二氧化铀粉末运输容器临界安全分析

焦力敏, 王智鹏, 张沛东, 郝嘉欣, 陈磊, 孙谦, 王长武, 庄大杰

包装工程(技术栏目) ›› 2025, Vol. 46 ›› Issue (21) : 326-331.

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包装工程(技术栏目) ›› 2025, Vol. 46 ›› Issue (21) : 326-331. DOI: 10.19554/j.cnki.1001-3563.2025.21.035
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二氧化铀粉末运输容器临界安全分析

  • 焦力敏, 王智鹏, 张沛东, 郝嘉欣, 陈磊, 孙谦, 王长武, 庄大杰
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Criticality Safety Analysis of Uranium Dioxide Powder Transport Container

  • JIAO Limin, WANG Zhipeng, ZHANG Peidong, HAO Jiaxin, CHEN Lei, SUN Qian, WANG Changwu, ZHUANG Dajie
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摘要

目的 临界安全是设计易裂变核材料UO2粉末运输容器时需考虑的重点,需要对其在正常运输和运输事故条件下容器的临界安全进行分析,确保容器的设计符合相应法规和标准对临界安全的要求。方法 基于国际临界安全手册中与本案例类似的实验案例,利用蒙特卡罗方法计算本案例的次临界限值,并对孤立货包和阵列货包在正常运输和运输事故条件下的反应性进行计算。结果 经计算,孤立货包在正常运输和运输事故条件下的最大有效增值系数为0.300 70,阵列货包在正常运输和运输事故条件下的最大有效增值系数为0.543 20。结论 二氧化铀粉末运输容器在正常运输和运输事故下的反应性均小于次临界限值,其临界安全指数(CSI)为0,表明此容器设计满足要求。

Abstract

Criticality safety is a primary concern in designing transport containers for fissile UO2 powder. Therefore, it is necessary to analyze the criticality safety of containers under both normal conditions and accident scenarios during transport, ensuring that the design complies with all applicable regulatory and standard requirements for criticality safety. Based on experimental cases from the International Handbook of Criticality Safety similar to the case at hand, the Monte Carlo method was employed to calculate the subcritical limit for this case. Reactivity calculations were then performed for both single and array packages under normal and accident conditions during transport. The maximum keff of the single package was 0.303 87 under normal transport and accident conditions, while that of the array package was 0.543 20. The reactivity of the uranium dioxide powder transport container is below the subcritical limit under both normal and accident conditions and its Criticality Safety Index (CSI) is 0, meeting the design requirements.

关键词

放射性物品运输 / 二氧化铀粉末 / 运输容器 / 临界安全

Key words

radioactive material transport / uranium dioxide powder / transport container / criticality safety

引用本文

导出引用
焦力敏, 王智鹏, 张沛东, 郝嘉欣, 陈磊, 孙谦, 王长武, 庄大杰. 二氧化铀粉末运输容器临界安全分析[J]. 包装工程. 2025, 46(21): 326-331 https://doi.org/10.19554/j.cnki.1001-3563.2025.21.035
JIAO Limin, WANG Zhipeng, ZHANG Peidong, HAO Jiaxin, CHEN Lei, SUN Qian, WANG Changwu, ZHUANG Dajie. Criticality Safety Analysis of Uranium Dioxide Powder Transport Container[J]. Packaging Engineering. 2025, 46(21): 326-331 https://doi.org/10.19554/j.cnki.1001-3563.2025.21.035
中图分类号: TB485.3   

