Author:
Chen Mingya,Lu Feng,Wang Rongshan,Yu Weiwei,Wang Donghui,Zhang Guodong,Xue Fei
Funder
National High Technology Research and Development Program of China
National Natural Science Foundation of China
Subject
Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Reference28 articles.
1. ASME Boiler and Pressure Vessel Code, Section XI, Appendix E, Evaluation of Unanticipated Operating Events;ASME,2013
2. Nuclear Power Plants Life Management Reactor Pressure Vessel Strategic Evaluation for Fluence in Relation with Integrity Assessment;Bezdikian,2008
3. The deterministic structural integrity assessment of reactor pressure vessels under pressurized thermal shock loading;Chen;Nucl. Eng. Des.,2015
4. Use of the failure assessment diagram to evaluate the safety of the reactor pressure vessel;Chen;J. Press. Vessel Technol.,2015
5. Structural integrity assessment of the reactor pressure vessel under the pressurized thermal shock loading;Chen;Nucl. Eng. Des.,2014
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