Design of a BNCT facility at Malaysian nuclear agency with MCNP code

The aim of this research is to optimally design a BNCT facility at a beam line through the Malaysian TRIGA MARK II Reactor's thermal column. Thermal neutron with a flux of 109 cm-2s-1 was the characteristics of the neutron beam needed. Monte Carlo N-Particle Transport Code version 5 (MCNP5) was used to simulate all collimators, moderator and treatment room together with the reactor core and thermal column. The engineering drawing of the BNCT facility design was made with CATIA software. The geometry of reactor core and thermal column is the actual geometry of the reactor. The BNCT facility room was designed accordingly to them.