Status for Fretting-Wear Study of Nuclear Structural Components

Gao Lixia; Li Pengzhou; Lai Jiang; Ma Jianzhong; Xi Zhide

doi:10.13832/j.jnpe.2016.S2.0073

Volume 37 Issue S2

Feb. 2025

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Article Navigation > Nuclear Power Engineering > 2016 > 37(S2): 73-76

ZHANG Sheng, GU Hanyang, CHEN Yuqing, ZHOU Xiaojia, LIU Gang. Experimental and Numerical Investigations of Natural Convection in a Vertical Annulus[J]. Nuclear Power Engineering, 2015, 36(1): 14-17. doi: 10.13832/j.jnpe.2015.01.0014

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Gao Lixia, Li Pengzhou, Lai Jiang, Ma Jianzhong, Xi Zhide. Status for Fretting-Wear Study of Nuclear Structural Components[J]. Nuclear Power Engineering, 2016, 37(S2): 73-76. doi: 10.13832/j.jnpe.2016.S2.0073

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Status for Fretting-Wear Study of Nuclear Structural Components

doi: 10.13832/j.jnpe.2016.S2.0073

Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2016-10-09
Rev Recd Date: 2016-12-22

Available Online: 2025-02-15

Publish Date: 2025-02-15

Abstract

Abstract

Flow-induced vibration of steam generator tubes or fuel rods results in fretting-wear damage due to impacting and rubbing of the tubes against their supports or fuel rods against their grids. Tubes and fuel rods are working at high temperature and pressure. The damages should be bad for the safety of nuclear reactors. Temperature and water chemistry are the key parameters for fretting-wear. This paper introduces the status for the studies of fretting wear in the world.
- High-temperature and pressure,
- Nuclear structural component,
- Fretting-wear

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