الفهرس 
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Abstract
This work is concerned with the investigation of the attenuation and energy degradation of 14.1 Mev neutrons passing inside graphite, 1ead, lithium fluoride, natural uranium and a homogeneous mixture of uranium and lithium fluoride slabs. The calculated spectra were carried out by using the modified version of the ANISN code with the new cross section data set ZZFEWG 1/31-1F to show the neutron attenuations in groups ranging from 14.2 to 0.158 MeV.