Development of a Three-Dimensional Transient Code for Reactivity-Initiated Events in Boiling Water Reactors— Models and Code Verifications-Reference-Cited by-同舟云学术

Development of a Three-Dimensional Transient Code for Reactivity-Initiated Events in Boiling Water Reactors— Models and Code Verifications

Published:1989-12-02 Issue:1 Volume:88 Page:87-97
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Uematsu Hitoshi¹,Izutsu Sadayuki²,Yamamoto Toru³,Yamashita Ryutaro⁴,Muto Sakae⁵,Toba Akio⁵

Affiliation:

1. Nippon Atomic Industry Group Company, Ltd. NAIG Nuclear Research Laboratory, 4-1 Ukishima-cho Kawasaki-ku, Kawasaki 210, Japan

2. Hitachi, Ltd., Hitachi Works 3-1 Saiwai-cho, Hitachi 317, Japan

3. Toshiba Corporation, Isogo Engineering Center 8 Shinsugita-cho, Isogo-ku, Yokohama 235, Japan

4. Hitachi Engineering Co., Ltd. 3-2 Saiwai-cho, Hitachi 317, Japan

5. Tokyo Electric Power Co., Inc. 4-1 Uchisaiwai-cho, Chiyoda-ku, Tokyo 100, 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/NT89-A34339

Reference13 articles.

1. C. J. PAONE, R. C. STIRN, and J. A. WOOLLEY, “Rod Drop Accident Analysis for Large Boiling Water Reactors,” NEDO-10527, General Electric Company (1972).

2. M. ISHIKAWA, Y. KUGE, N. OHNISHI, E. TAKEUCHI, and Y. KANBAYASHI, “EUREKA: A Computer Code for Uranium-Oxide Fueled, Water Cooled Reactor Kinetics Analysis,” JAERI-1235, Japan Atomic Energy Research Institute (1974).

3. Analyzing the Rod Drop Accident in a Boiling Water Reactor

4. Comparison of Two- and Three-Dimensional Calculations of Super Prompt Critical Excursions

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