DESIGN & SIMULATION OF A BNCT FACILITY AT MALAYSIAN NUCLEAR AGENCY WITH MCNP CODE

Abstract

The objective of this research is to optimally design an arrangement for BNCT facility at a beam line through the thermal column of Malaysian TRIGA MARK II Reactor. There is no similar research had been done at this thermal column and all TRIGA reactors have different characteristics. The characteristics of the neutron beam needed are thermal neutron with a flux of 109 cm-2s-1. Collimator, moderator and shielding components (room) with reactor core and thermal column will be simulated with Monte Carlo N-Particle Transport Code version 5 (MCNP5). Fluxes of neutron and photon will be calculated together with their energies with the same software.