Nuclear fuel rod fragmentation under accidental conditions-Reference-Cited by-同舟云学术

Nuclear fuel rod fragmentation under accidental conditions

Published:2013-02 Issue: Volume:255 Page:68-76
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Coindreau Olivia,Fichot Florian,Fleurot Joëlle

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

Reference44 articles.

1. Akers, D., Carlson, E., Cook, B., Ploger, S., Carlson, J., 1986. TMI-2 core debris grab samples – examination and analysis. Technical Report, Sandia National Laboratory, GEND-INF-075.

2. Data presentation and interpretation;Allen,2003

3. OCDE/NEA-EC/SARNET2 Workshop October 12–14;Amri,2009

4. Validation and application of the WABE code: investigations of constitutive laws and 2D effects on debris coolability;Bürger;Nucl. Eng. Des.,2006

5. Chung, H., Kassner, T., 1980. Embrittlement criteria for Zircaloy fuel cladding applicable to accident situations in light-water reactors: summary report. Technical Report, EGG Idaho, Inc., NUREG/CR-1344-ANL-79-48.

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