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Objective: This study aims to obtain an alternative method to reduce the tumor. Optimization of collimator and in vivo Boron Neutron Capture Therapy (BNCT) materials on translucent beam reactor Kartini Reactor eligible IAEA. Method: BNCT is a kind of alternative nuclear therapy that utilizes the reaction of B (n, α) Li which produces a total kinetic energy of 2.79 MeV. Linear Energy Transfer (LET) from α and Li particle recoil will be stored locally at a distance of 5-9 μm. Optimization of collimator design is by varying the walls of collimators, moderators, filters and gamma shields. Such optimizations produce epitermal neutron flux values, current components, thermal neutron components, rapid neutron dose components and gamma dose components according to IAEA requirements by utilizing Monte Carlo N-Particle Extended (MCNPX) simulations. Results: This study produced the best collimator design of 1.75 cm thick Ni-nat as a collimator wall, Al2S3 as thick as 29 cm as moderator, Al2O3 0.5 cm thick as filter, Pb and Bi as thick as 4 cm as a shield of collimator and Bi gamma end as thick as 1.5 cm as a gamma shield. Conclusion: This study concludes that the optimization of collimator designs meets the needs of the IAEA and can be simulated for in vivo test radiation.

The Optimization Of Collimator Design And In-Vivo Testing Of Boron Neutron Capture Therapy On Radial Piercing Beamport Kartini Nuclear Reactor By Monte Carlo N-Particle Extended Simulation Method