Collimator and shielding design for boron neutron capture therapy (BNCT) facility at TRIGA Mark II reactor
Abstract
ABSTRACT
The geometry of reactor core, thermal column, collimator and shielding system for BNCT application of TRIGA MARK II REACTOR were simulated with MCNP5 code. Neutron particle lethargy and dose were calculated with MCNPX code. Neutron flux in a sample located at the end of collimator after normalized to measured value (Eid Mahmoud Eid Abdel Munem, 2007) at 1 MW power was 1.06E8 n/cm2/s. According to IAEA (2001) flux of 1.00E9 n/cm2/s requires three hours of treatment. Few modifications were needed to get higher flux.
ABSTRAK
Geometri teras reaktor, kolum terma, kolimator dan sistem perisai untuk aplikasi BNCT pada reaktor TRIGA MARK II telah disimulasikan menggunakan kod MCNP5. Pengiraan zarah (letargi) dan dos neutron telah dilakukan menggunakan kod MCNPX. Didapati flux neutron pada sampel yang diletak dihujung kolimator selepas dinormalkan kepada nilai yang diukur oleh Eid Mahmoud Eid Abdel Munem (2007) pada kuasa reaktor 1 MW adalah 1.06E8 n/cm2/s. Mengikut IAEA (2001), flux 1.00E9 n/cm2/s memerlukan rawatan selama tiga jam. Beberapa pengubahsuaian perlu dilakukan untuk mendapatkan flux yang lebih tinggi.
