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Calculation of exposure buildup factors for point isotropic gamma ray sources in sttatified spherical shields of water surrounded by lead and optimization of water-lead combination
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Mix design effective parameters on Gamma-ray attenuation coefficient and strength of normal and heavyweight concrete
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Determination of neutron dose equivalent buldup factors for infinite slabs irradiated by point isotropic neutron sources using the MCNP code.
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A study of gamma ray exposure buildup factors instratified shields for point isotropic sources including the effects of incoherent andcoherent Scattering
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A measurent of pi ( ) proton backward elastic differential cross section from 1.282 to 2.472 GeV/c
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An energy dependent partial wave analysis of ... between threshold and 2.35 GeV
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Differential cross section and polarisation for... at 26 momenta between 1.282 2.473GeV/c
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شبيه سازي مونت كارلو يك دستگاه پرتودهي نوتروني به منظور تعيين بازده آشكارسازهاي نوترون هاي حرارتي
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تعيين لايه مرده و بازده قله تمام - انرژي آشكارسازHPGe با استفاده از كد MCNP و نتايج تجربي.
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تعيين توزيع شار نوترون در طول كانال خشك رآكتور MNSR و تعيين طيف انرژي نوترون در اين رآكتور.
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