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Cr涂层锆合金事故容错燃料包壳材料研究进展
引用本文:严俊,廖业宏,彭振驯,王占伟,李思功,马海滨,薛佳祥,任啟森.Cr涂层锆合金事故容错燃料包壳材料研究进展[J].表面技术,2023,52(12):206-224.
作者姓名:严俊  廖业宏  彭振驯  王占伟  李思功  马海滨  薛佳祥  任啟森
作者单位:中广核研究院有限公司 核燃料与材料研究所,广东 深圳 518000
基金项目:国家重点研发计划(2017YFB0702404)
摘    要:自2011年日本福岛核事故后,事故容错燃料成为核电企业和相关科研机构的研究重点,旨在提升反应堆燃料系统的可靠性与安全性。锆合金包壳表面涂层技术是事故容错燃料研发的短期目标之一,其中,Cr涂层锆合金包壳为当前的主要技术路线。围绕涂层制备工艺、微观组织以及关键服役性能三方面,对Cr涂层锆合金的相关研究进展进行了综述。首先,对比介绍了锆合金表面金属Cr涂层制备工艺及其特点,涵盖了物理气相沉积、冷喷涂和3D激光熔覆等技术,同步介绍了国际核电巨头所采用的制备工艺及相关研发进展。其次,简单阐述了Cr涂层微观组织特征,重点阐述了正常运行工况下Cr涂层锆合金高温高压水腐蚀性能、高温高压水微动磨蚀性能、高温力学行为和辐照行为,以及事故工况下该材料体系高温内压爆破行为、高温蒸气氧化-淬火行为等,并同步针对其微观辐照机制、高温氧化/腐蚀机制等进行了归纳和深入分析。最后,对当前研究所存在的问题和未来发展方向进行了归纳分析。

关 键 词:事故容错燃料  Cr涂层锆合金  腐蚀  氧化  力学性能
收稿时间:2022/11/24 0:00:00
修稿时间:2023/3/21 0:00:00

Review on Cr-coated Zirconium Alloy Cladding for Accident Tolerant Fuel
YAN Jun,LIAO Ye-hong,PENG Zhen-xun,WANG Zhan-wei,LI Si-gong,MA Hai-bin,XUE Jia-xiang,REN Qi-sen.Review on Cr-coated Zirconium Alloy Cladding for Accident Tolerant Fuel[J].Surface Technology,2023,52(12):206-224.
Authors:YAN Jun  LIAO Ye-hong  PENG Zhen-xun  WANG Zhan-wei  LI Si-gong  MA Hai-bin  XUE Jia-xiang  REN Qi-sen
Affiliation:Institute of Nuclear Fuel and Materials, China Nuclear Power Technology Research Institute, Guangdong Shenzhen 518000, China
Abstract:After the Fukushima nuclear accident in Japan in 2011, accident tolerant fuels (ATF) have become the research focus of nuclear power enterprises and related scientific research institutions, which aims to improve the reliability and safety of the nuclear reactors. The surface-modified Zr alloy cladding is a short-term goal for research and development of ATF and the Cr-coated Zr alloy cladding has become the current main technical route. Focusing on the preparation techniques, microstructural characteristics, and critical service performance, the related research of Cr-coated Zr alloy cladding was reviewed. Firstly, the various preparation techniques and characteristics of Cr coating on zirconium alloy surface were compared and introduced, including physical vapor deposition, cold spraying, and 3D laser and the preparation techniques and related research and development progress adopted by international nuclear power giants were introduced at the same time. Secondly, the microstructure of Cr coating was described and the corrosion performance, fretting and abrasion performance, high temperature mechanical behavior and irradiation behavior of Cr-coated Zr alloy under normal operating conditions were emphatically expounded. Moreover, the internal pressure creep and burst behavior at high temperature, high-temperature steam oxidation and quenching behavior the Cr-coated Zr alloy cladding were elaborated. In addition, the mechanisms related with irradiation, oxidation, and corrosion were summarized and analyzed in depth. Finally, the existing problems and the future development directions for the current research were thoroughly summarized and prospected.
Keywords:ATF  Cr-coated Zr alloy  corrosion  oxidation  mechanical properties
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