Test of Monte Carlo Code (mcnp) with Moderating Neutron Detector.

The purpose of this project is to provide strict tests to determine how accurately MCNP can predict the efficiency of neutron detectors under conditions that can be checked experimentally. This work thus provides a basis for calculating with confidence the efficiency of neutron detectors in an energy region where it is difficult to test efficiency directly. Experiments have been performed to measure the efficiency of neutron detectors with mineral oil or lucite as moderators, and with both a ^ {252}C f radioisotope spectral neutron source and a t(p, n) Van de Graaff accelerator-generated 1.2 MeV monoenergetic neutron source providing the incident neutrons. The accuracy of the MCNP prediction is (0.27 +/- 0.55)% for the ^ {252}C f neutron source and is (1.29 +/- 1.88)% for the 1.2 MeV monoenergetic neutron source.