The gamma-ray exposure doses in decontamination operation after a nuclear accident were evaluated with a consideration of various geometrical conditions and specific gamma-ray energies. The calculation domain is organized with three residence types and each form is divided into two kinds of geometrical arrangements. The position-wise air KERMA values were calculated with an assumption of evenly distributed gamma-ray source based on Monte Carlo radiation transport analysis using the MCNP code. The radioactivity is initially set to be unity to be multiplied by the deposition value measured in the actual accident condition. The workforce data set depending on the target object was determined by modifying the Fukushima report. The external exposure doses for decontamination workers were derived from the calculated KERMA values and the workforce analysis. These results can be used to efficiently determine the workforce required by the characteristics of the area and the structure to be decontaminated within the dose limits.

在考虑各种几何条件和特定伽马射线能量的情况下，对核事故后去污操作中的伽马射线照射剂量进行了评估。计算域以三种住宅类型组织，每种形式又分为两种几何排列。基于使用 MCNP 代码的蒙特卡罗辐射传输分析，假设伽马射线源均匀分布，计算位置方面的空气 KERMA 值。放射性最初设置为乘以在实际事故条件下测量的沉积值。取决于目标对象的劳动力数据集是通过修改福岛报告确定的。去污人员的外照射剂量来自计算的 KERMA 值和劳动力分析。这些结果可用于在剂量限制内有效地确定要净化的区域和结构特征所需的劳动力。