Analysis of Flow-Induced Vibration of Nuclear Reactor Internals

Lai Jiang; Yang Jie; Xi Zhide; Sun Lei; Li Pengzhou

doi:10.13832/j.jnpe.2016.S2.0028

Volume 37 Issue S2

Feb. 2025

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Lai Jiang, Yang Jie, Xi Zhide, Sun Lei, Li Pengzhou. Analysis of Flow-Induced Vibration of Nuclear Reactor Internals[J]. Nuclear Power Engineering, 2016, 37(S2): 28-31. doi: 10.13832/j.jnpe.2016.S2.0028

Citation:

Lai Jiang, Yang Jie, Xi Zhide, Sun Lei, Li Pengzhou. Analysis of Flow-Induced Vibration of Nuclear Reactor Internals[J]. Nuclear Power Engineering, 2016, 37(S2): 28-31. doi: 10.13832/j.jnpe.2016.S2.0028

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Analysis of Flow-Induced Vibration of Nuclear Reactor Internals

doi: 10.13832/j.jnpe.2016.S2.0028

Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2016-10-09
Rev Recd Date: 2016-11-12

Available Online: 2025-02-15

Publish Date: 2025-02-15

Abstract

Abstract

The flow-induced vibration characteristic of a new nuclear reactor was analyzed in this paper by performing dynamic test and numerical calculation. A 1/2 scaled-down model of a new designed nuclear reactor was manufactured for performing the dynamic test with the hydrodynamics simulation system at the 100% operation condition. And the dynamical responses of core barrel and secondary core support structure were measured in the test. Based on the results of the dynamic test, a three-dimensional finite element model of the reactor internals for the numerical analysis was constructed to obtain the max strains and stresses of core barrel and secondary core support structure at the 100% operation condition.
- Flow-induced vibration,
- Nuclear reactor,
- Core barrel,
- Secondary core support structure,
- Vortex-induced vibration