首页> 中文期刊> 《核电子学与探测技术》 >压水堆乏燃料运输容器对工作人员的辐射剂量计算

压水堆乏燃料运输容器对工作人员的辐射剂量计算

         

摘要

Based on the basic parameter of NAC-STC spent fuel transport container, the model of spent fuel transport container , 17 ×17 spent fuel component of pressurized water reactor and simple mannequin, is con-structed by MCNP code, and the equivalent dose of motorman and worker is calculated respectively.Results show that equivalent dose of motorman whose distance from spent fuel transport container impact limiter to him-self is one meter is 1.82 mSv/a, that equivalent dose of worker whose distance from spent fuel transport con-tainer center to himself is two meters is 1 .78 mSv/a, which is smaller than the limit of dose level 20 mSv/a which stipulate by ( GB18871 -2002 ) Ionization Radiation Protect and Radioactive Source Basic Standard. Therefore, NAC-STC spent fuel transport container can meet the requirement of radiation shield and safety. The calculated results will provide a reference for radiated dose evaluation of worker who irradiated by artificial radioactive source.%根据NAC-STC型乏燃料运输容器基本参数,用MCNP程序构建乏燃料运输容器、17×17压水堆乏燃料组件和简单人体模型;分别对乏燃料运输容器卡车司机和侧旁工作人员的当量剂量进行计算。计算结果表明:距乏燃料运输容器前端木质减震器1 m处的司机当量剂量为1.82 mSv/a,距乏燃料运输容器侧面2米处侧旁工作人员的当量剂量为1.78 mSv/a,均小于(GB18871-2002)《电离辐射防护与辐射源安全基本标准》规定的放射性工作人员剂量水平限值20 mSv/a,乏燃料运输容器能够满足辐射屏蔽与安全的要求。计算结果将为受人工放射源照射的工人辐射剂量评估提供参考。

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