Optimization study for BNCT facility based on a DT neutron generator

Background : A Boron Neutron Capture Therapy (BNCT) facility, based on a DT neutron generator, with the final goal to find out a potenal, alternave, soluon to exisng BNCT treatment facilies which a re based on nuclear reactors is examined. Materials and Method s: With the aim of the MCNP4B Monte Carlo code different beam-shaping assembly (BSA) configuraons were considered. Lead was selected as reflector material while CF 2, D 2O, Fluental, PbF 4, PbF 2, BiF 3, BiF 5, MgF 2, Al 2O3, AlF 3, TiF 3, BeD 2, CaF 2 and 7 LiF were examined as spectrum shi3ers. In order to improve t he quality of the beam �tanium, nickel-60, iron andtanium alloy (Ti 6Al 14 V) were simulated as fast neutrons filters while lead and bismuth were considered as gamma filters. Results: An extensive set of calculaons performed with MCNP4B Monte Carlo code have shown that the combinaon of 7 LiF which accommodates a conic part made of D 2O, then followed by a TiF 3 layer is the opmum moderator design. The use of three different materials for further reducon of fast neutrons, thermal neutrons and gamma rays is necessary. 60