Calculations of neutron shielding data for 10-100 MeV proton accelerators.
Calculations of neutron shielding data for 10-100 MeV proton accelerators.
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10-100 MeV 质子加速器的中子屏蔽数据计算。
DOI:
10.1093/rpd/nci193
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发表时间:
2005
影响因子:
1
通讯作者:
S. Jian
中科院分区:
文献类型:
--
作者:
C. C. Chen;R. Sheu;S. Jian
The characteristics of neutron sources and their attenuation in concrete were investigated in detail for protons with energies ranging from 10 to 100 MeV striking on target materials of C, N, Al, Fe, Cu and W. A two-step approach was adopted: thick-target double-differential neutron yields were first calculated from the (p, xn) cross sections recommended in the ICRU Report 63; further, transport simulations of those neutrons in concrete were performed by using the FLUKA Monte Carlo code. The purpose of this study is to provide reasonably accurate parameters for shielding design for 10-100 MeV proton accelerators. Source terms and the corresponding attenuation lengths in concrete for several target materials are given as a function of proton energies and neutron emission angles.