耐事故燃料用Cr涂层锆合金包壳研究进展  

Current progress of Cr-coated zirconium alloy cladding for accident tolerant fuel

作　　者：段振刚 陈平[1] 周毅[1] 高士鑫 焦拥军[1] 尹春雨[1] 何梁 DUAN Zhengang;CHEN Ping;ZHOU Yi;GAO Shixin;JIAO Yongjun;YIN Chunyun;HE Liang(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu 610213,China)

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610213

出　　处：《核技术》2022年第3期1-12,共12页Nuclear Techniques

基　　金：国家自然科学重点项目(No.U2067221);四川省科技计划(No.2021YJ0512)资助。

摘　　要：2011年日本福岛核事故后,燃料包壳表面涂层技术成为耐事故燃料研发的主要方向之一。国内外对此开展了大量的研究工作。经过10年多的技术探索,Cr涂层包壳从众多涂层方案中脱颖而出,已成为涂层包壳研发主要技术路线。目前国际上Cr涂层包壳技术已完成了制备工艺、性能评价及设计准则等研究工作,进入了由技术研发到工程应用的重要转型阶段。梳理国外的研发经验可为我国的Cr涂层研究提供参考。法国和美国在Cr涂层包壳研发中开展了大量的堆内外试验,在工程应用上取得了实质性的突破。因此,本文系统梳理了到目前为止法国和美国在Cr涂层研发方面主要研究内容、研究方法及其未来规划。Surface coating technology of nuclear fuel cladding has been one of the main research fields of accident tolerant fuel(ATF)since the Fukushima nuclear accident in Japan in 2011.A great deal of studies about the coating on nuclear fuel cladding have been carried out both at home and aboard.After nearly ten years of continuous technical exploration,Cr-coating cladding has stood out from the rest and has been the main technical roadmap of coated cladding development.At present,the development of Cr-coated cladding in the world has nearly completed the research on the preparation process,performance evaluation and design criterion,and has entered a critical phase from the technical research to engineering application.A large number of in-pile and out-of-pile tests for research and development(R&D)of Cr coated cladding have been carried out in France and United States,and substantive breakthroughs have been made in engineering application.The latest research contents,methods,achievements and future plans of Cr coating in France and the United States are systematically reviewed in this study.It is expected to provide valuable references for domestic R&D of Cr-coated cladding.

关 键 词：CR 涂层 燃料包壳 耐事故燃料 核燃料 

分 类 号：TL99[核科学技术—核技术及应用]