基于MCNP对γ射线吸收剂量累积因子的计算与研究

RADIATION PROTECTION ›› 2017, Vol. 37 ›› Issue (3): 161-168.

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Research on gamma ray buildup factor for energy absorption based on MCNP

Li Hua^1,2, Zhao Yuan¹, Liu Liye¹, Xiao Yunshi¹, Li Junli²

1. China Institute for Radiation Protection,Taiyuan 030006;
2. Department of Engineering Physics, Tsinghua University, Key Laboratory of Particle and Radiation Imaging, Ministry of Education, Key Laboratory of High Energy Radiation Imaging Fundamental Science, Beijing 100084

Received:2016-08-09 Online:2017-05-20 Published:2021-11-11

Abstract

Abstract: Energy absorption buildup factors of common materials were calculated using the Monte Carlo simulation code MCNP. In the calculations, the newer cross section library (MCPLIB04) and mass energy coefficients of common materials have been used with consideration of the bremsstrahlung and correlative scatter. The results were compared with the reference data and the differences were analyzed. It showed that, for the low-Z materials, the values of buildup factors calculated by MCNP were averagely smaller than the reference data for the intermediate γ energies, whilst the calculated values were averagely bigger than the reference data for the high γ energies. For high-Z materials, the calculated results of buildup factors were generally bigger than the reference data. This work could provide updated data for the old buildup factors.

Key words: buildup factor, MCNP, absorbed dose, point-kernel integral

CLC Number:

TL72

Li Hua, Zhao Yuan, Liu Liye, Xiao Yunshi, Li Junli. Research on gamma ray buildup factor for energy absorption based on MCNP[J].RADIATION PROTECTION, 2017, 37(3): 161-168.

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Research on gamma ray buildup factor for energy absorption based on MCNP

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