Calculations of neutron shielding data for 10-100 MeV proton accelerators.
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.
Chen
C C
CC
Department of Engineering and System Science, National Tsing Hua University, Hsinchu 300, Taiwan, Republic of China.
Sheu
R J
RJ
Jian
S H
SH
D003198:Computer Simulation; D003252:Construction Materials / Q000032:analysis*; D004867:Equipment Design; D019544:Equipment Failure Analysis; D018499:Linear Energy Transfer; D008422:Materials Testing; D015233:Models, Statistical; D009502:Neutrons; D010315:Particle Accelerators / Q000295:instrumentation*; D011522:Protons; D011829:Radiation Dosage; D011835:Radiation Protection / Q000295:instrumentation* / Q000379:methods; D011874:Radiometry / Q000379:methods*
D011522:Protons