Neutron, proton, and photonuclear cross-sections for radiation therapy and radiation protection
Neutron, proton, and photonuclear cross-sections for radiation therapy and radiation protection
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用于放射治疗和辐射防护的中子、质子和光核截面
DOI：
10.1007/s004110050124
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发表时间：
1998
影响因子：
1.7
通讯作者：
M. Chadwick
中科院分区：
文献类型：
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作者：
M. Chadwick
我回顾了洛斯阿拉莫斯最近根据实验数据和核模型计算评估中子、质子和高达 150 MeV（质子为 250 MeV）的光核截面的工作。这些数据以 ENDF 格式表示，可用于计算机代码中来模拟辐射传输。它们允许计算治疗束在体内的吸收剂量，并通过使用比释动系数可以估计给定中子能量分布的吸收剂量。在辐射防护中，这些数据可用于确定加速器环境中的屏蔽要求并计算中子、质子、伽马射线和放射性核素的产生。给出了评估的横截面和比释动系数数据与测量值的说明性比较。
I review recent work at Los Alamos undertaken to evaluate neutron, proton, and photonuclear cross-sections up to 150 MeV (to 250 MeV for protons), based on experimental data and nuclear model calculations. These data are represented in the ENDF format and can be used in computer codes to simulate radiation transport. They permit calculations of absorbed dose in the body from therapy beams, and through use of kerma coefficients allow absorbed dose to be estimated for a given neutron energy distribution. In radiation protection, these data can be used to determine shielding requirements in accelerator environments and to calculate neutron, proton, gamma-ray, and radionuclide production. Illustrative comparisons of the evaluated cross-section and kerma coefficient data with measurements are given.