Feasibility of a Neutron Beam for BNCT Application Based on Nuclear Fusion Reactions D-D and D-T

Abstract

A research has been made in order to evaluate the feasibility of an accelerator driven neutron source for Boron Neutron Capture Therapy (BNCT) based on nuclear fusion reactions D(d,n)3He and T(d,n)4He.The work focuses on determining which kind of moderator materials and beam shaping assembly geometry are the most suitable to slow down the very fast neutrons emitted by the fusion sources. The aim is to obtain an epithermal neutron flux for therapeutic application, as high as possible, affected by a low gamma and fast neutron contamination.We find that the DD reaction cannot be used, at present, for BNCT applications, owing to its low neutron yield. It has been demonstrated that the use of a DT source in a well optimised beam shaping geometry can lead to beam port parameters that are rather close to the ones usually required. It’s hoped, therefore, that an upgraded, multibeam DT source and the use of new porphyrine based boron carrier, would allow to use this kind of source into a BNCT facility.We would like to underline that all calculations performed has to be regarded as preliminary ones. They have the main purpose to evaluate the feasibility about a future use of this kind of source, namely the D-T one.