钴源辐照室防护屏蔽计算方法的比较研究  

Comparison study on different shielding calculation methods used in a cobalt source irradiation room

作　　者：李春松 姜文华[2] 廖爱莲 

机构地区：[1]北京三强核力辐射工程技术有限公司,北京100086 [2]环境保护部核与辐射安全中心,北京100082

出　　处：《辐射研究与辐射工艺学报》2017年第3期52-57,共6页Journal of Radiation Research and Radiation Processing

摘　　要：采用MCNP(Monte Carlo N particle transport code)程序和经验公式两种方法进行^(60)Co源辐照室的防护屏蔽计算,分析不同方法所得的辐照室外以及迷道内受照剂量率的变化情况。结果表明:从辐射防护最优化、土建经济性及实际测量等角度考虑,经验公式法的贯穿辐射计算结果偏保守;而迷道散射计算中,经验公式法方便省时,尤其是在迷道结构复杂的情况下计算,比MCNP快捷。MCNP （Monte Carlo N particle transport code） and the empirical equation were used for shielding calculation of a 6~Co irradiation room, The absorbed dose rates obtained outside the irradiation room and inside a maze were studied. The calculation results of the penetrating radiation using an empirical equation was obviously bigger than that of actual measurement and would increase the construction costs. The calculation results of maze scattering showed that the empirical equation was a convenient and time-saving method, and the calculation was especially quick and easy when the maze was complex.

关 键 词：MCNP 经验公式 屏蔽计算 

分 类 号：TL77[核科学技术—辐射防护及环境保护]