Critical Power Analysis with Mechanistic Models for Nuclear Fuel Bundles, (I)-Reference-Cited by-同舟云学术

Critical Power Analysis with Mechanistic Models for Nuclear Fuel Bundles, (I)

Published:2002-01 Issue:1 Volume:39 Page:40-52
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

NAITOH Masanori,IKEDA Takashi,NISHIDA Koji,OKAWA Tomio,KATAOKA Isao

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

http://www.tandfonline.com/doi/pdf/10.1080/18811248.2002.9715155

Reference25 articles.

1. Spacer Effects on Film Flow in BWR Fuel Bundle

2. Spacer Effect on Liquid Film Flow and Critical Power in BWR Fuel Bundles

3. Method of Critical Power Prediction Based on Film Flow Model Coupled with Subchannel Analysis

4. Sakai, T., Rummens, H. E. C. and Sugawara, S. “FIDAS: A three-fluid subchannel code for dryout prediction in rod bundles,”. Proc. FIDAS: A three-fluid subchannel code for dryout prediction in rod bundles. June5–81989, Ottawa, Canada.

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