A multiscale viewpoint is introduced into the modeling of radiation damage processes in nucle ar fission and fusion materials, where the processes occur at a wide variety of time and leng th scales. This viewpoint enables us to understand the dose-rate dependence of microstructural changes in materials, which is important for establishment of irradiation correlation rules....
英字タイトル:
Prediction of radiation-induced damage in nuclear materials

A multiscale viewpoint is introduced into the modeling methodology of radiation damage processes in fission and fusion materials, where the p rocesses occur at a wide variety of time and length scales. Attempt is also made to apply this viewpoint to the reactor integrity technology....
英字タイトル:
Multiscale viewpoint of material's degradation due to irradiation and its possible application to the lifetime assessment of nuclear power plants

The prediction of the initiation and propagetion of irradiation-assisted stress corrosion cracking is one of the issues for aging countermeasures in nuclear power plants, and it is desirable to improve the accuracy of the prediction. In recent years, theoretical calculations have shown that irradiation defects introduced by neutron irradiation generate internal stress. Therefore, in this research, we calculate the increase of internal stress using the molecular dynamics method when irradiation defects are f...
英字タイトル:
Influence of internal stress by irradiation defect formation on irradiation assisted stress corrosion cracking

Challenging efforts are discussed to establish an advanced methodology for prediction of material's property and performance changes by irradiation, which will be necessary by all means for the advanced reactor maintenance technology in the future. The changes of material's properties and perfor mance caused by irradiation, such as irradiation-induced hardening, ductility loss, and material's degradation leading to reduction in reactor lifetime, are primarily determined by microstructural changes in materi...
英字タイトル:
How can we predict microstructural changes caused by the multiscale irradiation process occurred in materials havingcomplicated and hierarchical structures?

1.はじめに方法である. 例えば運転開始 60 年後の材料劣化の程度を知りたいとしても,実際の照射場を使ったのでは, 軽水炉高経年化対策のひとつに,原子炉圧力容器鋼 材料照射データの取得に 60年もかかってしまう. そこ の中性子照射脆化対策がある.これは,中性子照射にで,中性子エネルギーや中性子束の高い代替の「加速」 よって徐々に劣化する原子炉圧力容器鋼に対する保全照射場を使うことにより,60年よりも短い年数で材料 計画策定を意味するが,このとき必要になる技術課題照射データを取得する.しかしながら,こう......
英字タイトル:
Establishment of the irradiation correlation rules of reactor materialstowards the advanced plant life management