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2.47 mSv/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.%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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