| 乏燃料干式贮存设施辐射屏蔽计算 |
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| 引用本文： | 洪哲,赵善桂,于婷,何玮,刘新华. 乏燃料干式贮存设施辐射屏蔽计算[J]. 核化学与放射化学, 2017, 39(6): 431-436. DOI: 10.7538/hhx.2017.39.06.0431 |
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| 作者姓名： | 洪哲 赵善桂 于婷 何玮 刘新华 |
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| 作者单位： | 1.环境保护部 核与辐射安全中心,北京100082;2.中国原子能科学研究院 放射化学研究所,北京102413 |
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| 摘 要： | 以干式贮存设施内部装载32组不同初始富集度、不同燃耗的乏燃料组件为研究对象,用MCNP程序,计算了不同冷却时间、不同位置处的中子剂量、γ剂量和总剂量,结果表明,随着冷却时间的延长,γ剂量率、中子剂量率和总的剂量率均在逐步减小。总的辐射剂量最大值出现在贮存设施表面活性段的中部,最大辐射剂量率约为2.47mSv/h,相当于核电厂辐射分区的高辐射区,应限制进入。为满足保护工作人员和公众所受剂量尽量低的要求,建议采取相关的措施例如增加屏蔽层厚度或者划定控制区域等,限制人员的进入。
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| 关 键 词： | 干式贮存 屏蔽安全 辐射 乏燃料 |
Calculation on Shielding of Dry Storage Facilities for Spent Fuel |
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| HONG Zhe,ZHAO Shan-gui,YU Ting,HE Wei,LIU Xin-hua. Calculation on Shielding of Dry Storage Facilities for Spent Fuel[J]. Journal of Nuclear and Radiochemistry, 2017, 39(6): 431-436. DOI: 10.7538/hhx.2017.39.06.0431 |
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| Authors: | HONG Zhe ZHAO Shan-gui YU Ting HE Wei LIU Xin-hua |
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| Affiliation: | 1.Nuclear and Radiation Safety Center, Ministry of Environmental Protection of the People’s Republic of China, Beijing 100082, China; 2.China Institute of Atomic Energy, P. O. Box 275(26), Beijing 102413, China |
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| Abstract: | The research object is HI-STORM 100 spent fuel dry storage facility internal loading AFA-3G fuel assembly in this paper. Using the MCNP (Monte Carlo N Particle Transport Code) code, neutron dose, γ dose and total dose were calculated under different conditions, such as cooling time, locations. Results show that the value of gamma dose rate, neutron dose rate and total dose rate reduce gradually with the extension of the cooling time. The maximum radiation dose rate is about 2.47 mSv/h. So it is a high radiation area that should not be entered. In order to meet the purpose of as low as reasonably achievable, it is recommended to take relevant measures such as increasing the thickness of shielding, or setting up control areas, etc. |
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