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A Test of MCNP with a 6Li-Glass Moderating Neutron Detector

J. C. Wang, Gary L. Jensen, J. B. Czirr

Nuclear Science and Engineering / Volume 113 / Number 1 / January 1993 / Pages 77-85

Technical Paper / dx.doi.org/10.13182/NSE93-A23995

Rigorous tests of the Monte Carlo transport code MCNP have been performed by measuring the efficiency of a 6Li-glass moderating neutron detector using Lucite as the moderator relative to the efficiency of the detector using mineral oil as the moderator, and comparing this with the MCNP predicted value. The tests were done using both 252Cf fission-source neutrons and 1.2-MeV neutrons produced by a Van de Graaff accelerator.