A study of heat capacity temperature limit of BWR-Reference-Cited by-同舟云学术

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A study of heat capacity temperature limit of BWR

Published:2012-02 Issue: Volume:243 Page:279-286
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Wang Shih-Jen,Chen Jyh-Jun,Chien Chun-Sheng,Teng Jyh-Tong

Funder

Institute of Nuclear Energy Research

Chung Yuan Christian University

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference17 articles.

1. BWROG EPGs/SAGs Revision 2;BWROG,2001

2. Determination of BWR minimum steam cooling reactor water level and associated steam flow using MAAP4 code;Chen;Nucl. Eng. Des.,2010

3. Development of parameter identification capability for MAAP4 code;Chien;Nucl. Technol.,2008

4. Study on the minimum number of SRVs required for emergency depressurization in EOP of BWR power plants;Chien;Nucl. Eng. Des.,2010

5. Simplification of the severe accident management guideline for the containment flooding in a Mark-III containment;Chuang;Nucl. Technol.,2009

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