Welcome to Research Group for Radiation Materials Engineering. Our research group studies the Irradiation Assisted Stress Corrosion Cracking (IASCC) and Stress Corrosion Cracking (SCC) in nuclear power plants. As a neutral independent organization, we investigate the causes of damage created in materials actually used in nuclear power plant.
We also investigate the irradiation effects of structural materials used in nuetron irradiation environment, such as fusion reactor blanket materials irradiated to high dose and stainless steels under high burn-up condition. Our research themes include "fundumental process of radiation damage formation", "microstructural evolution due to damage accumulation", and "property change of in-core components due to irradiation". The objectives of the research is to develop radiation-resistant materials and to develop in-core component design taking account of irradiation-induced change of material properties.
In Research Group for Nuclear Materials Modeling, the objective is to clarify the mechanisms and establish the prediction procedures for degradation phenomena of nuclear structural materials and fuels under combined environments by computational methods. We will construct the mechanistic models by comparison between multi-scale simulation and extremely precise experiments. In future, we aim to develop the next-generation nuclear structural materials and fuels by the simulation based on the models.