Neutron Flux Parameter for In-Vivo testing Boron Neutron Capture Therapy (BNCT) on Radial Piercing Beam Port Kartini Nuclear Reactor by Monte Carlo N-Particle Extended (MCNPX) Simulation Method

Abstract

The research of neutron flux parameters for in vivo testing BNCT on radial piercing beamport Kartini Nuclear Reactor was carried out using the MCNPX simulation method. BNCT is an alternative type of nuclear therapy that utilizes a 10 B (n, α) 7 Li reaction that produces a total kinetic energy of 2.79 MeV. Linear Energy Transfer (LET) of α particles and 7 Li recoil will be deposited locally in the range of 5-9 µm. The determination of neutron flux was carried out after optimizing the collimator through the translucent port of the Kartini Reactor with a neutron source according to the output of the collimator. Neutron flux obtained after irradiation with an optimum concentration of boron 10 was 47 g of output data tumors for skin tissue.