The focus of this research was to ensure radiation safety within the UMass Lowell Research Reactor beam port enclosure facility by determining neutron spectra and corresponding dose rates as well as developing a computer simulation model of the facility. This research involved the investigation of neutron spectra by activation foils, Bonner spheres, and by using a Monte Carlo Windows (TM) based particle transport simulator (MCNP). The MCNP simulations describe the spectra at the sample positioning transfer arm, at an activation foil location, and at a mobile platform location. Dose equivalent rates were measured by various passive dosimeters (OSL, TLD, and CR-39) and a tissue equivalent proportional counter. The determination of spectra and dose profiles in the beam port enclosure facility allows the Radiation Safety Office to better monitor and control worker exposures.