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Reactor Containment Dependability Analysis in Safety Critical Nuclear Power Plants: Design, Implementation and Experience

机译：安全关键核电厂的反应堆遏制可靠性分析：设计，实施和经验

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Chi-shiang Cho; Wei-ho Chung; Deyun Gao; Hongke Zhang; Sy-yen Kuo;
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年度 2015
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1. Reliability-based partial safety factors for dual performance level design of prestressed inner containment shells in Indian nuclear power plants [J] . Baidurya Bhattacharya, Aritra Chatterjee, Gunjan Agrawal, Nuclear Engineering and Design . 2013,第mara期

机译：印度核电厂预应力内部安全壳双重性能水平设计的基于可靠性的局部安全系数
2. Standard on Nuclear Safety Criteria and Design Process for Sodium Fast Reactor Nuclear Power Plants Approved (ANS-54.1) [J] . null Nuclear Standards News . 2020,第2期

机译：核安全标准标准及批准快速反应堆核电厂设计过程（ANS-54.1）
3. Analysis of the Probability of a Failure of the Prestressed Containment in the Event of Accidents Beyond the Design Basis at a Nuclear Power Station with a VVER Reactor [J] . E. Yu. Kuzmin, I. A. Magola, A. S. Solodovnikov Thermal engineering . 2004,第2期

机译：带有VVER反应堆的核电站发生超出设计基准的事故时，预应力安全壳失效的可能性分析
4. Reactor Containment Dependability Analysis in Safety Critical Nuclear Power Plants: Design, Implementation and Experience [C] . Cho Chi-Shiang, Chung Wei-Ho, Gao Deyun, 2011 17th IEEE International Conference on Parallel and Distributed Systems . 2011

机译：安全关键核电站的反应堆安全壳可靠性分析：设计，实施和经验
5. Analysis and Design of Thermal Management System for Thermoelectric Generators for Nuclear Power Plant Safety. [D] . Lin, Chih Chieh. 2014

机译：核电厂安全用热电发电机热管理系统的分析与设计。
6. Detection of alpha particle emitters originating from nuclear fuel inside reactor building of Fukushima Daiichi Nuclear Power Plant [O] . Yuki Morishita, Tatsuo Torii, Hiroshi Usami, -1

机译：在福岛第一核电站反应堆厂房内检测源自核燃料的α粒子发射器
7. Dependability Enhancement of Reactor Containment in Safety Critical Nuclear Power Plants [O] . Chi-shiang Cho, Wei-ho Chung, Deyun Gao, 2015

机译：安全关键核电厂反应堆遏制可靠性的提高
8. Reactor Safety Study:An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants. Appendix VII. Release of Radioactivity in Reactor Accidents. Appendix VIII. Physical Processes in Reactor Meltdown Accidents. Appendix IX. Safety Design Rationale for Nuclear Power Plants. Appendix X. Design Adequacy. [R] . 1976

机译：反应堆安全研究：美国商业核电厂事故风险评估。附录七。反应堆事故中放射性的释放。附录八。反应堆熔毁事故中的物理过程。附录九。核电厂安全设计理念。附录X.设计充分性。

Reactor Containment Dependability Analysis in Safety Critical Nuclear Power Plants: Design, Implementation and Experience

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