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。
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 ofβ-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 prospec
作者
杨红艳
陈寰
张瑞谦
韦天国
邱绍宇
彭小明
YANG Hong-yan;CHEN Huan;ZHANG Rui-qian;WEI Tian-guo;QIU Shao-yu;PENG Xiao-ming(Science and Technology on Reactor Fuel and Materials Laboratory,Nuclear Power Institute of China,Chengdu 610213,China)
出处
《表面技术》
EI
CAS
CSCD
北大核心
2022年第7期87-97,共11页
Surface Technology
基金
国防科技工业核动力技术创新中心科研项目(K305004008)。
关键词
耐事故包壳
Cr涂层
沉积技术
性能评价
accident tolerant fuel cladding
Cr coating
deposition technology
performance evaluation
