Experimental terminal design of BNCT neutron source based on 14 MeV proton cyclotron

Abstract

BackgroundWith the development of accelerator technology, the accelerator-based Boron Neutron Capture Therapy (BNCT) has attracted more and more attention, and metallic 9Be is one of the most suitable materials for neutron-producing targets.PurposeThe study aims to investigate the possibility of obtaining BNCT neutron sources based on proton cyclotron with energy of 14 MeV and current intensity of 80 μA.MethodsGeant4 was used to simulate the neutron beam properties of Be target bombarded by 14 MeV proton beams and to optimize the target thickness. In addition, spherical natural uranium was considered as a neutron multiplier, the neutron beams generated by the combination of different materials and thicknesses of Beam Shaping Assembly (BSA) were investigated by simulation.ResultsThe optimized irradiated field at beam outlet of proton cyclotron can reach 95.6% of epithermal neutrons, and 6.26×107 n·cm-2·s-1 of the epithermal flux rate.ConclusionsThis design solution can be initially used for the technical verification of BNCT neutron source experimental terminal.

Keywords

• bnct
• geant4
• 9be(p,n) reaction
• beam shaping assembly
• epithermal neutron field