Assessment of the Absorbed Dose Components of BNCT Method at the Dalat Research Reactor

Abstract

At the Dalat Nuclear Research Reactor (DNRR) in Vietnam, some calculations and experiments of the Boron Neutron Capture Therapy (BNCT) method have been performed at horizontal channel No. 2 of the DNRR using a phantom. This research used the Monte Carlo N-Particle version 5 (MCNP5) code to simulate and calculate the distribution of absorbed dose components of the BNCT method. The collimator of horizontal neutron channel No. 2 of the DNRR was changed from cylindrical to conical to increase the flux of the neutron beam. Simultaneously, neutron crystal filters corresponding to 20 cm Si and 3 cm Bi are also employed to produce high-purity thermal neutron beams. The thermal neutron flux and absorbed dose components have been computed in a water phantom. The gamma dose from the reactor core of the DNRR can be omitted when calculating the total absorbed dose in the BNCT method.