Safety performance of HTR-PM600 fresh fuel storage canister under drop impact
HAO Yuchen, WANG Jinhua, WANG Haitao, LIU Bing, LI Yue
Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China
Abstract:Fresh fuel storage container is key equipment in the fuel storage system in nuclear power plants.During hoisting,it may fall directly to the ground,thus damaging the canister and leaking the fuel element due to mechanical failure.Therefore,the safety performance of a fresh fuel storage container must be verified under the drop impact.In this paper,the HTR-PM600 fresh fuel storage canister is selected as the objective,and the FEM-DEM coupling method is used to simulate the movement law of the pebble bed.Subsequently,the maximum damage to the fuel storage canister under an accidental drop impact is calculated.The result shows that the containment boundary of the new fuel storage canister will not be destroyed under the 15-m drop condition,and the floor will not be penetrated;thus,the structural design meets the safety requirements.Under impact loading,the side plate of the thin-wall canister has a 35.26-mm expansion in the radial direction due to the interface force from the pebble bed.The maximum interaction force between the fuel element and the containment boundary is 6.295 kN,far less than the crush strength of the HTR-PM fuel element.
郝予琛, 王金华, 王海涛, 刘兵, 李悦. HTR-PM600新燃料贮存容器跌落冲击安全性能[J]. 清华大学学报(自然科学版), 2022, 62(10): 1668-1674.
HAO Yuchen, WANG Jinhua, WANG Haitao, LIU Bing, LI Yue. Safety performance of HTR-PM600 fresh fuel storage canister under drop impact. Journal of Tsinghua University(Science and Technology), 2022, 62(10): 1668-1674.
[1] 清华新闻网.华能石岛湾高温气冷堆示范工程并网发电[N/OL].(2021-12-21). https://www.tsinghua.edu.cn/info/1182/90247.htm. Tsinghua NEWS. China Huaneng starts 200 MW gas-cooled nuclear reactor in China[N/OL].(2021-12-21). https://www.tsinghua.edu.cn/info/1182/90247.htm.(in Chinese) [2] ZHANG Z Y, DONG Y J, LI F, et al. The Shandong Shidao Bay 200 MWe high-temperature gas-cooled reactor pebble-bed module (HTR-PM) demonstration power plant:An engineering and technological innovation[J]. Engineering, 2016, 2(1):112-118. [3] 徐超.基于安全分析的乏燃料运输容器关键技术研究[D].杭州:浙江大学, 2012. XU C. Research on the key technologies of safety design for spent fuel transportation cask[D]. Hangzhou:Zhejiang University, 2012.(in Chinese) [4] 杨星团,刘志勇,胡文平,等. HTR-10堆芯球流运动的唯象学DEM模拟[J].原子能科学技术, 2013, 47(12):2231-2237. YANG X T, LIU Z Y, HU W P, et al. DEM simulation of pebble flow in HTR-10 core by phenomenological method[J]. Atomic Energy Science and Technology, 2013, 47(12):2231-2237.(in Chinese) [5] 王文俊,姜胜耀,杨星团,等.二维双区球流运动唯象方法的数值模拟[J].原子能科学技术, 2013, 47(10):1713-1717. WANG W J, JIANG S Y, YANG X T, et al. Numerical simulation on pebble dynamics of two-dimensional two-region pebble-bed reactor using phenomenological method[J]. Atomic Energy Science and Technology, 2013, 47(10):1713-1717.(in Chinese) [6] LIN M S, WANG J H, WU B, et al. Dynamic analysis of dry storage canister and the spent fuels inside under vertical drop in HTR-PM[J]. Annals of Nuclear Energy, 2021, 154:108030. [7] 刘翔. HTR-PM乏燃料贮罐跌落工况的安全性分析与计算[D].北京:清华大学, 2015. LIU X. The theoretical and computational analysis for the drop events of HTR-PM spent fuel storage canister[D]. Beijing:Tsinghua University, 2015.(in Chinese) [8] American Society of Mechanical Engineers. Section II:Materials:2015 ASME boiler and pressure vessel code an international code:Part D properties (customary)[R]. New York:The American Society of Mechanical Engineers, 2015. [9] 中华人民共和国国家质量监督检验检疫总局,中国国家标准化管理委员会.紧固件机械性能不锈钢螺栓、螺钉和螺柱:GB/T 3098.6-2014[S].北京:中国标准出版社, 2015. General Administration of Quality Supervision, Inspection and Quarantine of the People's Republic of China, Standardi-zation Administration. Mechanical properties of fasteners:Stainless steel bolts, screws and studs:GB/T 3098.6-2014[S]. Beijing:Standards Press of China, 2014.(in Chinese) [10] USNRC. Stress analysis of closure bolts for shipping casks:NUREG/CR-6007[R]. Washington:USNRC, 1993. [11] Livermore Software Technology Corporation. LS-DYNA® keyword user's manual:Volume II:Material models[R]. Livermore:LSTC, 2019. [12] CUNDALL P A, STRACK O D L. Discussion:A discrete numerical model for granular assemblies[J]. Géotechnique, 1980, 30(3):331-336. [13] 孙其诚,王光谦.颗粒物质力学导论[M].北京:科学出版社, 2009. SUN Q C, WANG G Q. Introduction to discrete element method[M]. Beijing:Science Press, 2009.(in Chinese) [14] LIN M S, LI Y. Analysis of the interactions between spent fuel pebble bed and storage canister under impact loading[J]. Nuclear Engineering and Design, 2020, 361:110548. [15] KUGELER K, ZHANG Z Y. Modular high-temperature gas-cooled reactor power plant[M]. Berlin:Springer, 2019. [16] 国家能源局.核电厂厂房设计荷载规范:NB/T 20105-2012[S].北京:原子能出版社, 2012. National Energy Administration. Load code for the design of nuclear power plants building structures:NB/T 20105-2012[S]. Beijing:Atomic Energy Press, 2012.(in Chinese) [17] 中华人民共和国住房和城乡建设部.混凝土结构设计规范:GB 50010-2010[S].北京:中国建筑工业出版社, 2011. Ministry of Housing and Urban-Rural Development of the people's Republic of China. Code for design of concrete structures:GB 50010-2010[S]. Beijing:China Architecture&Building Press, 2011.(in Chinese)