New calculations of neutron kerma coefficients and dose equivalent.
For neutron energies ranging from 1 keV to 20 MeV, the kerma coefficients for elements H, C, N, O, light water, and ICRU tissue were deduced respectively from microscopic cross sections and Monte Carlo simulation (MCNP code). The results are consistent within admitted uncertainties with values evaluated by an international group (Chadwick et al 1999 Med. Phys. 26 974-91). The ambient dose equivalent generated in the ISO-recommended neutron field for an Am-Be neutron source (ISO 8529-1: 2001(E)) was obtained from the kerma coefficients and Monte Carlo calculation. In addition, it was calculated directly by multiplying the neutron fluence by the fluence-to-ambient dose conversion coefficients recommended by ICRP (ICRP 1996 ICRP Publication 74 (Oxford: Pergamon)). The two results agree well with each other. The main feature of this work is our Monte Carlo simulation design and the treatments differing from the work of others in the calculation of neutron energy transfer in non-elastic processes.
Liu
Zhenzhou
Z
State Key Laboratory of Nuclear Physics and Technology, School of Physics, Peking University, Beijing 100871, People's Republic of China.
Chen
Jinxiang
J
D055592:Biophysical Phenomena; D001703:Biophysics; D002244:Carbon; D005214:Fast Neutrons / Q000627:therapeutic use; D006801:Humans; D006859:Hydrogen; D009010:Monte Carlo Method; D009584:Nitrogen; D010100:Oxygen; D011829:Radiation Dosage; D011835:Radiation Protection; D011874:Radiometry / Q000379:methods*; D011879:Radiotherapy Dosage; D011882:Radiotherapy, High-Energy
D002244:Carbon; D006859:Hydrogen; D009584:Nitrogen; D010100:Oxygen