Whole-core damage analysis of EBR-II driver fuel elements following SHRT program-Reference-Cited by-同舟云学术

Whole-core damage analysis of EBR-II driver fuel elements following SHRT program

Published:1987-04 Issue:1 Volume:101 Page:67-74
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Chang L.K.,Koenig J.F.,Porter D.L.

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

Reference14 articles.

1. Decay heat removal and natural convection testing at EBR-II;Singer,1985

2. The EBR-II shutdown heat removal testing program: Results and plans;Planchon;Am. Nucl. Soc. Trans.,1985

3. Evolution of thermal-hydraulics testing in EBR-II;Golden;Nucl. Engrg. Des.,1987

4. Evaluation of EBR-II driver fuel elements following an unprotected station blackout accident;Chang,1986

5. Safety analysis for the loss-of-flow and loss-of-heat-sink without scram tests in EBR-II;Lehto;Nucl. Engrg. Des.,1987

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