PuO{sub 2} with 3% {sup 235}U and 1% fissile plutonium, UO{sub 2}-PuO{sub 2} with 2% {sup 235}U and 2% fissile plutonium, and UO{sub 2} with 4% {sup 235}U. The two UO{sub 2}-PuO{sub 2} mixtures have completely different isotopic contents of {sup 240}Pu: 7% and 17%. In the first part of the experimental programme, a study is being made of regular lattices in cores having two  More>>
Authors:
Debrue, J.; Fabry, A.; Leenders, L.; Motte, F.; Van Den Broeck, H. [1] 
  1. Centre d'Etude de l'Energie Nucleaire, Mol (Belgium)
Publication Date:
Sep 15, 1967
Product Type:
Conference
Report Number:
IAEA-SM-88/50
Resource Relation:
Conference: Symposium on the Use of Plutonium as a Reactor Fuel, Brussels (Belgium), 13-17 Mar 1967; Other Information: 30 refs., 8 figs., 5 tabs.; Related Information: In: Plutonium as a Reactor Fuel. Proceedings of a Symposium on the Use of Plutonium as a Reactor Fuel| 876 p.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; BR-3 REACTOR; CHOOZ-A REACTOR; ENERGY SPECTRA; FISSION; FISSION PRODUCTS; FUEL ASSEMBLIES; NEUTRON SOURCES; NEUTRON SPECTRA; NEUTRONS; NUCLEAR FUELS; PLUTONIUM; PLUTONIUM 233; PLUTONIUM 240; PLUTONIUM OXIDES; REACTOR CORES; URANIUM 235; URANIUM DIOXIDE; WATER
OSTI ID:
22117119
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
French
Contract Number:
Contract 001-64-1 TRUB
Other Identifying Numbers:
Other: ISSN 0074-1884; TRN: XA13M1351073740
Submitting Site:
INIS
Size:
page(s) 85-107
Announcement Date:
Aug 01, 2013

Conference:

