Published 1977 | Version v1
Report Open

Proceedings of a specialist meeting on the behaviour of water reactor fuel elements under accident conditions

Creators

Description

The contributions of this meeting report experimental, numerical and research investigations on the oxidation behaviour of zircaloy in case of a loss-of-coolant accident (LOCA), analysis of the kinetics of the oxidation rate, very high temperature behaviour of fuel rod claddings (failure mechanics, ballooning), the interaction between cladding and fuel, the mechanical behaviour of zircaloy, etc. Numerous experimental and computer code analysis results are given

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Additional details

Publishing Information

Imprint Pagination
774 p.
Report number
NEA-CSNI-R--1977-13

Conference

Title
Specialist meeting on the behaviour of water reactor fuel elements under accident conditions
Dates
13-16 Sep 1976
Place
Spaatind (Norway)

INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
Nuclear Energy Agency of the OECD (NEA)
INIS RN
42006191
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
Resource subtype / Literary indicator
Conference
Is Lead record
Yes
Descriptors DEI
CLADDING; COMPARATIVE EVALUATIONS; COMPUTER CODES; DEFORMATION; FUEL ELEMENT FAILURE; FUEL RODS; FUEL-CLADDING INTERACTIONS; LEADING ABSTRACT; NEA; OXIDATION; REACTOR ACCIDENT SIMULATION; REACTOR ACCIDENTS; REACTOR SAFETY; SENSITIVITY ANALYSIS; SYSTEM FAILURE ANALYSIS; TEMPERATURE DISTRIBUTION; TRANSIENTS; WATER COOLED REACTORS; ZIRCALOY
Descriptors DEC
ABSTRACTS; ACCIDENTS; ALLOYS; CHEMICAL REACTIONS; DEPOSITION; EVALUATION; FAILURES; FUEL ELEMENTS; INTERNATIONAL ORGANIZATIONS; OECD; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; SURFACE COATING; SYSTEMS ANALYSIS; TRANSITION ELEMENT ALLOYS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS