Published August 1969 | Version v1
Report Open

Experiments of progressive replacement in Cesar at operation temperature. Uranium-plutonium fuels. Study performed within the frame of the CEA-EURATOM - No. 002 64 9 TRUF contract - 'Plutonium recycling'

Creators

  • 1. Commissariat a l'Energie Atomique - CEA (France)
  • 2. Electricite de France - EDF (France)

Description

Experiments of progressive replacement (or substitution) of uranium-plutonium alloy fuels are part of a general program of experimental studies which are aimed at testing the methods used by the CEA to calculate the evolution of nuclear power reactors (calculation of spectrum in plutonium-containing fuels and validity of data used in these calculations, calculation of cross sections). Such progressive replacements have been performed in Aquilon (with heavy water as moderator) and measurements have been performed by oscillation in Marius and Cesar (graphite moderator). Herein reported experiments have been performed at 20, 100 and 200 C during a first campaign in 1966, and at 300, 400 and 450 C during a second campaign in 1968. Measurements are interpreted by means of the Coregraf 2 code. The report presents experimental conditions in Cesar, the measurement principle and the interpretation method (substitution experiments, enriched uranium calibration, interpretation steps, and temperature coefficient measurement), the obtained results and their discussion

Abstract (French)

Les experiences de remplacement progressif (ou substitution) de combustibles d'alliage uranium-plutonium s'inscrivent dans le programme general d'etudes experimentales destinees a tester les methodes employees au C.E.A. pour le calcul de l'evolution des reacteurs de puissance. En ce qui concerne l'etude des combustibles d'alliage uranium-plutonium, des mesures de remplacement progressif ont ete effectuees dans AQUILON (moderateur eau lourde) et des mesures par oscillation dans MARIUS et CESAR (moderateur graphite). Les experiences, dont l'interpretation fait l'objet du present rapport, ont ete effectuees en 1966 a 20 deg., 100 deg. et 200 deg. et en 1968 a 300 deg., 400 deg., 450 deg. C, Rappelons que les premieres etudes relatives a ces experiences ont fait l'objet d'une partie du premier contrat CEA-EURATOM sur le sujet 'Recyclage du Plutonium' (Rapport final EUR 2853 1966). La presente etude a ete effectuee dans le cadre du contrat CEA-EURATOM No. 002 64 9 TRUF, 'Recyclage du plutonium'. Les experiences qui font l'objet du present rapport sont les suivantes: 1) Mesures de remplacement progressif a 100 deg., 200 deg., 300 deg., 450 deg. C pour les jeux 1 P, 2 P, 3 P et a 400 deg. C pour 2 P. 2) Mesure du coefficient de temperature differentiel pour le jeu 2 P a 20 deg., 100 deg., 200 deg., 300 deg., 400 deg. C. L'interpretation de ces experiences a ete faite avec le code COREGRAF 2 (calcul de reseaux moderes au graphite, utilisant en sous-programme le code DEP 35 pour le calcul du spectre) dont la principale modification dans le domaine thermique par rapport au formulaire precedent COREGRAF 1 est le choix de la bibliotheque UKAEA 1967 pour la variation des sections efficaces en fonction de l'energie. (auteurs)

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Additional details

Additional titles

Original title (French)
Experiences de remplacement progressif dans CESAR en temperature combustibles uranium-plutonium. Etude effectuee dans le cadre du contrat CEA-EURATOM - No. 002 64 9 TRUF - 'Recyclage du plutonium'

Identifiers

URL
http://www.iaea.org/inis/Contacts/;

Publishing Information

Imprint Pagination
50 p.
Report number
CEA-N--1173

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
46058069
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ALLOY NUCLEAR FUELS; AQUILON REACTOR; CEA; CESAR REACTOR; FUEL CYCLE; FUEL SUBSTITUTION; MARIUS REACTOR; PILE REPLACEMENT TECHNIQUES; PLUTONIUM; TEMPERATURE COEFFICIENT; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 0273-0400 K; TEMPERATURE RANGE 0400-1000 K; URANIUM; VALIDATION
Descriptors DEC
ACTINIDES; CARBON DIOXIDE COOLED REACTORS; ELEMENTS; ENERGY SOURCES; EXPERIMENTAL REACTORS; FRENCH ORGANIZATIONS; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MATERIALS; METALS; NATIONAL ORGANIZATIONS; NATURAL URANIUM REACTORS; NUCLEAR FUELS; REACTIVITY COEFFICIENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID FUELS; TANK TYPE REACTORS; TEMPERATURE RANGE; TESTING; THERMAL REACTORS; TRANSURANIUM ELEMENTS; ZERO POWER REACTORS

Optional Information

Notes
3 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/inis/Contacts/