Beam optimization for boron neutron capture theraphy at thermal column of TRIGA Mark-II research reactor

The thermal column at TRIGA PUSPATI research reactor has an ability to produce thermal neutron. However, the optimization on the thermal neutron flux produced should be performed in order to gain a sufficient thermal neutron for boron neutron capture therapy purpose. Thus, the objective of this stud...

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Main Author: Shalb, Safwan
Format: Thesis
Language:English
Published: 2018
Subjects:
Online Access:http://eprints.utm.my/id/eprint/86952/1/SafwanShalbiMSChE2018.pdf
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spelling my-utm-ep.869522020-10-30T05:13:38Z Beam optimization for boron neutron capture theraphy at thermal column of TRIGA Mark-II research reactor 2018 Shalb, Safwan TP Chemical technology The thermal column at TRIGA PUSPATI research reactor has an ability to produce thermal neutron. However, the optimization on the thermal neutron flux produced should be performed in order to gain a sufficient thermal neutron for boron neutron capture therapy purpose. Thus, the objective of this study is to optimize the thermal neutron flux by designing the collimator with different materials at the thermal column. In order to fulfil the requirement, set by the IAEA standard, the collimator was designed using Monte Carlo N-Particle simulation. Initially, the measurement of the thermal neutron flux was conducted along the thermal column at 250 kW. The thermal column was divided into 3 phases (Phase 1, Phase 2 and Phase 3) so that an accurate measurement can be obtained by using gold foil activation method and thermoluminescent dosimeter detector. This value was used as a benchmark for the neutron flux produced from the thermal column. The collimator was designed using different types of materials and their characteristic towards gamma and neutron flux was investigated. The results demonstrated that the final thermal neutron flux produced was significantly depends on the shielding thickness, aperture size and collimator conditions (uncovered or fully covered). The collimator design using thickness shielding of 5+10 cm of lead, aperture size of 3 cm and operated using uncovered condition has produced the optimum thermal neutron flux. The sufficient amount of thermal neutron flux of 3.28 x 108 neutron.cm-2s-1 at 250 kW of TRIGA PUSPATI research reactor power produced from the designated collimator was achieved. 2018 Thesis http://eprints.utm.my/id/eprint/86952/ http://eprints.utm.my/id/eprint/86952/1/SafwanShalbiMSChE2018.pdf application/pdf en public http://dms.library.utm.my:8080/vital/access/manager/Repository/vital:131893 masters Universiti Teknologi Malaysia, Faculty of Engineering - School of Chemical & Energy Engineering Faculty of Engineering - School of Chemical & Energy Engineering
institution Universiti Teknologi Malaysia
collection UTM Institutional Repository
language English
topic TP Chemical technology
spellingShingle TP Chemical technology
Shalb, Safwan
Beam optimization for boron neutron capture theraphy at thermal column of TRIGA Mark-II research reactor
description The thermal column at TRIGA PUSPATI research reactor has an ability to produce thermal neutron. However, the optimization on the thermal neutron flux produced should be performed in order to gain a sufficient thermal neutron for boron neutron capture therapy purpose. Thus, the objective of this study is to optimize the thermal neutron flux by designing the collimator with different materials at the thermal column. In order to fulfil the requirement, set by the IAEA standard, the collimator was designed using Monte Carlo N-Particle simulation. Initially, the measurement of the thermal neutron flux was conducted along the thermal column at 250 kW. The thermal column was divided into 3 phases (Phase 1, Phase 2 and Phase 3) so that an accurate measurement can be obtained by using gold foil activation method and thermoluminescent dosimeter detector. This value was used as a benchmark for the neutron flux produced from the thermal column. The collimator was designed using different types of materials and their characteristic towards gamma and neutron flux was investigated. The results demonstrated that the final thermal neutron flux produced was significantly depends on the shielding thickness, aperture size and collimator conditions (uncovered or fully covered). The collimator design using thickness shielding of 5+10 cm of lead, aperture size of 3 cm and operated using uncovered condition has produced the optimum thermal neutron flux. The sufficient amount of thermal neutron flux of 3.28 x 108 neutron.cm-2s-1 at 250 kW of TRIGA PUSPATI research reactor power produced from the designated collimator was achieved.
format Thesis
qualification_level Master's degree
author Shalb, Safwan
author_facet Shalb, Safwan
author_sort Shalb, Safwan
title Beam optimization for boron neutron capture theraphy at thermal column of TRIGA Mark-II research reactor
title_short Beam optimization for boron neutron capture theraphy at thermal column of TRIGA Mark-II research reactor
title_full Beam optimization for boron neutron capture theraphy at thermal column of TRIGA Mark-II research reactor
title_fullStr Beam optimization for boron neutron capture theraphy at thermal column of TRIGA Mark-II research reactor
title_full_unstemmed Beam optimization for boron neutron capture theraphy at thermal column of TRIGA Mark-II research reactor
title_sort beam optimization for boron neutron capture theraphy at thermal column of triga mark-ii research reactor
granting_institution Universiti Teknologi Malaysia, Faculty of Engineering - School of Chemical & Energy Engineering
granting_department Faculty of Engineering - School of Chemical & Energy Engineering
publishDate 2018
url http://eprints.utm.my/id/eprint/86952/1/SafwanShalbiMSChE2018.pdf
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