Published December 1990 | Version v1
Journal article Metadata-only

A study of fuel behavior in PWR design basis accident: An analysis of results from the PHEBUS and EDGAR experiments

Creators

  • 1. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France). Dept. d'Etudes et de Recherches en Securite

Description

As part of the French PWR safety study programme, fuel behavior during a design basis accident has been investigated in three parallel directions: Separate effect tests in the EDGAR apparatus for developing and validating cladding deformation models, integral tests in PHEBUS for verifying codes, development of fuel behavior codes for plant calculation after assessment against experimental results. After describing the objectives and content of each of these programmes, the main findings are highlighted and discussed. (orig.)

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
124
Journal Issue
3
Series
Nucl. Eng. Des.
Journal Page Range
363-378
ISSN
0029-5493
CODEN
NEDEA

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
22034912
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
CREEP; DEFORMATION; DESIGN BASIS ACCIDENTS; ECCS; FLOWSHEETS; FUEL CANS; LOSS OF COOLANT; P CODES; PWR TYPE REACTORS; REWETTING; RUPTURES; TEMPERATURE GRADIENTS; TEST FACILITIES; VERIFICATION
Descriptors DEC
ACCIDENTS; COMPUTER CODES; DIAGRAMS; ENRICHED URANIUM REACTORS; FAILURES; INFORMATION; MECHANICAL PROPERTIES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS