Numerical simulation of grid-to-rod fretting wear coupling with fuel properties during burnup

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-08-14 DOI:10.1016/j.anucene.2025.111792

Kangkang Jin , Shiwei Wang , Xiaojing Liu , Tengfei Zhang , Xiang Chai , Hui He

引用次数: 0

Abstract

A model of Flow-induced Vibration and Fretting Wear of fuel rod was developed to evaluate the nonlinear vibration and cladding wear of the fuel rod under the coolant excitation force, and fuel properties during burnup for a pressurized water reactor. For a fuel rod equipped with a middle grid, its vibration frequency was predominantly governed by the second-order modal frequency. The influence of initial gap between fuel rod and grid on the wear rates was not linear with maximum value at gap of 0. Fretting wear would produce an extra reduction of 38.94 MPa in the circumferential stress and an increase of 1.64 MPa in the radial stress compared to that by only considering changes in pellet-cladding gap pressure, creep, and thermal expansion over a period of 18 months. These findings suggest that the increase in radial stress constitutes the primary contributor to the elevated risk of fuel failure.

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燃耗过程中网格-杆微动磨损与燃油特性耦合的数值模拟

为了研究压水堆燃料棒在冷却剂激励力作用下的非线性振动和包壳磨损，以及燃料在燃耗过程中的性能，建立了燃料棒流动诱导振动和微动磨损模型。对于带有中间栅格的燃料棒，其振动频率主要受二阶模态频率控制。燃料棒与栅极之间的初始间隙对磨损率的影响不是线性的，在间隙为0时最大。相比于仅考虑包层间隙压力、蠕变和热膨胀的变化，微动磨损在18个月的时间内使周向应力额外减少38.94 MPa，径向应力额外增加1.64 MPa。这些发现表明，径向应力的增加是燃料失效风险增加的主要原因。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

期刊介绍： Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.