CZ2合金熔覆层预氧化规律及微动磨损性能研究

IF 0.4 Q4 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Fuel Cycle and Waste Technology Pub Date : 2022-08-08 DOI:10.1115/icone29-93804
Guocheng Sun, Shi Lin, Xu Wang, Liu-tao Chen
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引用次数: 0

摘要

在压水堆堆芯中,冷却剂流动引起的格棒微动振动是导致燃料棒损坏的主要因素。锆包层预氧化处理在其表面形成陶瓷层是减少GTRF磨损的主要途径。研究了在空气中形成的CZ2合金包覆预氧化氧化锆陶瓷层的生长规律。采用原位纳米力学测试系统测量了CZ2合金熔覆层和氧化锆陶瓷层的显微硬度和弹性模量。扫描电镜观察了预氧化氧化锆陶瓷层的形貌。通过高温、高压微动磨损试验研究了预氧化氧化锆陶瓷层的微动磨损性能。结果表明:在560℃和600℃时,CZ2合金覆层预氧化氧化锆陶瓷层生长规律一致,预氧化氧化锆陶瓷层致密、无裂纹;预氧化氧化锆陶瓷层可以提高CZ2合金熔覆层在高温高压下的抗微动磨损性能,最大磨损深度降低80%。
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Study of Pre-Oxidization Law and Fretting Wear Resistance of CZ2 Alloy Cladding
In the core of pressurized water nuclear reactor, coolant flow-induced vibration of Grid to rod fretting (GTRF) is the dominant factor leading to fuel rod damage. pre-oxidization treatment of zirconium cladding forming a ceramic layer on its surface is the main way to reduce the GTRF wear. In this paper, the growth law of CZ2 alloy cladding pre-oxidization zirconia ceramic layer formed in air was studied. The micro-hardness and elastic modulus of CZ2 alloy cladding and zirconia ceramic layer were measured by in-situ nano-mechanical testing system., while the morphology of these pre-oxidization zirconia ceramic layer were observed by scanning electron microscope. The fretting wear properties of the pre-oxidization zirconia ceramic layer were studied by high temperature and high pressure fretting wear tests. The results show that the pre-oxidization zirconia ceramic layer growth law of CZ2 alloy cladding at 560°C and 600°C is consistent, and the pre-oxidization zirconia ceramic layer are compact and crack-free. The pre-oxidization zirconia ceramic layer can improve the fretting wear resistance of CZ2 alloy cladding at high temperature and high pressure, and the maximum wear depth were reduced by 80%.
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来源期刊
CiteScore
0.80
自引率
25.00%
发文量
35
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