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...

وصف كامل

التفاصيل البيبلوغرافية
المؤلف الرئيسي:	Hamzah, Hafida
التنسيق:	أطروحة
اللغة:	الإنجليزية
منشور في:	2010
الموضوعات:	QC Physics
الوصول للمادة أونلاين:	http://eprints.utm.my/11300/4/HafidaHamzahMFS2010.pdf

مواد مشابهة

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