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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Détails bibliographiques
Auteur principal:	Hamzah, Hafida
Format:	Thèse
Langue:	anglais
Publié:	2010
Sujets:	QC Physics
Accès en ligne:	http://eprints.utm.my/11300/4/HafidaHamzahMFS2010.pdf

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