杨红艳,陈寰,张瑞谦,韦天国,邱绍宇,彭小明.核电耐事故锆包壳表面涂层研究进展[J].表面技术,2022,51(7):87-97.
YANG Hong-yan,CHEN Huan,ZHANG Rui-qian,WEI Tian-guo,QIU Shao-yu,PENG Xiao-ming.Research Progress of the Surface Coating for Zirconium Alloy Cladding of Accident Tolerant Fuel in Nuclear Power Plant[J].Surface Technology,2022,51(7):87-97
核电耐事故锆包壳表面涂层研究进展
Research Progress of the Surface Coating for Zirconium Alloy Cladding of Accident Tolerant Fuel in Nuclear Power Plant
  
DOI:10.16490/j.cnki.issn.1001-3660.2022.07.008
中文关键词:  耐事故包壳  Cr涂层  沉积技术  性能评价
英文关键词:accident tolerant fuel cladding  Cr coating  deposition technology  performance evaluation
基金项目:国防科技工业核动力技术创新中心科研项目(K305004008)
作者单位
杨红艳 中国核动力研究设计院 反应堆燃料及材料重点实验室,成都 610213 
陈寰 中国核动力研究设计院 反应堆燃料及材料重点实验室,成都 610213 
张瑞谦 中国核动力研究设计院 反应堆燃料及材料重点实验室,成都 610213 
韦天国 中国核动力研究设计院 反应堆燃料及材料重点实验室,成都 610213 
邱绍宇 中国核动力研究设计院 反应堆燃料及材料重点实验室,成都 610213 
彭小明 中国核动力研究设计院 反应堆燃料及材料重点实验室,成都 610213 
AuthorInstitution
YANG Hong-yan Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610213, China 
CHEN Huan Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610213, China 
ZHANG Rui-qian Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610213, China 
WEI Tian-guo Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610213, China 
QIU Shao-yu Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610213, China 
PENG Xiao-ming Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610213, China 
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中文摘要:
      锆合金表面涂层作为一种短期内最易于实现商业化工程应用的耐事故包壳材料,已成为国际上新型核电燃料元件研发的热点。综述了近年锆包壳表面涂层研究已取得的重要研究成果。阐述了锆合金表面涂层材料的发展,包括MAX相、Cr系、陶瓷和FeCrAl合金等,重点分析了金属Cr因易于获得高质量涂层,且具有优异的耐腐蚀、耐高温氧化等性能,成为耐事故锆包壳表面涂层的首选材料。讨论了锆合金表面Cr涂层沉积技术的发展,包括物理气相沉积法、冷喷涂、激光熔覆和等离子喷涂等,着重分析了不同的科研机构均形成了各自的涂层锆管研发路线。评价了锆包壳表面Cr涂层的关键应用性能,重点分析了高温氧化–脆化、腐蚀、环压、磨损以及高温爆破等条件下的表面涂层效应。水蒸气环境中表面Cr涂层可有效阻止氧元素向锆基体的扩散,高温氧化–淬火后锆基体内残留了大量β–Zr相,涂层锆管仍具有一定的残余塑性;小变形工况下表面Cr涂层与锆基体间具有良好的膜基协同变形能力;Cr涂层对锆管基体具有一定的表面强化效应,一定程度上可改善涂层锆管的高温爆破性能;堆内辐照后Cr–Zr界面成分、微结构稳定性良好,21%环向肿胀后表面Cr涂层依然未剥落。最后,总结与展望了锆包壳表面Cr涂层的科研成果与研究方向。
英文摘要:
      With realizing engineering application easily in the short term, the surface coating of zirconium alloy for accident tolerant cladding has become hotspot in the research and development of latest nuclear fuel elements in the world. This report was about the main research achievements of surface coating on zirconium cladding in recent years. The development of the coating materials on zirconium alloy was reviewed, including Max phase, Cr series, ceramics and FeCrAl alloy. For its high-quality, excellent corrosion resistance and high temperature oxidation resistance, the metal Cr had become the preferred material of zirconium surface coating for accident tolerant cladding. The deposition technology of Cr coating on zirconium alloy were discussed, including physical vapor deposition, cold spraying, laser cladding and plasma spraying. The different technology developments of coated tube for different research institute were mainly analyzed. The key application properties of Cr coating on zirconium alloy were evaluated and the surface coating effects were analyzed especially under high temperature oxidation embrittlement, corrosion, and ring compression, wears and high temperature burst. Cr coating could effectively prevent oxygen diffusing into zirconium alloy in steam environment, and zirconium substrate remained a large amount of β-Zr phase after oxidation test, and the zirconium tube coated Cr still had residual plasticity after high temperature oxidation-quenching test. There were good coordinating deformation between Cr coating and zirconium substrate under small deformation. The burst performances of the coated zirconium tube were improved for surface strengthening effect of Cr coating. After reactor irradiation, the composition and micro-structure of Cr-Zr interface were stable. With 21% expansion due to compression of coated tube after irradiation, the surface Cr coating was still tight. Finally, the research achievements and research directions of Cr coating on zirconium cladding for accident tolerant cladding were summarized and prospected.
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