Published 2007 | Version v1
Miscellaneous Metadata-only

A thermomechanical model of CANDU fuel

Creators

Description

A fundamental code for predicting CANDU nuclear fuel thermomechanical behaviour in normal operating conditions was developed with the use of the Comsol Multiphysics finite element modelling environment. The code predicts the thermal response of the fuel, fuel thermal expansion, irradiation-induced densification, fission product swelling, fission gas release, and elastic and plastic deformation of the fuel and cladding. The evolution of the fuel-to-clad gap was predicted using the overall deformation of the fuel and sheath. The code was able to predict the behaviour of fuel under normal operating conditions and has been benchmarked against the industry-standard ELESTRES-IST fuel performance code. (author)

Availability note (English)

Available from University Microfilms International-UMI, 300 North Zeeb Road, PO Box 1346, Ann Arbor, Michigan (United States), under document no. MR29824.

Additional details

Publishing Information

ISBN
978-0-494-29824-4
Imprint Pagination
191 p.

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
41038394
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Thesis, Non-conventional Literature
Descriptors DEI
CANDU TYPE REACTORS; CHEMICAL ANALYSIS; FINITE ELEMENT METHOD; FUEL CANS; NUCLEAR FUELS; THERMAL ANALYSIS
Descriptors DEC
CALCULATION METHODS; ENERGY SOURCES; FUELS; HEAVY WATER MODERATED REACTORS; MATERIALS; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS