DEVELOPMENT OF AN MCNP MODEL OF A BORON-10 ZINC SULFIDE SILVER-ACTIVATED [ ¹⁰ B/ZnS(Ag)] DETECTOR AND DIRECTIONAL SHIELDING USING RADIATION COUNTING

Abstract

For radiological neutron surveying, neutron detectors require shielding to minimize contributions from sources outside the area of interest. To test the effectiveness of such a shield, Monte Carlo N-Particle Transport Codes (MCNP) were used to model a neutron detector so that the effectiveness of such a shield design could be explored. In this research, MCNP models of a 10 B/ZnS detector within a shield were developed and compared to experimental results. By carefully modeling the specifics of the neutron detector as well as the neutron source used in the experiments, the simulation was able to accurately predict the experimental results within 20%.