Published December 1987 | Version v1
Report Open

Study of thermic numeric modelization for an outside reactor nuclear assembly

Creators

Description

A spent fuel assembly emits a residual power which is principally the result of the radioactive decay of fission products. It is necessary to know the evolution of the temperature in the spent fuel in order to prevent for an excessive overheating in the fuel during all the operations after unloading. To response at this objective we have realized a numeric program modelling the thermic of spent fuel assembly, outside nuclear reactor, in gaseous environment. The originality of this computer code COBRA is to purpose a simplified formulation for the calcul of exchanges by thermal radiation

Abstract (French)

Lorsqu'un element combustible est decharge d'un reacteur nucleaire, il degage une puissance residuelle qui resulte essentiellement de la decroissance radioactive des produits de fission accumules dans le materiau fissile au cours de son irradiation dans le coeur. Il est indispensable de connaitre l'evolution des temperatures au sein de l'element combustible en dehors du reacteur, afin de prevenir un echauffement excessif dans l'element pendant toutes les etapes qui suivent le dechargement (stockage, transport, manutention, demantelement en usine de retraitement). C'est pour repondre a cet objectif que nous avons realise un programme de calcul numerique COBRA modelisant la thermique d'un assemblage de combustible nucleaire en dehors du coeur du reacteur, sous ambiance gazeuse. L'originalite de ce code est de proposer une formulation simplifiee du calcul des echanges par rayonnement thermique dans un reseau d'aiguilles enferme dans un etui

Files

19051130.pdf

Files (1.2 MB)

Name Size Download all
md5:1da2c6fbfb2cc5c0c2a78d8757acd791
1.2 MB Preview Download

Additional details

Additional titles

Original title (French)
Etude de la modelisation numerique de la thermique d'un assemblage de combustible nucleaire en dehors du reacteur

Publishing Information

Imprint Pagination
126 p.
Report number
FRCEA-TH--58

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
19051130
Subject category
S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Thesis
Descriptors DEI
C CODES; FUEL ASSEMBLIES; GAS COOLING; LMFBR TYPE REACTORS; PWR TYPE REACTORS; SIMULATION; SPENT FUEL ELEMENTS; THERMAL RADIATION
Descriptors DEC
BREEDER REACTORS; COMPUTER CODES; COOLING; ELECTROMAGNETIC RADIATION; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; POWER REACTORS; RADIATIONS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS