Study on LBB Behavior of Nuclear Primary Pipes after Long-Term Thermal Aging

Author:

Lv Xuming1,Li Shilei1,Zhang Hailong1,Wang Yanli12,Xue Fei3,Wang Xitao12

Affiliation:

1. State Key Laboratory for Advanced Metals and Materials; University of Science and Technology Beijing; Beijing China

2. Collaborative Innovation Center of Steel Technology; University of Science and Technology Beijing; Beijing China

3. Suzhou Nuclear Power Research Institute; Suzhou China

Publisher

John Wiley & Sons, Inc.

Reference16 articles.

1. P. Scott R. J. Olson G. Wilkowski Development of Technical Basis for Leak-Before-Break Evaluation Procedures” (Report NUREG/CR-6765, Nuclear Regulatory Commission, 2002)

2. Leak-before-break qualification of primary heat transport piping of 500 MWe Tarapur Atomic Power Plant;Chattopadhyay;International Journal of Pressure Vessels and Piping,1999

3. Effect of nozzle geometry on leak-before-break analysis of pressurised piping;Nam;Engineering Fracture Mechanics,2001

4. Aging and life prediction of cast duplex stainless steel components;Chung;International Journal of Pressure Vessels and Piping,1992

5. Study of phase transformation and mechanical properties evolution of duplex stainless steels after long term thermal ageing (> 20years);Pareige;Journal of Nuclear Materials,2011

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