轻量化乏燃料运输容器的设计研究

贺俨; 刘兆阳

doi:10.19554/j.cnki.1001-3563.2026.13.005

PDF(8333 KB)

包装工程（技术栏目） ›› 2026, Vol. 47 ›› Issue (13) : 37-45. DOI: 10.19554/j.cnki.1001-3563.2026.13.005

复杂辐射场下多场景辐射防护与屏蔽技术

轻量化乏燃料运输容器的设计研究

贺俨, 刘兆阳^*

作者信息 +

Design of Lightweight Spent Fuel Transport Casks

HE Yan, LIU Zhaoyang^*

Author information +

文章历史 +

摘要

目的针对乏燃料运输容器重量大、运输效率低的问题,设计了一种多层夹芯结构的乏燃料运输容器。方法以临界与屏蔽要求为基础、力学与热工要求为约束的方法进行轻量化设计,将货包总质量控制在限值内,通过数值计算对容器开展安全分析,并结合货包跌落试验及耐热试验对计算分析进行验证。结果经过试验验证,运输容器的数值计算结果与试验结果相吻合。结论结果表明运输容器安全性能能够满足GB 11806对B(U)F型Ⅲ级黄货包的要求,能够在满足重量限制的条件下对乏燃料进行安全运输。

Abstract

The work aims to design a spent fuel transport cask with a multi-layer sandwich structure to solve the problems of heavy weight and low transportation efficiency of spent fuel transport casks. Lightweight design was carried out on the basis of criticality and shielding requirements, with mechanical and thermal requirements as constraints to control the total package mass within the limit. Safety analysis of the cask was conducted through numerical calculation, and the calculation analysis was verified by package drop tests and heat resistance tests. The numerical calculation results of the transport cask were consistent with the test results through test verification. The results show that the safety performance of the transport cask can meet the requirements of GB 11806 for Type B(U)F Category Ⅲ yellow packages, and it can safely transport spent fuel under the condition of meeting the weight limit.

导出引用

贺俨, 刘兆阳. 轻量化乏燃料运输容器的设计研究[J]. 包装工程. 2026, 47(13): 37-45 https://doi.org/10.19554/j.cnki.1001-3563.2026.13.005

HE Yan, LIU Zhaoyang. Design of Lightweight Spent Fuel Transport Casks[J]. Packaging Engineering. 2026, 47(13): 37-45 https://doi.org/10.19554/j.cnki.1001-3563.2026.13.005

中图分类号： TB485.3

参考文献

[1] 中华人民共和国生态环境部.放射性物品安全运输规程: GB 11806—2019[S]. 北京:中国环境科学出版社, 2019.
Ministry of Ecology and Environment of the People’s Republic of China. Regulations for the Safe Transport of Radioactive Materials: GB 11806-2019[S]. Beijing: China Environmental Science Press, 2019.
[2] 中华人民共和国国家核安全局. GB/T41024—2021乏燃料运输容器结构分析的载荷组合和设计准则[S]. 北京: 中国标准出版社, 2021.
State Nuclear Safety Administration of the People’s Republic of China. GB/T 41024-2021, Load Combinations and Design Criteria for Structural Analysis of Spent Fuel Transport Casks[S]. Beijing: Standards Press of China, 2021.
[3] 中华人民共和国生态环境部.乏燃料运输容器设计要求: HJ1355—2024[S]. 北京: 中国环境科学出版社, 2024.
Ministry of Ecology and Environment of the People’s Republic of China. Design Requirements for Spent Fuel Transport Casks: HJ 1355-2024[S]. Beijing: China Environmental Science Press, 2024.
[4] 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.
[5] 张白茹, 李馨楠, 姚琳. 乏燃料干法贮存密封贮存罐设计及关键技术分析[J]. 包装工程, 2025, 46(1): 273-278.
ZHANG B R, LI X N, YAO L.Analysis on Design and Key Technologies of Dry Storage Canister for Spent Fuel under Dry Storage[J]. Packaging Engineering, 2025, 46(1): 273-278.
[6] 李宁, 张洪军, 徐小刚. CNFC-HTR新燃料运输容器结构设计与验证[J]. 科技视界, 2016, 6(8): 204-205.
LI N, ZHANG H J, XU X G.Structural Design and Verification of the CNFC-HTR New Fuel Transport Container[J]. Science&Technology Vision, 2016, 6(8): 204-205.
[7] 刘兆阳, 曹健, 李晓轩, 等. 快堆MOX元件运输容器的缓冲器研究[J]. 原子能科学技术, 2018, 52(8): 1468-1473.
LIU Z Y, CAO J, LI X X, et al.Study of Impact Limiter for MOX Fuel Assembly Transportation Package of Fast Reactor[J]. Atomic Energy Science and Technology, 2018, 52(8): 1468-1473.
[8] IKUSHIMA T.Handbook for Structural Analysis of Radioactive Material Transport Casks: JAERI-M--91-060[R]. Ibaraki, Japan: Japan Atomic Energy Research Institute, 1991.
[9] SHAPPERT L B, WANGLER M E.The Radioactive Materials Packaging Handbook: Design, Operations, and Maintenance[M]. Oak Ridge: Oak Ridge National Laboratory, 1998.
[10] CHURCHILL S W, CHU H H S. Correlating Equations for Laminar and Turbulent Free Convection from a Vertical Plate[J]. International Journal of Heat and Mass Transfer, 1975, 18(11): 1323-1329.
[11] LIN C W, TSENG Y S, LIN K Q, et al.A Numerical Investigation of an Indoor Dry Storage Facility on Heat Transfer[J]. Annals of Nuclear Energy, 2024, 196: 110225.
[12] 李精精, 刘梦影, 桂重. 压水堆24P乏燃料运输容器热工安全分析研究[J]. 包装工程, 2024, 45(21): 62-68.
LI J J, LIU M Y, GUI Z.Thermal Analysis of PWR 24P Spent Fuel Transport Cask[J]. Packaging Engineering, 2024, 45(21): 62-68.
[13] BOILER A, Pressure Vessel Committee on Construction of Nuclear Facility Components. Rules for Construction of Nuclear Facility Components, Part III Division 5. High Temperature Reactors[M]. New York, NY: The American Society of Mechanical Engineers, 2015.
[14] 张振雨, 陈孟, 庄小东, 等. 二氧化铀粉末运输容器假想跌落事故下的安全设计与试验验证[J]. 包装工程, 2024, 45(1): 273-280.
ZHANG Z Y, CHEN M, ZHUANG X D, et al.Safety Design and Test Verification of Uranium Dioxide Powder Transport Container under Imaginary Drop Accident[J]. Packaging Engineering, 2024, 45(1): 273-280.
[15] 谢季佳, 杜柔. 筒体材料本构关系拟合报告[R]. 北京: 中国科学院力学研究所, 2019.
XIE J J, DU R.Fitting Report on Constitutive Relation of Cylinder Material[R]. Beijing: Institute of Mechanics, Chinese Academy of Sciences.
[16] 陈磊, 孙谦, 荣誉, 等. 乏燃料运输容器安全验证试验报告[R]. 太原: 中国辐射防护研究院, 2025.
CHEN L, SUN Q, RONG Y, et al.Safety Verification Test Report on Spent Fuel Transport Cask[R]. Taiyuan: China Institute for Radiation Protection, 2025.