Neutron flux evaluation algorithm with a combination of Monte Carlo and removal‐diffusion calculation methods for boron neutron capture therapy

Abstract

AbstractBackgroundIn Japan, the clinical treatment of boron neutron capture therapy (BNCT) has been applied to unresectable, locally advanced, and recurrent head and neck carcinomas using an accelerator‐based neutron source since June of 2020. Considering the increase in the number of patients receiving BNCT, efficiency of the treatment planning procedure is becoming increasingly important. Therefore, novel and rapid dose calculation algorithms must be developed. We developed a novel algorithm for calculating neutron flux, which comprises of a combination of a Monte Carlo (MC) method and a method based on the removal‐diffusion (RD) theory (RD calculation method) for the purpose of dose calculation of BNCT.PurposeWe present the details of our novel algorithm and the verification results of the calculation accuracy based on the MC calculation result.MethodsIn this study, the “MC‐RD” calculation method was developed, wherein the RD calculation method was used to calculate the thermalization process of neutrons and the MC method was used to calculate the moderation process. The RD parameters were determined by MC calculations in advance. The MC‐RD calculation accuracy was verified by comparing the results of the MC‐RD and MC calculations with respect to the neutron flux distributions in each of the cubic and head phantoms filled with water.ResultsComparing the MC‐RD calculation results with those of MC calculations, it was found that the MC‐RD calculation accurately reproduced the thermal neutron flux distribution inside the phantom, with the exception of the region near the surface of the phantom.ConclusionsThe MC‐RD calculation method is useful for the evaluation of the neutron flux distribution for the purpose of BNCT dose calculation, except for the region near the surface.