Citation Formats

Debrue, J., Fabry, A., Leenders, L., Motte, F., and Van Den Broeck, H. Experimental Determination of the Neutron Characteristics of UO{sub 2}-PuO{sub 2}-H{sub 2}O Lattices; Determination Experimentale Des Caracteristiques Neutroniques De Reseaux UO{sub 2}-PuO{sub 2}-H{sub 2}O. IAEA: N. p., 1967. Web.
Debrue, J., Fabry, A., Leenders, L., Motte, F., & Van Den Broeck, H. Experimental Determination of the Neutron Characteristics of UO{sub 2}-PuO{sub 2}-H{sub 2}O Lattices; Determination Experimentale Des Caracteristiques Neutroniques De Reseaux UO{sub 2}-PuO{sub 2}-H{sub 2}O. IAEA.
Debrue, J., Fabry, A., Leenders, L., Motte, F., and Van Den Broeck, H. 1967. "Experimental Determination of the Neutron Characteristics of UO{sub 2}-PuO{sub 2}-H{sub 2}O Lattices; Determination Experimentale Des Caracteristiques Neutroniques De Reseaux UO{sub 2}-PuO{sub 2}-H{sub 2}O." IAEA.
@misc{etde_22117119,
title = {Experimental Determination of the Neutron Characteristics of UO{sub 2}-PuO{sub 2}-H{sub 2}O Lattices; Determination Experimentale Des Caracteristiques Neutroniques De Reseaux UO{sub 2}-PuO{sub 2}-H{sub 2}O}
author = {Debrue, J., Fabry, A., Leenders, L., Motte, F., and Van Den Broeck, H.}
abstractNote = {As part of the investigation, in the VENUS test facility, of the variably moderated core of the BR3/VULCAIN reactor, a fuel assembly consisting of 37 UO{sub 2}-PuO{sub 2} pins (94% natural UO{sub 2}, 6% PuO{sub 2} ) was substituted for one of the enriched (to 7% {sup 235}U) UO{sub 2} fuel assemblies constituting the reactor core. Experiments were carried out with the object of refining the mathematical models for calculating the performance of this special assembly; inter alia, the fission density distribution and the changing ratio of the effective cross-sections for fission in the {sup 233}Pu and {sup 235}U were measured. Using the same critical facility, the authors are carrying out a critical experiment related directly to the problems of plutonium recycling in pressurized light-water thermal reactors. Three types of fuel are being used: UO{sub 2}-PuO{sub 2} with 3% {sup 235}U and 1% fissile plutonium, UO{sub 2}-PuO{sub 2} with 2% {sup 235}U and 2% fissile plutonium, and UO{sub 2} with 4% {sup 235}U. The two UO{sub 2}-PuO{sub 2} mixtures have completely different isotopic contents of {sup 240}Pu: 7% and 17%. In the first part of the experimental programme, a study is being made of regular lattices in cores having two co-axial cylindrical zones: a UO{sub 2}-PuO{sub 2} zone and a UO{sub 2} zone. Particular attention is being paid to investigating the region on either side of the interface separating the two zones, where the neutron spectrum reflects the characteristic energy distributions in each of the two lattices. The experimental results are to be used in calibrating the computational methods. In the second part of the experimental programme, parts of the core of the SENA power reactor will be simulated with a view to studying the problems of reloading one third of the core with mixed UO{sub 2}-PuO{sub 2} fuel. Among the experimental techniques employed in these various experiments emphasis is given to those most specifically related to the presence of plutonium: fission density measurements by direct counting of the fission products formed in the mixed fuel as a result of irradiation, and measurements of spectral indices by means of fission detectors and detectors having resonances close to those of the isotopes of plutonium. The optimum conditions for applying these techniques are described and the effect on the fuel cycle of uncertainties in the values for the spectral indices (ratios of cross-sections) is discussed. A brief reference is finally made to a programme of sub-critical experiments conducted hitherto with two batches of UO{sub 2} fuel enriched to 5% and 7% {sup 235}U, and having the purpose of studying possible methods of exciting a sub-critical lattice by means of an external neutron source in pulsed and modulated operation. The aim of this programme is to ascertain to what extent these methods, which employ a quantity of fuel considerably less than the critical mass, can help in determining the characteristics of a lattice. The advantages of such methods are particularly obvious in the case of plutonium fuels. (author) [French] Au cours de l'etude dans l'installation critique VENUS du coeur a moderation variable du reacteur BR3/VULCAIN, un assemblage combustible constitue de 37 crayons UO{sub 2}-PuO{sub 2} (94% UO{sub 2} naturel, PuO{sub 2}) a ete substitue a un des assemblages combustibles UO{sub 2} enrichi a 7% {sup 235}U constituant le coeur de ce reacteur. Des experiences ont ete effectuees dans le but de permettre l'ajustement des modeles du calcul des performances de cet assemblage special: on a notamment mesure la distribution de la densite de fission ainsi que l'evolution du rapport des sections efficaces effectives de fission dans {sup 239}Pu et {sup 235}U. Une experience critique directement orientee sur les problemes de recyclage du plutonium dans les reacteurs thermiques a eau legere pressurisee est en cours d'execution dans la meme installation critique. A cette fin, on dispose de deux combustibles mixtes UO{sub 2}-PuO{sub 2} enrichis respectivement a 3% {sup 235}U- 1% Pu fissile et 2% {sup 235}U-2% Pu fissile, et d'un combustible UO{sub 2} enrichi a 4% {sup 235}U; les teneurs isotopiques en {sup 240}Pu des deux combustibles mixtes sont en outre nettement differentes, respectivement 7 et 17%. Dans une premiere partie du programme, on etudie des reseaux reguliers dans des coeurs a deux zones cylindriques coaxiales, une zone UO{sub 2}-PuO{sub 2} et une zone UO{sub 2} ; on s'attache particulierement a explorer, de part et d'autre de la frontiere commune a ces deux zones, la region de transition dans laquelle le spectre neutronique evolue entre les distributions energetiques caracteristiques de chacun des deux reseaux. Les resultats experimentaux sont destines a l'etalonnage des methodes de calcul. Dans une seconde partie du programme, on simulera des portions du coeur du reacteur de la centrale SENA afin d'etudier les problemes particuliers au rechargement d'un tiers de ce coeur par du combustible mixte UO{sub 2}-PuO{sub 2}. Parmi les techniques experimentales mises en oeuvre a l'occasion de ces differentes experiences, on met en evidence celles qui sont les plus specifiques de la presence du plutonium: mesure de la densite de fission par comptage direct des produits de fission formes par irradiation dans le combustible mixte, mesure d'indices de spectre au moyen de detecteurs fissiles et de detecteurs presentant des resonances voisines de celles des isotopes du plutonium. Les conditions optimales d'application de ces techniques sont presentees; l'incidence des incertitudes affectant les resultats experimentaux des indices de spectre (rapports de sections efficaces) sur le cycle du combustible est discutee. Enfin, on presente brievement un programme d'essais sous-critiques conduit jusqu'a present sur deux lots de crayons combustibles UO{sub 2} enrichi a 5 et 1% {sup 235}U, dans le but d'etudier les possibilites des methodes consistant a exciter un reseau sous-critique au moyen d'une source extrinseque de neutrons en regimes puise et module. L'objectif de ce programme est d'apprecier dans quelle mesure ces methodes, qui mettent en oeuvre une quantite de combustible sensiblement' inferieure a la masse critique, peuvent contribuer a la determination des caracteristiques d'un reseau: dans le cas des combustibles plutoniferes, l'interet de telles methodes serait particulierement evident. (author)}
place = {IAEA}
year = {1967}
month = {Sep}
}