Partial flow blockage analysis of the hottest fuel assembly in SNCLFR-100 reactor core-Reference-Cited by-同舟云学术

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Partial flow blockage analysis of the hottest fuel assembly in SNCLFR-100 reactor core

Published:2018-01 Issue:1 Volume:29 Page:
ISSN:1001-8042
Container-title:Nuclear Science and Techniques
language:en
Short-container-title:NUCL SCI TECH

Author:

Shi Kang-Li,Li Shu-Zhou,Zhang Xi-Lin,Zhao Peng-Cheng,Chen Hong-Li

Publisher

Springer Science and Business Media LLC

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

http://link.springer.com/article/10.1007/s41365-017-0351-3/fulltext.html

Reference20 articles.

1. H.W. Bertini, Descriptions of selected accidents that have occurred at nuclear reactor facilities. Tennessee, USA, ORNL/NSIC-176, 1980

2. I. Di Piazza, F. Magugliani, M. Tarantino et al., A CFD analysis of flow blockage phenomena in ALFRED LFR demo fuel assembly. Nucl. Eng. Des. 276, 202–215 (2014). https://doi.org/10.1016/j.nucengdes.2014.05.033

3. Q. Lu, S. Qiu, G.H. Su, Flow blockage analysis of a channel in a typical material test reactor core. Nucl. Eng. Des. 239(1), 45–50 (2009). https://doi.org/10.1016/j.nucengdes.2008.06.016

4. H.M. Son, S.H. Yang, C. Park et al., Transient thermal–hydraulic analysis of complete single channel blockage accident of generic 10 MW research reactor. Ann. Nucl. Energy 75, 44–53 (2015). https://doi.org/10.1016/j.anucene.2014.08.002

5. S.U.D. Khan, S.U.D. Khan, M. Peng, Flow blockage accident or loss of flow accident by using comparative approach of NK/TH coupling codes and RELAP5 code. Ann. Nucl. Energy 64, 311–319 (2014). https://doi.org/10.1016/j.anucene.2013.10.010

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