Comparative analysis of MCNPX and GEANT4 codes for fast-neutron radiation treatment planning

The paper presents a comparative analysis of the MCNPX and GEANT4 simulation tools for the beam therapy fast neutron transport calculation problems. Groups of model experiments are described which compare the absorbed energy calculated values obtained on different types of phantoms and the rate of calculation for both simulation tools is assessed depending on the variation in the phantom and source parameters. The results of the studies can be used as the basis for the fast-neutron treatment radiation planning.