FEMAXI-IV: A computer code for the analysis of thermal and mechanical behavior of light water reactor fuel rods-Reference-Cited by-同舟云学术

FEMAXI-IV: A computer code for the analysis of thermal and mechanical behavior of light water reactor fuel rods

Published:1994-06 Issue:1 Volume:148 Page:41-52
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Nakajima T.,Saito H.,Osaka T.

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

Reference16 articles.

1. The effect of irradiation-induced re-solution on fission gas release

2. An analytic model for the prediction of in-pile behavior of oxide fuel rods;Duncombe;Nucl. Technol.,1971

3. A quantitative model for fission gas release and swelling in irradiated uranium dioxide;Hargreaves;J. Br. Nucl. Energy Soc.,1976

4. The International Over-Ramp Project at Studsvik;Hollowell,1982

5. Axial transport of fission gas in LWR fuel rods;Kinosita,1982

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