Experimental and mcnp5 based evaluation of neutron and gamma flux in the irradiation ports of the university of Utah research reactor

Abstract

Neutron and gamma flux environment of various irradiation ports in the University of Utah training, research, isotope production, general atomics reactor were experiment tally assessed and fully modeled using the MCNP5 code. The experimental measurements were based on the cadmium ratio in the irradiation ports of the re actor, flux profiling using nickel wire, and gamma dose measurements using thermo luminescence dosimeter. Full 3-D MCNP5 reactor model was developed to obtain the neutron flux distributions of the en tire re actor core and to com pare it with the measured flux focusing at the irradiation ports. Integration of all these anal y sis pro vided the up dated comprehensive neutron-gamma flux maps of the existing irradiation facilities of the University of Utah TRIGA reactor.