2Rudolf MasopustSeismic Verification Methods for Structures and Equipment of VVER-Type and RBMK-Type NPPs Summary of Experiences[C]. Transactions of the 17th International Conference on Structural Mechanics in Reactor Technology SMiRT 17, Prague, Czech Republic, 2003.
3Structural Integrity Associates. Vibration Fatigue of Small Bore Socket-Welded Pipe Joints[R]. EPRI TR- 107455, Electric Power Research Institute, Palo Alto, CA,1997.
4Fei Xue, Lei Lin, Wenxin Ti,et al. Vibration Assessment Method and Engineering Applications to Small Bore Piping in Nuclear Power Plant[C]. the 9th International Conference on Engineering Structural Integrity Assessment, 2007, 204-205.
5Lu Nianwen, Wang Xiaolong, Wu Xiaozhen. Piping Vibration Stress 'Measurement and Life Assessment [C]. 18th International Conference on Structural Mechanics inReactor Technology, Beijing, China, August 7-12, 2005, SMiRT 18-D03-8, 777-780.
6Shah V N. Assessment of Pressurized Water Reactor Primary System Leaks[R]. NUREG/CR-6582, INEEL/ EXT-97-01068, 1998.
7EDF. EME CR 01 0059-IPS[R]. STOLLER, S. M, 1974- 1994 Nuclear Power Experience, PWR-2, V. B., S. M. Stoller Corporation, Lafayette, CO, 1994.
8JAMES R,FARR MAAN H JAWAD.ASME压力容器设计指南[M].郑津洋,译.北京:化学工业出版社,2003.
