Comparison between simulations using the PHITS code and activated materials analysis toward JT-60SA radiation safety assessment

In the present study, a comparison between simulations using the PHITS code and activated material analysis of JT-60U have been performed. Neutron transport has been simulated using the Monte Carlo methods PHITS to determine the neutron fluency at the irradiation position. The activated analysis has been complemented by the foil-activation technique. The preliminary accuracy assessment of these PHITS simulations has been confirmed by comparing the reaction rates of gold, cobalt, and nickel foil activation. The simulation results by PHITS consisted with the measured reaction rate of each foils near the device.