NuScale Power LLC (NuScale) is developing safer, smaller, scalable pressurized water reactor technology under the U.S. Department of Energy's cost-sharing program. The determination of vessel damage due to irradiation requires the spatial determination of energy-dependent neutron flux for each location of interest by combining calculations and measurements. The effect of the fast neutron (E > 1 MeV) flux level and displacements per atom (DPA) are significantly important parameters for predicting the core component and vessel embrittlement per U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide 1.99, Revision 2 and Revision 3 (draft) in commercial reactors. The Monte Carlo transport method is acceptable to NRC for determining the best-estimate neutron fluence in vessels per NRC Regulatory Guide 1.190. NuScale uses the three-dimensional Monte Carlo N-Particle code, Version 1.0, to perform neutron-gamma transport calculations with the point-wise cross-section Evaluated Nuclear Data Files/B-VII.1 data library and standard iron DPA cross-section data from ASTM E693, Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA). A three-dimensional Monte Carlo N-Particle model of the NuScale reactor module including the core, reflector, core barrel, reactor pressure vessel, and containment vessel has been developed. This paper presents a general discussion of NuScale calculational neutron fluence methodology for evaluating neutron flux (neutrons/cm2 · s−1) and the DPA rate (displacements/atom · s−1) at the lower core plate, upper core plate, core reflector, core barrel, pressure vessel and containment vessel at 0.25T, 0.5T, 0.75T, and 4/4T, respectively. The results of the best-estimate fluence analysis to support the Design Certification Application and technical details are included in the licensing technical report that had been submitted to the NRC for review.