Void Fraction Distribution in A Boiling Water Reactor Fuel Assembly and the Evaluation of Subchannel Analysis Codes-Reference-Cited by-同舟云学术

Void Fraction Distribution in A Boiling Water Reactor Fuel Assembly and the Evaluation of Subchannel Analysis Codes

Published:1995-12 Issue:3 Volume:112 Page:388-400
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Inoue Akira¹,Futakuchi Masanobu²,Yagi Makoto²,Mitsutake Toru³,Morooka Shin-Ichi³

Affiliation:

1. Tokyo Institute of Technology, 2-12-1 Oh-okayama Meguro-ku, Tokyo 152, Japan

2. Nuclear Power Engineering Corporation, 4-3-13 Toranomon Minato-ku, Tokyo 105, Japan

3. Toshiba Corporation, Nuclear Engineering Laboratory 8, Shinsugita, Isogo-ku, Yokohama 235, Japan

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT95-A35165

Reference3 articles.

1. Subchannel analysis of a critical power test, using simulated BWR S × S fuel assembly

2. J. E. KELLY, S. P. KAO, and M. KAZIMI, “THERMIT-2; A Two-Fluid Model for Light Water Reactor Subchannel Transient Analysis,” MIT-EL-81-014, Massachusetts Institute of Technology (1981).

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