Mohd Solleh, Mohd Rafi
(2016)
Moderator, Collimator And Shielding Studies For Bnct Research At Malaysian Nuclear Agency.
PhD thesis, Universiti Sains Malaysia.
Abstract
Objektif penyelidikan ini adalah untuk mengkaji pengoptimunan susun atur bagi kemudahan Boron Neutron Capture Therapy (BNCT) pada garisan alur neutron yang melalui kolum termal pada Reaktor TRIGA MARK II Malaysia. Belum ada penyelidikan sebegini dilakukan di kolum termal tersebut dan ciri setiap reaktor TRIGA adalah berbeza. Ciri alur neutron yang diperlukan adalah neutron yang bertenaga terma dengan fluk sebanyak 109 cm-2s-1 dan alurnya berdiameter 15 cm. Kolimator, moderator dan komponen perisaian bersama teras reaktor dan kolum termal disimulasi menggunakan Monte Carlo N-Particle Transport Code. Fluk neutron dan foton dikira bersama dengan tenaga masing-masing menggunakan perisian yang sama. Selepas itu kolimator dan perisai telah dibina. Polyethylene dan air telah digunakan sebagai perisai neutron laju dan neutron epiterma. Plumbum pula digunakan sebagai perisai sinar gama. Kolimator diperbuat dari paip polyethylene berdiameter 8 cm dan disikan dengan lilin. Pengukuran neutron dan sinar gama di dalam Graphite Stringer tengah (G7) pada kolum termal telah dilakukan menggunakan pengesan TLD.
The objective of this research is to optimally study an arrangement for BNCT facility at a beam line through the thermal column of Malaysian TRIGA MARK II Reactor. There is no similar research had been done at this thermal column and all TRIGA reactors have different characteristics. The characteristics of the neutron beam needed are thermal neutron with a flux of 109 cm-2s-1 and the diameter of the beam is 15 cm. Collimator, moderator and shielding components with reactor core and thermal column were simulated with Monte Carlo N-Particle Transport Code. Fluxes of neutron and photon were calculated together with their energies with the same software. After that, collimator and shielding are fabricated. For fast and epithermal neutron shielding, a polyethylene and water were used. For gamma-ray shielding, lead was used. The collimator is made from polyethylene pipe with 8 cm of diameter filled with paraffin. Neutron and gamma-ray measurement in a Central Graphite Stringer (G7) of thermal column was done with TLD detectors.
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