Extensive neutron and gamma-ray measurements were performed in the reflector and primary shield of the NPR, a large power and plutonium production reactor. The measurements yielded fast, epithermal, and thermal-neutron flux and gamma-ray dose distributions through approximately 9 ft of reflector and shield assembly. Emphasis was placed on obtaining absolute flux and dose measurements with respect to reactor power. The measured fluxes and dose rates were compared to those calculated by the removal diffusion theory computer program MAC; a calculation in 18 removal groups and 31 diffusion groups. Agreement is excellent for fast-neutron flux and gamma-ray dose rate in the concrete shield and for thermal and epithermal flux in the graphite reflector. Calculations of thermal and epithermal fluxes in the concrete shield are in lesser agreement with measured values; generally within a factor of 2.