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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| 第一著者: | |
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| フォーマット: | 学位論文 |
| 言語: | English |
| 出版事項: |
2010
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| 主題: | |
| オンライン･アクセス: | http://eprints.utm.my/id/eprint/11300/4/HafidaHamzahMFS2010.pdf http://eprints.utm.my/id/eprint/11300/ |
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