A model for predicting pellet-cladding interaction-induced fuel rod failure-Reference-Cited by-同舟云学术

A model for predicting pellet-cladding interaction-induced fuel rod failure

Published:1995-06 Issue:3 Volume:156 Page:393-399
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Jernkvist Lars Olof

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference13 articles.

1. Iodine-induced stress corrosion of zircaloy fuel cladding: initiation and growth;Brunisholz;ASTM STP 939,1987

2. Recent studies of crack initiation during stress corrosion cracking of zirconium alloys;Cox;ASTM STP 939,1987

3. Fission gas release under time varying conditions;Forsberg;J. Nucl. Mater.,1985

4. Cesium and iodine release (CESIOD), MAT-PRO version 11; a handbook of materials properties for use in the analysis of light water reactor fuel rod behaviour;Hagrman;NUREG Rep. CR-0497,1981

5. Analysis of pellet-cladding mechanical interaction behavior of different ABB Atom fuel rod designs;Massih,1993

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