Cr涂层锆合金事故容错燃料包壳材料研究进展  

Review on Cr-coated Zirconium Alloy Cladding for Accident Tolerant Fuel

作　　者：严俊 廖业宏 彭振驯 王占伟 李思功 马海滨 薛佳祥 任啟森 YAN Jun;LIAO Ye-hong;PENG Zhen-xun;WANG Zhan-wei;LI Si-gong;MA Hai-bin;XUE Jia-xiang;REN Qi-sen(Institute of Nuclear Fuel and Materials,China Nuclear Power Technology Research Institute,Guangdong Shenzhen 518000,China)

机构地区：[1]中广核研究院有限公司核燃料与材料研究所,广东深圳518000

出　　处：《表面技术》2023年第12期206-224,共19页Surface Technology

基　　金：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。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.

关 键 词：事故容错燃料 Cr涂层锆合金 腐蚀 氧化 力学性能 

分 类 号：TG174.4[金属学及工艺—金属表面处理]