Models for reactor fuel elements which consider void deployment-Reference-Cited by-同舟云学术

Models for reactor fuel elements which consider void deployment

Published:1969-01 Issue:1 Volume:9 Page:15-28
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Merckx K.R.

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

Reference29 articles.

1. FIGRO-Fortran IV digital computer program for the analysis of fuel swelling and calculation of temperature in bulk-oxide cylindrical fuel elements;Goldberg;WAPD-TM-618,1968

2. The longitudinal and diametral expansions of UO2 fuel elements;Notley;AECL-2143,1964

3. A failure analysis for the low temperature performance of dispersion fuel elements;Weir;ORNL-2902,1960

4. Mechanical models for tubular reactor fuel elements;Merckx;Trans. ASME,1962

5. A program for calculating the steady state deformation rates for cylindrical fuel elements;Merckx;BNWL-663,1968

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