Flow Induced Vibration and Fretting Wear in PWR Fuel

Author:

King S. J.1,Young M. Y.1,Seel D. D.1,Conner M. E.1,Lu Roger Y.1,Paramonov D. V.2

Affiliation:

1. Westinghouse Nuclear Fuel, Columbia, SC

2. Westinghouse Science and Technology, Pittsburgh, PA

Abstract

Fuel rod fretting wear is due to complex combinations of factors. Excitation of the fuel rod and motion relative to its supports can be caused by coolant flow and mechanical forces. The amplitude of response for a given set of flow and mechanical forces is dependent on the fuel rod and its support system. The fuel rod mass and stiffness and location of supports along its length dictate the mode shapes and natural frequencies. The contact geometry between the support system and fuel rod is also an important factor. The two primary areas covered in this paper are 1) the types of flow conditions that may exist in a reactor core and how they would result in excitation of the fuel rod and 2) how the relative motion of the rod to its supports can result in fretting wear. Numerous testing techniques, ranging from microscopic, to single grid cell tests, to high temperature and flow full scale multiple fuel assembly tests, are discussed.

Publisher

ASMEDC

Cited by 8 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

1. Review of spacer grid to rod fretting in pressurized water reactor;Nuclear Engineering and Design;2024-03

2. Study on the characteristics of axial fluid excitation on fuel rods with spacer grids;Annals of Nuclear Energy;2023-12

3. STRESS-STRAIN STATE AND WEAR MODELLING FOR FUEL ROD – GRID CONTACT;Problems of Atomic Science and Technology;2023-04-11

4. Effects of Normal Load, Thickness of Oxide Layer and Number of Cycles on Fretting Wear of PWR Fuel ROD Cladding;Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 2;2023

5. Nuclear power systems;Fretting Wear and Fretting Fatigue;2023

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