Application of Monte Carlo method in the design of shielding scheme for cobalt source containers
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摘要: 采用蒙特卡罗方法,针对钴源容器的辐射安全性能进行了分析和验证,主要利用屏蔽容器主体、铅屏蔽层等结构实现其屏蔽功能,单根成品源不同的活度及摆放位置对钴源容器的屏蔽性能会产生影响,对比了各装载方案在不同角度剂量点的剂量率水平变化趋势,并通过MESH网格图直观反映人员可达平台的剂量率水平分布,分析结果验证了钴源容器满足国家标准GB 11806-2019《放射性物品安全运输规程》对货包辐射水平的规定,可达到其固有安全性。Abstract:
Background Radiation protection and the safety of radiation sources are critical in industrial applications. The Basic Standard for Protection against Ionizing Radiation and Safety of Radiation Sources is a key technical standard in China, establishing personal dose limits for occupational exposure and the public. Ensuring that the radiation dose from the transport of radioactive sources remains below these limits is essential. Cobalt-60 (60Co) sources are widely used in industrial applications, and their transport containers must provide adequate shielding to minimize radiation exposure.Purpose This study aims to evaluate and optimize the shielding performance of a cobalt source container to ensure compliance with national standards and to protect personnel during transportation. The research focuses on analyzing the shielding effectiveness under different loading configurations and verifying the container's performance against regulatory requirements.Methods The shielding analysis was conducted using the Monte Carlo method and MESH grid mapping. The study considered the activity of individual radioactive sources and their loading configurations, focusing on four eccentric loading schemes. The dose rate levels were analyzed at various angles, and MESH grids were used to visualize the spatial distribution of dose rates on accessible platforms.Results The analysis demonstrated that the cobalt source container meets the national standard (GB). The dose rate levels at different angles and positions were found to be consistent with regulatory limits. The MESH grid visualization provided a clear understanding of the dose rate distribution, confirming the container's shielding performance under the tested configurations.Conclusions The research validates the shielding effectiveness of the cobalt source container and provides a systematic approach for evaluating and optimizing shielding designs. The findings contribute to ensuring safe transport of radioactive sources and compliance with radiation protection standards.-
Key words:
- cobalt source container /
- radiation safety /
- Monte Carlo method /
- MESH analysis
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表 1 60Co成品源的γ源强
Table 1. γ Source Intensity of the Cobalt-60 Source
Energy/MeV γ source intensity/(photons·s−1) 0.6938 1.21E+12 1.1732 7.40E+15 1.3325 7.40E+15 Total source intensity 1.48E+16 表 2 四种布置方案的屏蔽分析结果(1/2)
Table 2. The Shielding Analysis Results of the Four Layout Schemes(1/2)
surface dose
rate/mSv∙hdose rate at 1 meter from
the outer surface/mSv∙hdose rate at 2 meters from
the outer surface/mSv∙htop bottom side top bottom side top bottom side Scheme 1 conventional transportation
condition2.37E-01 3.06E-01 7.06E-01 5.87E-02 2.18E-02 8.23E-02 2.00E-02 7.31E-03 2.94E-02 limiting value 2 2 2 − − − 0.1 0.1 0.1 scheme 2 conventional transportation
condition2.14E-01 4.81E-01 5.69E-01 5.15E-02 2.42E-02 6.55E-02 1.73E-02 8.16E-03 2.43E-02 limiting value 2 2 2 − − − 0.1 0.1 0.1 scheme 3 conventional transportation
condition2.69E-01 3.72E-01 4.81E-01 5.60E-02 2.20E-02 7.09E-02 1.90E-02 7.37E-03 2.54E-02 limiting value 2 2 2 − − − 0.1 0.1 0.1 scheme 4 conventional transportation
condition2.69E-01 4.37E-01 5.91E-01 5.38E-02 2.38E-02 7.06E-02 1.84E-02 7.81E-03 2.60E-02 limiting value 2 2 2 − − − 0.1 0.1 0.1 表 2 四种布置方案的屏蔽分析结果(2/2)
Table 2. The Shielding Analysis Results of the Four Layout Schemes (2/2)
