Physics-Informed Plasma Profile Input for OpenMC Fusion Neutronics

In this contribution, we present a new package for creating fixed-source neutron source profiles for OpenMC from both simulated and experimental tokamak plasma states. Realistic fusion neutronics simulations ultimately require information on plasma equilibrium, plasma transport, and a realistic source geometry. In this work, a new flexible tool is presented that allows the user to input detailed plasma states to create OpenMC neutron sources for fixed-source problems. The toolkit accepts radially and poloidally varying plasma density and temperature profiles from either experimental or simulated plasma states. Either D-T or D-D reaction rates may be used in the case of predictive or experimental simulations, respectively. This process provides a realistic neutron source that is intrinsically coupled to tokamak plasma physics parameters.