Atanackovic J
Chalk River Laboratories, AECL Dosimetry Services, Chalk River, Ontario, Canada.
Radiat Prot Dosimetry. 2012 Jun;150(2):223-30. doi: 10.1093/rpd/ncr389. Epub 2011 Oct 13.
Three alpha volume sources (low-enriched uranium-U(3)Si) were analysed using Monte Carlo modelling in order to calculate the dose delivered to the dermis from a small embedded fuel fragment (sliver). Three shapes were analysed using MCNPX 2.6.0 code: sphere, cylinder and parallelepiped. Essentially, two kinds of runs were performed: count rate run and dosimetry run. The two results were combined to estimate dose coefficients that can be used for alpha dose assessments in the field. The two results were obtained for the 1 and 0 cm counting geometries. These results are very stable and show that the actual dose delivered to the skin per unit count rate for the recovered particle is independent of the shape of the volume alpha source.
使用蒙特卡罗建模分析了三个α体积源（低浓铀-U(3)Si），以计算从小的嵌入燃料碎片（薄片）传递到真皮的剂量。使用MCNPX 2.6.0代码分析了三种形状：球体、圆柱体和平行六面体。基本上，进行了两种运行：计数率运行和剂量测定运行。将这两个结果结合起来以估计可用于现场α剂量评估的剂量系数。这两个结果是针对1厘米和0厘米计数几何结构获得的。这些结果非常稳定，表明回收粒子每单位计数率传递到皮肤的实际剂量与体积α源的形状无关。
