Calculation of a Simple Cylindrical Moderator for Neutron Detector
Abstract
Mathematical modeling of the passage of neutrons through cylindrical polyethylene moderator of neutron detector had been performed. Had been calculated amount of thermal neutrons that fall in located on the axis of the moderator gas discharge tube counters of thermal neutrons. For different diameters of the moderator the energy depending of the detection efficiency of incident neutrons had been obtained. Found the diameter of the moderator, in which the detection efficiency is quite high (10%) and nearly constant for neutrons with energies from thermal to 1 MeV. It is noted that a detector with these characteristics is optimal for the registration of delayed fission neutrons and can be used in installations of activation analysis for the content of fissionable materials.
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References
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