Dose rate at 1 meter from the outer surface/mSv∙h Side Transport accident conditions 9.30E-02 Limiting value 10 Transport accident conditions 8.94E-02 Limiting value 10 Transport accident conditions 8.12E-02 Limiting value 10 Transport accident conditions 7.44E-02 Limiting value 10 -
[1] GB/T 7465-2015, 高活度钴60密封放射源[S]GB/T 7465-2015, High activity cobalt-60 sealed radioactive sources[S] [2] GB 18871-2002, 电离辐射防护与辐射源安全基本标准[S]GB 18871-2002, Basic STANDARDs for protection against ionizing radiation and for the safety of radiation sources[S] [3] GB 11806-2019, 放射性物品安全运输规程[S]GB 11806-2019, Regulations for the safe transport of radioactive material[S] [4] TEAM X. MCNP-A general Monte Carlo n-particle transport code, Version 5: LA-UR-03-1987[R]. Los Alamos Nuclear Laboratory, 2005. [5] 康崇禄. 蒙特卡罗方法理论和应用[M]. 北京: 科学出版社, 2015Kang Chonglu. Theory and application of Monte Carlo method[M]. Beijing: Science Press, 2015 [6] 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 doi: 10.13832/j.jnpe.2019.06.0064Li Yinghong, Huang Hao, Zhou Rongsheng, 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 doi: 10.13832/j.jnpe.2019.06.0064 [7] 田英男, 赵秋娟, 陈宗欢, 等. 高温气冷堆新燃料运输容器辐射安全分析[J]. 包装工程, 2024, 45(23): 318-324 doi: 10.19554/j.cnki.1001-3563.2024.23.035Tian Yingnan, Zhao Qiujuan, Chen Zonghuan, et al. Radiation safety analysis of a new fuel container for high temperature gas-cooled reactor[J]. Packaging Engineering, 2024, 45(23): 318-324 doi: 10.19554/j.cnki.1001-3563.2024.23.035 [8] 薛娜, 王炳衡, 毛亚蔚. 大容量钴源运输容器屏蔽研究[J]. 原子能科学技术, 2015, 49(7): 1298-1302 doi: 10.7538/yzk.2015.49.07.1298Xue Na, Wang Bingheng, Mao Yawei. Research on shielding of high-capacity cobalt source transport cask[J]. Atomic Energy Science and Technology, 2015, 49(7): 1298-1302 doi: 10.7538/yzk.2015.49.07.1298 [9] HAD 701-01, 放射性物品运输容器设计安全评价(分析)报告的标准格式和内容[S]HAD 701-01, Standard format and content of safety evaluation (analysis) report for the design of radioactive material transportation containers[S] [10] 曲泓宇, 陈珍平, 孙爱扣, 等. 蒙特卡罗MagicMC程序网格权窗全局减方差模块开发与验证[J]. 核电子学与探测技术, 2025, 45(4): 481-489 doi: 10.3969/j.issn.0258-0934.2025.04.006Qu Hongyu, Chen Zhenping, Sun Aikou, et al. Development and validation of the global variance reduction module with grid weight window based on the Monte Carlo MagicMC program[J]. Nuclear Electronics & Detection Technology, 2025, 45(4): 481-489 doi: 10.3969/j.issn.0258-0934.2025.04.006 [11] 邱有恒, 邓力, 李百文, 等. 基于MESH技术的伴随权重窗自动生成方法及其应用[J]. 原子能科学技术, 2014, 48(11): 2148-2152 doi: 10.7538/yzk.2014.48.11.2148Qiu Youheng, Deng Li, Li Baiwen, et al. Automatic generation method of MESH-based Adjoint weight window and its application[J]. Atomic Energy Science and Technology, 2014, 48(11): 2148-2152 doi: 10.7538/yzk.2014.48.11.2148 [12] 史涛, 马纪敏, 邱有恒, 等. 基于蒙特卡罗正算输运的全局减方差方法[J]. 强激光与粒子束, 2018, 30: 016006Shi Tao, Ma Jimin, Qiu Youheng, et al. Global variance reduction based on forward Monte Carlo Calculation[J]. High Power Laser and Particle Beams, 2018, 30: 016006 [13] 李国强, 庄大杰, 孙洪超, 等. FCTC10型工业辐照60Co运输容器屏蔽测量与评价[J]. 辐射防护, 2015, 35(4): 204-208Li Guoqiang, Zhuang Dajie, Sun Hongchao, et al. Shielding performance measurement and assessment for FCTC10 industrial cobalt-60 transport container[J]. Radiation Protection, 2015, 35(4): 204-208 [14] 刘慧芳, 张鑫. GY-20和GY-40型大容量钴-60运输容器关键技术研究[J]. 原子能科学技术, 2012, 46(s1): 749-752Liu Huifang, Zhang Xin. Key technology studies of GY-20 and GY-40 high-capacity Cobalt-60 transport casks[J]. Atomic Energy Science and Technology, 2012, 46(s1): 749-752 [15] 李春松, 姜文华, 廖爱莲. 钴源辐照室防护屏蔽计算方法的比较研究[J]. 辐射研究与辐射工艺学报, 2017, 35: 030601 doi: 10.11889/j.1000-3436.2017.rrj.35.030601Li Chunsong, Jiang Wenhua, Liao Ailian. Comparison study on different shielding calculation methods used in a cobalt source irradiation room[J]. Journal of Radiation Research and Radiation Processing, 2017, 35: 030601 doi: 10.11889/j.1000-3436.2017.rrj.35.030601 -
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