INORGANIC MATERIALS AND CERAMIC MATRIX COMPOSITES |
|
|
|
|
|
A Complete Review on the Accident Tolerant Fuel for the High Burnup Assembly |
FU Hao1, PENG Zhenxun2, LIAO Yehong2, XUE Jiaxiang2, SHEN Zhao3, ZHOU Zhangjian4,*
|
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.
|
Published: 25 November 2024
Online: 2024-11-22
|
|
|
|
1 Smith F, Daum R. Alternative licensing approaches for higher burnup fuel-a scoping study on deterministic and risk-informed alternatives supporting fuel discharge burnup extension, Electric Power Research Institute, USA, 2020, pp. 2. 2 Pimentel F, Smith F. The economic benefits and challenges with utilizing increased enrichment and fuel burnup for light-water-reactors, Nuclear Energy Institute, USA, 2019, pp. 2. 3 Wiesenack W. Nuclear Engineering and Dseign, 1997, 172(1), 83. 4 Rondinella V V, Wiss T. Materials Today, 2010, 13(12), 24. 5 Xiao H, Long C, Chen H. Journal of Nuclear Materials, 2021, 556, 153151. 6 Michelle B, Alice C, James C, et al. Interpretation of research on fuel fragmentation, reclocation, and dispersal at high burnup, United States Nuclear Regulatory Commission, 2021, pp.24. 7 Heinz S, Wolfgang W, Veronique G, et al. Report on fuel fragmentation, relocation and dispersal, Nuclear Energy Agency, USA, 2016, pp.23. 8 Bischoff J, Brachet J C, Bragg-Sitton S M, et al. State-of-the-art report on light water reactor accident-tolerant fuels, Nuclear Energy Agency, Organisation for Economic Co-operation and Development, 2018, pp.115. 9 Brachet J C, Idarraga-Trujillo I, Flem M L, et al. Journal of Nuclear Materials, 2019, 517, 268. 10 Brachet J C, Rouesne E, Ribis J, et al. Corrosion Science, 2020, 167, 108537. 11 Brachet J C, Le Saux M, Bischoff J, et al. Journal of Nuclear Materials, 2020, 533, 152106. 12 Brian R M. Draft safety evaluation for global nuclear fuel proposed amendment 51 to topical rport, NEDE-24011-P-A-29, general electric standard application for reactor fuel, Global Nuclear Fuel, United States Nuclear Regulatory Commission, 2020, pp.1. 13 Walter L K, et al. Incremental extension of burnup limit for westinghouse and combustion engineering fuel designs, United States Nuclear Regulatory Commission, 2024, pp.1. 14 United States Nuclear Regulatory Commission. In: Rulemaking Plan on Use of Increased Enrichment of Conventional and Accident Tolerant Fuel Designs for Light-Water Reactors. United States, 2022, pp.1. 15 Nuclear Regulatory Commission Staff Organization. Project plan to prepare the U.S. Nuclear Regulation Commision for efficient and effective licensing of accident tolernat fuels, United States Nuclear Regulatory Commission, 2021, pp.35. 16 Yan J, Liao Y, Peng Z, et al. Surface Technology, 2023, 52(12), 206(in Chinese). 严俊, 廖业宏, 彭振驯, 等. 表面技术, 2023, 52(12), 206. 17 Duan Z G, Chen P, Zhou Y, et al. Nuclear Techniques, 2022, 45(3), 3(in Chinese). 段振刚, 陈平, 周毅, 等. 核技术, 2022, 45(3), 3. 18 Pang H, Xin Y, Yue H F, et al. Materials Reports, 2022, 36(4), 5(in Chinese). 庞华, 辛勇, 岳慧芳, 等. 材料导报, 2022, 36(4), 5. 19 Ikatsu N, Itagaki N, Ohira K, et al. In: Proceedings of the Technical Committee. Sweden, 1998, pp.177. 20 Noirot J, Desgranges L, Lamontagne J. Journal of Nuclear Materials, 2008, 372, 318. 21 Rest J, Cooper M W D, Spino J, et al. Journal of Nuclear Materials, 2019, 513, 310. 22 Wiesenack W. Nuclear Engineering and Dseign, 1997, 172, 83. 23 Avera. U. S. EPR Final safety analysis report, Revision 4, pp.4.2-1. 24 Yilmazbayhan A. Microstructural basis of uniform corrosion in zirconium alloys. Ph. D. Thesis, The Pennsylvania State University, USA, 2004. 25 Motta A T, Couet A, Comstock R J. Annual Review of Materials Research, 2015, 45, 311. 26 Couet A, Motta A T, Comstock R J. Journal of Nuclear Materials, 2014, 451, 1. 27 United States Nuclear Regulatory Commission. Determining post quench ductility, United States Nuclear Regulatory Commission, 2014, pp.A-14. 28 United States Nuclear Regulatory Commission. Expanded Post Quench Ductility (PQD) Empirical Database, 2009, pp.1. 29 Bales M, Chung A, Corson A, et al. Interpretation of research on fuel fragmentation, relocation, and dispersal at high burnup, United States Nuclear Regulatory Commission, 2021, pp.2. 30 Exelon Generation Company (USA). Supplement #3 to license amendment request to utilize accident, United States Nuclear Regulatory Commission, 2019, pp.1. 31 Dumerval M, Houmaire Q, Brachet J C, et al. In:Conference Record of the Topfuel 2018. Prague, 2018. 32 Brachet J C, Saux M L, Lomello F, et al. In:Conference Record of the Topfuel 2016. Boise, 2016. 33 Wang Z W, Yan J, Peng Z X, et al. Nuclear Power Engineering, 2023, 44(2), 122(in Chinese). 王占伟, 严俊, 彭振驯, 等. 核动力工程, 2023, 44(2), 122. 34 Backman K, Hallstaius L. In:IAEA Technical Meeting on Advanced Fuel Pellet Materials and Fuel Rod Designs for Water Cooled Reactors. Vienna, 2009. 35 Che Y, Pastore G, Hales J, et al. Nuclear Engineering and Design, 2018, 337, 271. |
|
|
|