Probabilistic analysis of core shroud cracks

Author:

Wu Wen-Fang,Tsai Chuen-Horng,Tu Kuan-Chywan,You Jang-Shyong

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

Reference18 articles.

1. Basic Principles;Ang,1975

2. Ford, F.P., Anderson, P.L., Haschke, D., 1997. PLEDGE Analysis of Cracking in Irradiated Core Shroud at KKM. GE Nuclear Energy Water Chemistry and Materials Workshop.

3. Harris, F.O., Lim, E.Y., Dedhia, D.D., Woo, H.H., Chou, C.K., 1982. Fracture Mechanics Models Developed for Piping Reliability Assessment in Light Water Reactors, NUREG/GE-2301. U.S. Nuclear Regulatory Commission, Washington, DC.

4. Hazelton, W.S., Koo, W.H., 1988. Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping, NUREG-0313, Rev. 2. U.S. Nuclear Regulatory Commission, Washington, DC.

5. Formation and growth of cracking in feedwater pipes and RPV nozzles;Kussmaul;Nuclear Engineering and Design,1984

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1. Risk-based inspection and maintenance in process plants and their practices in Taiwan;Journal of the Chinese Institute of Engineers;2016-03-21

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