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...

書目詳細資料
主要作者:	Hamzah, Hafida
格式:	Thesis
語言:	英语
出版:	2010
主題:	QC Physics
在線閱讀:	http://eprints.utm.my/11300/4/HafidaHamzahMFS2010.pdf

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