Unified formulae for evaluating load reduction by change in stiffness of circumferential crack considering general piping systems

Author:

Kim Yeji,Hwang Il-Soon,Oh Young-Jin

Funder

Korea Institute of Energy Technology Evaluation and Planning

Ministry of Trade, Industry & Energy, Republic of Korea

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference28 articles.

1. Leak-before-break evaluation procedures, US NRC Standard review plan 3.6.3;NUREG-0800,2007

2. Report of the US Nuclear Regulatory Commission piping review committee -Evaluation of potential for pipe breaks;NUREG-1061 Vol 3,1984

3. Development of technical basis for leak-before-break evaluation procedures;Scott,2002

4. State-of-the-art report on piping fracture mechanics;Wilkowski,1998

5. Effect of pipe restraint on the conservatism of leak-before-break design of nuclear power plant;Kim,2015

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