参考文献

[1] 杨海涛, 刘小龙, 卢长先, 等. ADU粉末比表面积控制工艺研究[J]. 铀矿冶, 2022, 41(4): 401-405.
YANG H T, LIU X L, LU C X, et al.Study on Specific Surface Area Control Technology of ADU Powder[J]. Uranium Mining and Metallurgy, 2022, 41(4): 401-405.
[2] 中华人民共和国生态环境部. 放射性物品安全运输规程: GB/T 11806—2019[S]. 北京: 中国标准出版社, 2019.
Regulations for the Safe Transport of Radioactive Material: GB/T 11806-2019[S]. Beijing: Standards Press of China, 2019.
[3] Regulations for the Safe Transport of Radioactive Material: SSR-6[S]. Vienna: International Atomic Energy Agency, 2018.
[4] Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material: SSG-26[S]. Vienna: International Atomic Energy Agency, 2018.
[5] 庄大杰, 孙洪超, 孙树堂, 等. UO2芯块运输容器核临界安全分析[J]. 包装工程, 2022, 43(11): 168-173.
ZHUANG D J, SUN H C, SUN S T, et al.Nuclear Criticality Safety Analysis for the UO2 Pellets Transport Container[J]. Packaging Engineering, 2022, 43(11): 168-173.
[6] 贾晓淳. 中国先进研究堆新燃料组件运输的临界安全分析[J]. 同位素, 2022, 35(6): 513-518.
JIA X C.Criticality Safety Analysis on the Fuel Assembly Transportation of China Advanced Research Reactor[J]. Journal of Isotopes, 2022, 35(6): 513-518.
[7] 王学新, 庄大杰, 曹芳芳, 等. AP1000新燃料组件运输货包的临界安全计算[J]. 辐射防护, 2014, 34(2): 97-101.
WANG X X, ZHUANG D J, CAO F F, et al.Criticality Safety Analysis to Transport Package of Intact AP1000 Fuel Assembly[J]. Radiation Protection, 2014, 34(2): 97-101.
[8] 李颖虹, 黄灏, 周荣生, 等. 高温气冷堆新燃料元件运输容器临界安全分析[J]. 核动力工程, 2019, 40(6): 64-71.
LI Y H, HUANG H, ZHOU R S, et al.Criticality Safety Calculation and Analysis of Fresh Fuel Element Transport Containers for High Temperature Gas-Cooled Reactor[J]. Nuclear Power Engineering, 2019, 40(6): 64-71.
[9] 叶佳佳, 陈灵芝. 压水堆乏燃料包装容器临界安全计算[J]. 江西化工, 2019, 35(4): 51-53.
YE J J, CHEN L Z.The Criticality Safety Calculation of Spent Fuel Packaging Containers for PWR[J]. Jiangxi Chemical Industry, 2019, 35(4): 51-53.
[10] 张敏, 王婧, 洪哲, 等. CNSC乏燃料组件运输容器临界安全分析[J]. 核技术, 2020, 43(3): 41-46.
ZHANG M, WANG J, HONG Z, et al.Criticality Safety Analysis of CNSC Spent Fuel Assembly Transport Container[J]. Nuclear Techniques, 2020, 43(3): 41-46.
[11] 曹攀, 周科源, 张强, 等. CEFR-MOX新燃料组件运输货包临界安全计算[J]. 辐射防护, 2019, 39(2): 89-94.
CAO P, ZHOU K Y, ZHANG Q, et al.Criticality Safety Analysis on Transport Package of Fresh CEFR-MOX Fuel Assembly[J]. Radiation Protection, 2019, 39(2): 89-94.
[12] 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.
[13] 李天玉, 张宇航. 干法UO2粉末松装密度和振实密度的影响因素研究[C]// 中国核科学技术进展报告(第6卷)——中国核学会2019年学术年会论文集第6册(核化工分卷、辐射防护分卷), 2019: 130-137.
LI T Y, ZHANG Y H.Influencing Factors of Bulk Density and Tapped Density of Dry UO2 Powder[C]// Report on the Progress of Nuclear Science and Technology in China (Vol.6)-Volume 6 of Collected Papers of Academic Annual Conference of Chinese Nuclear Society in 2019 (for Nuclear Chemical Engineering and Radiation Protection), 2019: 130-137.
[14] 国家国防科技工业局. 反应堆外易裂变材料的核临界安全第 2 部分: 易裂变材料操作、加工、处理的基本技术准则与次临界限值: GB/T 15146.2—2008[S]. 北京: 中国标准出版社, 2008.
Nuclear Criticality Safety for Fissile Materials Outside Reactors-Part 2: Basic Technical Practices and Subcritical Limits for Handing, Processing and Operations with Fissile Materials: GB/T 15146.2-2008[S]. Beijing: Standards Press of China, 2008.
[15] 周琦, 夏兆东, 成昱廷, 等. 铀溶液多体系统核临界安全实验不确定度分析与基准化[J]. 原子能科学技术, 2024, 58(6): 1319-1326.
ZHOU Q, XIA Z D, CHENG Y T, et al.Uncertainty Analysis and Benchmark for Nuclear Criticality Safety Experiment about Uranium Solution Multiple-Unit System[J]. Atomic Energy Science and Technology, 2024, 58(6): 1319-1326.
[16] BRIGGS J B.The Activities of the International Handbook of Evaluated Project(ICSBEP)[J]. Journal of Nuclear Science & Technology, 2014, 30(2): 1427-1432.

基金

中国辐射防护研究院青年基金(YQ24000517)

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