1 Nuclear and Radiation Safety Center, Beijing 100082, China 2 China Nuclear Power Technology Research Institute, Shenzhen 518000, Guangdong, China 3 School of Materials Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China 4 School of Materials Science and Engineering, University of Science and Technology Beijing, Beijing 100083, China
Abstract: In the pursuit of the dual objectives of heightened economic efficiency and enhanced safety, the trend of achieving high burnup levels, exceeding 62 GWd/MTU, has become a prominent focal point in nuclear fuel development. However, it is imperative to recognize that increasing burnup levels inevitably introduce challenges, leading to the degradation and potential failure of both fuel pellets and cladding materials, thus giving rise to safety concerns. This paper initiates with a comprehensive examination and delineation of the challenges confronted by conventional UO2 fuel pellet and Zr alloy cladding when operating under high burnup conditions. For instance, the formation and rapid propagation of high burnup structures at the periphery of pellets, increasing proportion of fission gas release, heightened internal pressures within fuel rods, enhancement of corrosion associated with hydrogen pickup of claddings. In addition, the fragmentation, relocation, and dispersal of fuel pellets during the loss of coolant accident scenarios. This paper elucidates the critical strategies employed to address the above challenges effectively. Subsequently, the article consolidates and summarizes the recent developments and accomplishments within the nuclear industry pertaining to accident tolerant fuel. It places particular emphasis on the critical in-service performance of Cr-coated Zr alloy claddings and large-grained UO2 fuel pellet, including fission gas release, pellet and cladding mechanical interactions, corrosion of cladding in aqueous environments, and high-temperature steam oxidation and quenching behavior. Simultaneously, the paper conducts a comparative analysis between the Cr-coated Zr alloy cladding and large-grained UO2 fuel pellets ATF project with the traditional nuclear fuel system. Particular attention is given to operational advantages, particularly in the context of high burnup conditions. The research findings strongly suggest the recent ATF projects hold significant promise for application in high burnup projects. This review aims to deepen nuclear industry stakeholders' understanding of high burnup initiatives while offering insightful guidance for integrating domestically developed ATF materials into high burnup applications, thus contributing to the advancement of nuclear power safety and economic viability.
通讯作者:
*周张健,北京科技大学材料科学与工程学院教授、博士研究生导师。1996年于中国地质大学(北京)矿物专业获硕士学位,2007年于北京科技大学材料专业获博士学位。担任国际梯度材料顾问委员会(IACFGM)委员,Journal of Nuclear Materials期刊编辑顾问委员,《材料导报》编委。主要从事能源系统等极端环境用先进材料研究,包括ODS钢、难熔金属、功能梯度材料等,以第一作者或通信作者发表论文160余篇。zhouzhj@mater.ustb.edu.cn
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2024, Vol. 38 
