An Optimization Design of Collimator in The Thermal Column of Kartini Reactor For BNCT

Abstract

Studies were carried out to design a collimator which results in epithermal neutron beam for in vivo experiment of Boron

Neutron and Gamma Spectrum Analysis of Kartini Research Reactor for Boron Neutron Capture Therapy (Bnct)

“…KRR uses U-235 as a fuel and is capable of producing neutrons. Currently, KRR is operated at 100 kW power [8]. The KRR has 6 beamports that are directly connected to the reactor core [9].…”

“…In Indonesia, KRR-Based BNCT is being developed. The utilization of MCNP for design, simulation, optimization design of biological shielding and collimator based on KRR neutron source has been done through the simulation of neutron and gamma interaction with many kind of collimator and shielding materials [8,13,14]. In addition, study of dosimetry calculation for in vivo test preparation has been done as well [15].…”

“…Thermal neutron fluxes recorded on the base of radial piercing beamport were 4.678×10 10 n/cm 2 s, with the epithermal neutron flux of 5.37×10 9 n/cm 2 s and fast neutron flux of 4.17×10 10 n/cm 2 s. The gamma flux on that side reaches 4.22×10 12 particles/cm 2 s. On the 92-cm-ranges from the base inside radial piercing beamport, both neutron and gamma flux decrease up to 5.11×10 8 n/cm2s for thermal neutron flux, 4.598×10 6 n/cm 2 s for epithermal neutron flux, 2.55×10 7 n/cm 2 s for fast neutron flux and 8.214×10 10 particles/cm 2 s for gamma flux. In conclusion, the spectrum yield from this study can be use to define the source spectrum of the simulations and optimations prior to BNCT pre-clinical trial (in vivo/in vitro test) use KRR radial piercing beamport.…”