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Study of moderator (Collimator) materials for boron neutron capture therapy (BNCT) facilities

TP245.B6 M83 2016

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Main Author: Muhammed Ariff Mohd Sarif
Format: text::Final Year Project
Language:English
Published: 2024
Subjects:
Boron > Biotechnology
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spelling my.uniten.dspace-352112024-12-08T02:02:12Z Study of moderator (Collimator) materials for boron neutron capture therapy (BNCT) facilities Muhammed Ariff Mohd Sarif Boron -- Biotechnology TP245.B6 M83 2016 The Malaysian TRIGA Mark II reactor was investigated for this research. The objective of this research is to study the moderator (collimator) materials for Boron Neutron Capture Therapy (BNCT) facilities proposed. The experiment was conducted by using Small Angle Neutron Scattering (SANS) beam as the neutron source. The materials used as the sample was Steel slab, Aluminum slab, Cadmium slab, Lead slab, Boron Carbide (B,C), Plasticine Clay, Water, Concrete slab, Polyethylene, and Paraffin. The samples were irradiated by using SANS neutron and the fluxes of neutron with energies were measured using MICROSPEC-Spectrometer detector. The neutron spectrum profiles for each sample were recorded and compared for the purpose of analyzing the materials characteristic. Based on the results, Paraffin possesses the highest thermal peaks, followed by Concrete and Steel. The experiment result analysis was continued with neutron penetration and attenuation coefficient measurement for each sample. Cadmium slab shows the highest attenuation coefficient value, follows by Polyethylene and Water respectively. Neutron cross section analysis was also conducted based on the data collected from the experiment. The highest scattering cross section is demonstrated by Water followed by Polyethylene. The lowest was Paraffin. The highest absorption cross section is demonstrated by Cadmium and the lowest was Boron Carbide. Weight ratio used to determine the material characteristics on acting as the good neutron moderator. Polyethylene possesses the highest ratio, followed by Water and Paraffin. Based on results and analysis, BNCT facility is proposed to be consisting of three different materials, combining of Paraffin, Polyethylene and Water. Neutron shielding elements surrounding the collimator should be a combination of Cadmium and Boron Carbide. The structural frame of BNCT facility is suggested to consist of Concrete, Steel and Aluminum, due to the materials capabilities and the cost factor. 2024-12-04T01:50:29Z 2024-12-04T01:50:29Z 2016 Resource Types::text::Final Year Project https://irepository.uniten.edu.my/handle/123456789/35211 en application/pdf
institution Universiti Tenaga Nasional
building UNITEN Library
collection Institutional Repository
continent Asia
country Malaysia
content_provider Universiti Tenaga Nasional
content_source UNITEN Institutional Repository
url_provider http://dspace.uniten.edu.my/
language English
topic Boron -- Biotechnology
spellingShingle Boron -- Biotechnology
Muhammed Ariff Mohd Sarif
Study of moderator (Collimator) materials for boron neutron capture therapy (BNCT) facilities
description TP245.B6 M83 2016
format Resource Types::text::Final Year Project
author Muhammed Ariff Mohd Sarif
author_facet Muhammed Ariff Mohd Sarif
author_sort Muhammed Ariff Mohd Sarif
title Study of moderator (Collimator) materials for boron neutron capture therapy (BNCT) facilities
title_short Study of moderator (Collimator) materials for boron neutron capture therapy (BNCT) facilities
title_full Study of moderator (Collimator) materials for boron neutron capture therapy (BNCT) facilities
title_fullStr Study of moderator (Collimator) materials for boron neutron capture therapy (BNCT) facilities
title_full_unstemmed Study of moderator (Collimator) materials for boron neutron capture therapy (BNCT) facilities
title_sort study of moderator (collimator) materials for boron neutron capture therapy (bnct) facilities
publishDate 2024
_version_ 1818838874050265088
score 13.222552

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