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Simulation of neutron flux in silicon, cadmium and plumbum using Monte Carlo method

The purpose of this study is to investigate the neutron energy flux from reactor after attenuated by silicon, cadmium and plumbum at the end of the beam port. Neutrons can be categorized into thermal neutron, intermediate and fast neutron according to their energies. Fast neutrons in reactor needs t...

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Main Author: Hamzah, Hafida
Format: Thesis
Language:English
Published: 2010
Subjects:
QC Physics
Online Access:http://eprints.utm.my/id/eprint/11300/4/HafidaHamzahMFS2010.pdf
http://eprints.utm.my/id/eprint/11300/
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spelling my.utm.113002017-09-27T04:13:02Z http://eprints.utm.my/id/eprint/11300/ Simulation of neutron flux in silicon, cadmium and plumbum using Monte Carlo method Hamzah, Hafida QC Physics The purpose of this study is to investigate the neutron energy flux from reactor after attenuated by silicon, cadmium and plumbum at the end of the beam port. Neutrons can be categorized into thermal neutron, intermediate and fast neutron according to their energies. Fast neutrons in reactor needs to be thermalized before it can be utilized for applications such as in medicine, industrial and research purposes. The fast neutron will lost its energy into thermal neutrons due to scattering and absorption process with nucleuses. The neutron probability of interaction with nucleus depends on the microscopic cross-section, which is different for each material. All the cross-section data for every element have been compiled in ENDF (Evaluated Nuclear Data File) format and internationally recognized. In this study, the neutron transport was simulated using Monte Carlo N-Particle Transport Code, Version 5 (MCNP5). The thickness of the materials used in this research is in the range of 1 cm to 10 cm. The result shows that the neutron was reduced significantly by silicon then follows by plumbum and cadmium. The thermal neutron flux was the lowest in cadmium because it have high thermal neutron cross-section. 2010-04 Thesis NonPeerReviewed application/pdf en http://eprints.utm.my/id/eprint/11300/4/HafidaHamzahMFS2010.pdf Hamzah, Hafida (2010) Simulation of neutron flux in silicon, cadmium and plumbum using Monte Carlo method. Masters thesis, Universiti Teknologi Malaysia, Faculty of Science.
institution Universiti Teknologi Malaysia
building UTM Library
collection Institutional Repository
continent Asia
country Malaysia
content_provider Universiti Teknologi Malaysia
content_source UTM Institutional Repository
url_provider http://eprints.utm.my/
language English
topic QC Physics
spellingShingle QC Physics
Hamzah, Hafida
Simulation of neutron flux in silicon, cadmium and plumbum using Monte Carlo method
description The purpose of this study is to investigate the neutron energy flux from reactor after attenuated by silicon, cadmium and plumbum at the end of the beam port. Neutrons can be categorized into thermal neutron, intermediate and fast neutron according to their energies. Fast neutrons in reactor needs to be thermalized before it can be utilized for applications such as in medicine, industrial and research purposes. The fast neutron will lost its energy into thermal neutrons due to scattering and absorption process with nucleuses. The neutron probability of interaction with nucleus depends on the microscopic cross-section, which is different for each material. All the cross-section data for every element have been compiled in ENDF (Evaluated Nuclear Data File) format and internationally recognized. In this study, the neutron transport was simulated using Monte Carlo N-Particle Transport Code, Version 5 (MCNP5). The thickness of the materials used in this research is in the range of 1 cm to 10 cm. The result shows that the neutron was reduced significantly by silicon then follows by plumbum and cadmium. The thermal neutron flux was the lowest in cadmium because it have high thermal neutron cross-section.
format Thesis
author Hamzah, Hafida
author_facet Hamzah, Hafida
author_sort Hamzah, Hafida
title Simulation of neutron flux in silicon, cadmium and plumbum using Monte Carlo method
title_short Simulation of neutron flux in silicon, cadmium and plumbum using Monte Carlo method
title_full Simulation of neutron flux in silicon, cadmium and plumbum using Monte Carlo method
title_fullStr Simulation of neutron flux in silicon, cadmium and plumbum using Monte Carlo method
title_full_unstemmed Simulation of neutron flux in silicon, cadmium and plumbum using Monte Carlo method
title_sort simulation of neutron flux in silicon, cadmium and plumbum using monte carlo method
publishDate 2010
url http://eprints.utm.my/id/eprint/11300/4/HafidaHamzahMFS2010.pdf
http://eprints.utm.my/id/eprint/11300/
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score 13.211869

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