Published February 1980 | Version v1
Journal article

On behaviour of fuel elements subject to combined cyclic thermomechanical loads

Creators

  • 1. Manitoba Univ., Winnipeg (Canada). Dept. of Mechanical Engineering

Description

This paper presents detailed finite element formulations on the kinematic hardening rule of plasticity included in an existing thermoelastoplastic stress analysis code primarily designed to predict the thermomechanical behaviour of nuclear reactor fuel elements. The kinematic hardening rule is considered to be important for structures subject to repeated (or cyclic) loads. The start-up/operation/shut-down and various power excursions in a reactor all can be classified as cyclic loadings. In addition to the shifting of material yield surfaces as usually handled by the kinematic hardening rule, the thermal effect and temperature-dependent material properties have also been included in the present work for the first time. A case study related to an in-reactor experiment on a single fuel element indicated that significantly higher cumulative sheath residual strains after two load cycles was obtained by the present scheme than those calculated by the usual isotropic hardening rule. This observation may alert fuel modellers to select proper hardening rules in their analyses. (orig.)

Additional details

Publishing Information

Journal Title
Nucl. Eng. Des.
Journal Volume
56
Journal Issue
1
Series
Nucl. Eng. Des.
Journal Page Range
279-287
ISSN
0029-5493

Conference

Title
IAEA specialists' meeting on fuel element performance computer modelling.
Dates
13 - 17 Mar 1978.
Place
Blackpool, UK.

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
11531979
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FINITE ELEMENT METHOD; FUEL ELEMENT FAILURE; FUEL ELEMENTS; HARDENING; PLASTICITY; STRESS ANALYSIS; THERMAL CYCLING
Descriptors DEC
ACCIDENTS; MECHANICAL PROPERTIES; NUMERICAL SOLUTION; REACTOR ACCIDENTS; REACTOR COMPONENTS