Measurement of absorbed dose distributions in a plastic phantom irradiated by 40- and 65-MeV quasi-monoenergetic neutrons
Measurement of absorbed dose distributions in a plastic phantom irradiated by 40- and 65-MeV quasi-monoenergetic neutrons
复制标题
测量 40 MeV 和 65 MeV 准单能中子辐照的塑料体模中吸收剂量分布
DOI：
10.1016/s0168-9002(00)01022-6
复制
发表时间：
2001
影响因子：
1.4
通讯作者：
Y. Sakamoto
中科院分区：
文献类型：
--
作者：
Y. Nakane;Y. Sakamoto
为了验证用于加速器辐射屏蔽设计的剂量评估方法，用组织等效正比计数器和组织等效电离室测量了40 MeV和65 MeV准单能中子在30×30×30 cm~3平板塑料体模中的吸收剂量分布。用蒙特卡罗程序HETC-3STEP和MORSE-CG/KFA计算了带电粒子能量沉积和中子能谱的分布，并与实测值进行了比较。结果表明，本文所采用的计算方法适用于中能中子吸收剂量估算，具有较高的精度。
In order to validate dose evaluation methods for radiation shielding design of accelerator facilities, absorbed dose distributions in a plastic phantom of 30×30×30cm3slab were measured for 40- and 65-MeV quasi-monoenergetic neutrons with a tissue-equivalent proportional counter and a tissue-equivalent ionization chamber. The measured distributions were compared with the calculated ones from the energy deposition of charged particles and neutron energy spectra by using the Monte Carlo codes, HETC-3STEP and MORSE-CG/KFA, respectively. As a result, it was revealed that the calculation method used in the present work was applicable to absorbed dose evaluation for intermediate energy neutrons with high accuracy.