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Research Group for Radiation Materials EngineeringS.Yamashita


Since structural materials of nuclear reactor are subjected under various radiation conditions such as high-energy neutron irradiation during reactor operation, the degradation behavior of nuclear structural materials is quite different from that of structural materials used in non-nuclear industry fields. We have been engaged in both experimental investigation and simulation study aiming clarification of degradation mechanism of nuclear structural material and also organically coupled with each other.

As for the experimental investigation, we have been conducted analysis and evaluation for the clarification of stress corrosion cracking (SCC) mechanism with focusing on the influence of long time a thermal aging on SCC initiation in the structural material of boiling water reactor. On the other hand, we have also been performed a simulation study for exploring a direct defect evolution and relationship with mechanical properties by means of massive atomistic simulation technique.

In addition, we have been engaged in material development of accelerator driven subcritical reactor and science & basic study on radiation damage of several types of condensed matters.

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