Fretting wear mechanism of nuclear fuel cladding tube under different tangential displacement

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2024-12-01 Epub Date: 2024-09-04 DOI:10.1016/j.nucengdes.2024.113567
Jialing Li , Huoming Shen , Yehong Liao , Yuxing Wang , Songye Jin , Zhenxun Peng , Kaimo Wang , Qisen Ren
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Abstract

The fretting wear behavior of Zr-1Nb alloy cladding tubes under different tangential displacement amplitudes under grid-to-rod contact conditions was investigated. The dependence of the morphology of wear scars, microstructure, and wear mechanisms on the tangential displacement amplitudes was analyzed. The results indicate that as the tangential displacement amplitude increases, the fretting regime transitions from the mixed fretting regime to the gross slip regime gradually, moreover, the coefficient of friction initially increases and then decreases, while the wear volume and maximum wear depth gradually increase. In the mixed fretting regime, the primary wear mechanism is adhesive wear, whereas the primary wear mechanism in the gross slip regime is delamination. Moreover, the extent of oxidative wear becomes more severe while the tangential displacement amplitude is larger.

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不同切向位移下核燃料包壳管的摩擦磨损机理
研究了Zr-1Nb合金覆层管在栅对杆接触条件下不同切向位移幅度下的摩擦磨损行为。分析了磨损疤痕形态、微观结构和磨损机制对切向位移振幅的影响。结果表明,随着切向位移振幅的增大,烧蚀机制逐渐从混合烧蚀机制过渡到粗滑机制,而且摩擦系数先增大后减小,磨损量和最大磨损深度逐渐增大。在混合摩擦状态下,主要的磨损机制是粘着磨损,而在粗滑状态下,主要的磨损机制是分层。此外,当切向位移幅度较大时,氧化磨损的程度会变得更加严重。
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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