Simulation of Collimator for Neutron Imaging Facility of TRIGA MARK II PUSPATI Reactor

Abstract Neutron Radiography facility in TRIGA MARK II PUSPATI reactor is being upgraded to obtain better image resolution as well as reducing exposure time. Collimator and exposure room are the main components have been designed for fabrication. This article focuses on the simulation part that was carried out to obtain the profile of collimated neutron beam by utilizing the neutron transport protocol code in the Monte Carlo N -Particle (MCNP) software. Particular interest is in the selection of materials for inlet section of the collimator. Results from the simulation indicates that a combination of Bismuth and Sapphire, each of which has 5.0 cm length that can significantly filter both the gamma radiation and the fast neutrons. An aperture made of Cadmium with 1.0 cm opening diameter provides thermal neutron flux about 1.8 x10 8 ncm −2 s −1 at the inlet, but reduces to 2.7 x10 6 ncm −2 s −1 at the sample plane. Still the flux obtained is expected to reduces exposure time as well as gaining better image resolution.