Activation Calculation Comparison for FISPACT-II, ORIGEN, and OpenMC

The increasing potential of fusion as an energy source highlights the importance of engineering considerations for fusion systems. One concern for fusion devices designed for energy generation is the activation of materials because of higher fusion power density than research fusion devices (which leads to higher neutron fluence). Additionally, when using a deuterium-tritium neutron source of 14.06 MeV, large uncertainties exist with accurately predicting the activated material characteristics in nuclear data: isotopics, decay heat, and radioactivity. This paper presents an additional comparison of two codes-OpenMC and ORIGEN-used for activation experiments on various materials at the Fusion Neutron Source facility at the Japan Atomic Energy Agency. For this work, we develop a Python wrapper to standardize input generation and output processing for code-agnostic activation calculation. This paper discusses methods for nuclear data selection for OpenMC and ORIGEN well as data that have to be added to OpenMC for an accurate activation calculation. Results show as good agreement for most isotopes and sensitivity to nuclear data.