Published November 1965 | Version v1
Report Open

Calculation of the heat flow peak in case of local defect of the fuel plate of a nuclear reactor

Creators

Description

The author reports the calculation of the local thermal flow which exits a fuel plate in a nuclear reactor, where a fabrication defect creates a much localized peak of the power density released in the plate. He first reports the development of the problem equations: hypotheses and data, equation elaboration, simplification and resolution. He presents the results of a numeric application to actual cases, and describes how the conduction in the sheath is taken into account (study of the influence of peak width and shape), and gives a synthetic presentation of the formula for the approximate calculation of the heat flow in case of local defect

Abstract (French)

On calcule le pic de flux thermique local qui sort d'une plaque combustible de reacteur, dans le cas ou un defaut de fabrication cree un pic tres local de la puissance volumique degagee dans la plaque. La conduction thermique laterale dans la plaque tend a ecraser le pic de flux d'autant plus que le defaut est peu etendu (soit 2R sa longueur), que l'epaisseur (soit 2e) de la 'viande' est grande, que la conductivite thermique de la 'viande' (soit λ) est elevee et que le coefficient de convection (soit h) est petit. Le parametre qui intervient est y = R/e √(he/λ); p21our y = 1, l'affaiblissement (rapport de l'ecart relatif maximal de flux sur l'ecart relatif maximal de puissance volumique) est de l'ordre de 0,40. C'est cet ordre de grandeur qui concernerait le cas pratique des plaques en alliage d'aluminium. (auteur)

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Additional details

Additional titles

Original title (French)
Calcul du pic de flux calorifique en cas de defaut local de la plaque combustible d'un reacteur nucleaire

Identifiers

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

Publishing Information

Imprint Pagination
13 p.
Report number
CEA-N--1143

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
46034819
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
CALCULATION METHODS; CEA GRENOBLE; DEFECTS; FUEL CANS; FUEL PLATES; HEAT FLUX; HEAT TRANSFER; HOT SPOTS; POWER DENSITY; REACTORS
Descriptors DEC
CEA; ENERGY TRANSFER; FRENCH ORGANIZATIONS; FUEL ELEMENTS; NATIONAL ORGANIZATIONS; REACTOR COMPONENTS

Optional Information

Notes
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/
Secondary number(s)
TT--209-SF-24