Study on Flow Induced Vibration in Reactor Internals of HPR1000

Yang Jie; Xi Zhide; Yu Danping; Ma Jianzhong; He Chao; Tan Tiancai

doi:10.13832/j.jnpe.2016.S2.0037

Volume 37 Issue S2

Feb. 2025

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Yang Jie, Xi Zhide, Yu Danping, Ma Jianzhong, He Chao, Tan Tiancai. Study on Flow Induced Vibration in Reactor Internals of HPR1000[J]. Nuclear Power Engineering, 2016, 37(S2): 37-39. doi: 10.13832/j.jnpe.2016.S2.0037

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Yang Jie, Xi Zhide, Yu Danping, Ma Jianzhong, He Chao, Tan Tiancai. Study on Flow Induced Vibration in Reactor Internals of HPR1000[J]. Nuclear Power Engineering, 2016, 37(S2): 37-39. doi: 10.13832/j.jnpe.2016.S2.0037

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Study on Flow Induced Vibration in Reactor Internals of HPR1000

doi: 10.13832/j.jnpe.2016.S2.0037

Reactor Engineering Research Institute, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2016-10-09
Rev Recd Date: 2016-12-18

Available Online: 2025-02-15

Publish Date: 2025-02-15

Abstract

Abstract

The flow induced vibration is studied in this paper by the combined methods of experiment and simulation. Based on the similarity criterion for the flow induced vibration, a 1:5 test model is designed. According to the RG1.20, the experiment study and analysis and calculation are conducted by finite element method. The challenges in the layout of sensor are solved in this test, and full test data are obtained. Based on the test data, the response of the key structures is obtained. Finally the comprehensive assessment for nuclear reactor internals fatigue strength is implemented. These methods can be of important reference value for other reactor internals FIV studies.
- Flow induced vibration,
- Similarity criterion,
- Fatigue strength