Measurement and analysis of the leak tightness of reactor containment vessels: experiences and results-Reference-Cited by-同舟云学术

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Measurement and analysis of the leak tightness of reactor containment vessels: experiences and results

Published:2015-10 Issue: Volume:292 Page:112-122
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Cho Chi-Shiang,Chung Wei-Ho,Kuo Sy-Yen

Funder

Ministry of Science and Technology

NSC

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

Reference22 articles.

1. Primary Reactor Containment Leakage Testing for Water-cooled Power Reactors;10 CFR Part 50 Appendix J,1996

2. Leakage Rate Testing of Containment Structures for Nuclear Reactors;ANSI N45.4,1972

3. Verification and Validation of Non-safety-related Scientific and Engineering Computer Programs for the Nuclear Industry;ANSI/ANS 10.4,2008

4. Containment System Leakage Testing Requirements;ANSI/ANS 56.8,1987

5. Containment System Leakage Testing Requirements;ANSI/ANS 56.8,1994

Cited by 2 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Research on mechanism of gas leakage in microchannels of steel containment vessels for nuclear power plants;Nuclear Engineering and Technology;2024-08

2. The Mechatronic System Design Of Ultrasonic Scanner For Inservice Inspection Of Research Reactor;Journal of Physics: Conference Series;2018-02

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