GEANT4 calculations of neutron dose in radiation protection using a homogeneous phantom and a Chinese hybrid male phantom Abstract
The purpose of this study are to verifyThe feasibility (feasibility) of applying GEANT4 (version 10.01) in neutron dose calculationsIn radiation protection bycomparing the calculation results with MCNP5. The depth dose distributions is investigated in a homogeneous phantom, and the Fluence-to-dose conversion coefficients AR E calculated for different organs in the Chinese hybrid male phantom for neutrons withEnergy ranging from 1x10−9 to MeV. By comparing the simulation results between GEANT4 and MCNP5, it's shown thatusing the high-precision (HP) neutron physics list, GEANT4 produces the closest simulation results to MCNP5. However,differences could be observed when the neutron energy is lower than 1x10−6 MeV. Activating the thermal scattering with anS Matrix CorrectionIn GEANT4 with HP and MCNP5 in thermal energy range can reduce the difference between these and codes.
First a lot of concepts may not be very good translation, for the time being just their own point of view
G4 has to perform validation analysis when many simulations are actually deployed, because G4 is not necessarily verified in a specific area over and over again. This article is the author uses G4 and MCNP to the same neutron irradiation human body model analysis, the main calculation of neutron dose, the body model used two, one is a homogeneous body model, a Chinese male human body model, calculated the depth of the uniform body mold dose distribution, The dosage-dose conversion coefficients of different organs in Chinese male mixed body were also calculated. The simulated neutron energy range is 0.001eV to 10MeV, and the results show that the most approximate results are obtained with the G4 hp (high precision) neutron physics model. However, there is a big difference at less than 1eV, the paper uses the S-matrix correction to activate the thermal neutron scattering method to solve the problem of the large difference in the thermal neutron energy region. But there are problems here, how to do the S-matrix correction? The basis for this is experience? Dine or something else is a question that needs to be considered in the future.
Recently helping people to see a simulation, but also at the time of the low-energy neutron simulation and theoretical numerical calculation there is a large deviation, did not use MCNP calculation, so still need to consider.
RPD Volume 168 Issue 4 March 2016 Comments 1