Monte Carlo simulation of biological shielding parameters in PGNAA

Monte Carlo simulation of biological shielding parameters in PGNAA
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PGNAA 中生物屏蔽参数的蒙特卡罗模拟

DOI:
10.1049/mnl.2017.0644
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发表时间:
2018
影响因子:
1.3
通讯作者:
Li Zhe
Li Zhe
中科院分区:
材料科学4区
文献类型:
--
作者:
Yang Jianbo;Peng Kexin;Qiao Yujie;Zhang Can;Li Rui;Li Zhe

文献摘要

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进行了基于252Cf自发裂变中子的瞬发γ中子活化分析(PGNAA)设施,最终目标是获得各种优化的辐射防护设计参数。采用MCNP蒙特卡罗程序模拟样品室两侧铅(Pb)屏蔽厚度,选择B4C、B2O3、LiOH、LiF和硼砂作为中子吸收材料进行模拟,以确定生物多层复合材料屏蔽优化设计的最佳参数。利用MCNP程序进行的一系列计算表明,生物屏蔽的5 cm厚的Pb最内层快速还原快中子,并选择25 cm厚的石蜡、20 mm厚的硼砂和2 mm厚的B4C作为中子吸收材料。计算得到的生物屏蔽防护参数满足实验中使用的PGNAA设施的要求。
A promptγneutron activation analysis (PGNAA) facility based on a252Cf spontaneous fission neutron was performed with the final goal of obtaining various optimised radiation protection design parameters. MCNP Monte Carlo code was used to simulate the lead (Pb) shield thickness on two sides of the sample chamber, and B4C, B2O3, LiOH, LiF, and borax were selected as neutron‐absorbing materials that were simulated to determine optimal parameters for the optimal design of a biological multilayer composite shield. A series of calculations performed with the MCNP code indicated that the 5 cm thick Pb innermost layer of a biological shield rapidly reduced fast neutrons, and a moderation layer of 25 cm thick paraffin, 20 mm thick borax, and 2 mm thick B4C were selected as neutron‐absorbing materials. The calculated biological shield protection parameters satisfied the requirements of the PGNAA facility used in the experiment.