Analysis of Fatigue Time Limit Aging of Reactor Pressure Vessels

Shao Xuejiao; Xie Hai; Zhang Liping; YangYu; Du Juan; Tian Jun; Kuang Linyuan; Gao Shiqing

Volume 41 Issue 5

Sep. 2020

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Article Navigation > Nuclear Power Engineering > 2020 > 41(5): 60-64

Shao Xuejiao, Xie Hai, Zhang Liping, YangYu, Du Juan, Tian Jun, Kuang Linyuan, Gao Shiqing. Analysis of Fatigue Time Limit Aging of Reactor Pressure Vessels[J]. Nuclear Power Engineering, 2020, 41(5): 60-64.

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Shao Xuejiao, Xie Hai, Zhang Liping, YangYu, Du Juan, Tian Jun, Kuang Linyuan, Gao Shiqing. Analysis of Fatigue Time Limit Aging of Reactor Pressure Vessels[J]. Nuclear Power Engineering, 2020, 41(5): 60-64.

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Analysis of Fatigue Time Limit Aging of Reactor Pressure Vessels

Publish Date: 2020-09-27

Abstract

Abstract

Based on two methods of evaluating the influence of the coolant environment on the fatigue life of equipment proposed by U.S.NRC in the management guideline RG1.207, the effects on different environmental fatigue correction factor（F_en） expressions and boundary conditions were compared between the NUREG/CR-6909 of USA and JNES of JAPAN. The difference of the environmental fatigue life assessment between environmental fatigue correction factor and environmental fatigue curve was also analyzed. Finally, the three methods were adopted in the analysis of the reactor pressure vessel inlet nozzle fatigue assessment. The methods are Fen method considering strain rate history, environmental fatigue curve method and the Fen method using conservative parameters. The results show that, compared with other two methods, the Fen method considering strain rate history can evaluate the environmental fatigue life of structures with higher accuracy.
- Environmental fatigue curve,
- Environmental fatigue correction factor,
- Fatigue life

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