In the materials used in nuclear power systems, collisions of neutrons generated by nuclear reactions cause atoms to be knocked out of their original lattice locations and aggregate, and voids where atoms have displaced. Macroscopic properties such as reduction in strength and toughness of the material and volumetric expansion also change. We have been engaged on both various experimental studies and simulation studies to elucidate the mechanism and behavior prediction of the property change of nuclear materials, while trying to combine experimental studies and computational science methods.

In experimental research, research on candidate materials for accident-tolerant fuel (ATF) cladding tubes, which has been studied and developed worldwide since the Fukushima 1F accident, basic research aimed at elucidating the mechanism of stress corrosion cracking (SCC) and irradiation damage. In addition, in computer simulation research, in order to predict the macroscopic mechanical properties of actual materials, we are proceeding with direct analysis of defect structures using large-scale atomic simulation technology using large-scale computers and machine learning potential.

In addition, we are also conducting experimental research on the compatibility and irradiation effects of materials and liquid metals used in the accelerator-driven system (ADS), which is expected as a partitioning and transmutation technology.