Heat Removable Limit for Nuclear Fuel(<Special Issue>Challenge to Ultimate Cooling Technique Using Phase Change Process)-Reference-Cited by-同舟云学术

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Heat Removable Limit for Nuclear Fuel(Challenge to Ultimate Cooling Technique Using Phase Change Process)

Published:2009 Issue:758 Volume:75 Page:1890-1895
ISSN:0387-5016
Container-title:Transactions of the Japan Society of Mechanical Engineers Series B
language:en
Short-container-title:Trans.JSME, Ser.B

Author:

MOROOKA Shinichi¹,KUDO Yoshiro,HOTTA Akitoshi

Affiliation:

1. Toshiba Corporation

Publisher

Japan Society of Mechanical Engineers

Subject

Mechanical Engineering,Condensed Matter Physics

Link

https://www.jstage.jst.go.jp/article/kikaib1979/75/758/75_KJ00005756328/_pdf

Reference18 articles.

1. 1) LAHEY R. T. The thermal-hydraulics of a Boiling Water Reactor. ANS. (1979) p.91-138.

2. 2) TONG L. T. Thermal Analysis of Pressurized Water Reactors. ANS. (1995) vol.462,

3. 3) AESJ. Standard for Assessment of Fuel Integrity under Anticipated Operational Occurrences in BWR Power Plants : 2003. AESJ-SC-P 002-2003. (2003)

4. 4) Nuclear Safety Commission of Japan. Guideline for Nuclear Safety Commission. Taisei Publishing Co. Ltd.. (1999) vol.159,1314,

5. 5) TONG L. S. Boiling Crisis and Critical Heat Flux. U.S. Atomic Energy Commission. (1972)

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3. Study on pressure drop prediction of BWR fuel assembly using CFD analysis;Transactions of the JSME (in Japanese);2017

4. Study on Critical Power Prediction of Vertical Circular Tube;JAPANESE JOURNAL OF MULTIPHASE FLOW;2014

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