| Shrnutí: | The optimation of collimator design on radial piercing beam port in Kartini Nuclear
Reactor using MCNP5 simulation has been carried out. This optimation has been used
for obtaining neutron flux according to International Atomic Energy Agency (IAEA)
regulation. The methode used in this experiment was combination of shifting methode
and filtering methode. Independent variables varied, were material and thickness of
collimator wall, moderator, filter and gamma shielding. Optimized epithermal neutron
flux of the collimator for in vivo testing has been achieved 1.20 n/cm2s. The
result of beam quality are 0.8 for neutron current component, 0.03 for thermal neutron
component, 312 Gy cm2s/n for fast neutron component and 38.5 Gy
cm2s/n for gamma contamination component. It can be concluded that, the designed
collimator is feasible and applicable for In Vivo testing of BNCT
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