UWFDM-1408 3-D Modeling of Neutron Wall Loading, Tritium Breeding Ratio, and Nuclear Heating Distribution for ARIES-ACT-DCLL Design

Accurate neutronic characterizations of fusion power plant designs are essential in determining their operational parameters. The neutron wall loading (NWL), tritium breeding ratio (TBR), and nuclear heating distribution are parameters that must be determined for adequate shielding and protection and fuel self-sustainability of a fusion power plant. After determining the NWL for the first wall (FW), radial builds were designed to satisfy the corresponding shielding requirements. Using the DAGMC code to couple solid-modeling geometry software with Monte Carlo radiation transport, these parameters were determined for the ARIES-ACT-DCLL design. The peak NWL values are 4.0 MW/m for the inboard FW, 5.5 MW/m for the outboard FW, and 2.2 MW/m for the divertor. The degradation of the tritium breeding based on the addition of individual design elements to the 3-D model calculated a final TBR of 1.05. Analysis of the nuclear heating determined the energy multiplication factor to be 1.1.