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

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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书目详细资料
主要作者:	Hamzah, Hafida
格式:	Thesis
语言:	English
出版:	2010
主题:	QC Physics
在线阅读:	http://eprints.utm.my/id/eprint/11300/4/HafidaHamzahMFS2010.pdf
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