軽水型原子炉におけるプロアクティブ材料経年劣化研究課題
英字タイトル:
Proactive Material Degradation Research Subjects for LWR
著者:
庄子 哲雄 Tetsuo SHOJI 竹田 陽一 Yoichi TAKEDA 国谷 治郎 Jiro KUNIYA ピーター・フォード Peter FORD ピーター・スコット Peter SCOTT
発刊日:
公開日:
BWRFlow Assisted CorrosionLong Term OperationLWRPlant AgingProactive materials degradation assessmentProactive materials degradation managementPWRStress Corrosion Cracking
Proactive Material Degradation Research Subjects for LWR
著者:
庄子 哲雄 Tetsuo SHOJI 竹田 陽一 Yoichi TAKEDA 国谷 治郎 Jiro KUNIYA ピーター・フォード Peter FORD ピーター・スコット Peter SCOTT
発刊日:
公開日:
カテゴリ: 論文
キーワードタグ:BWRFlow Assisted CorrosionLong Term OperationLWRPlant AgingProactive materials degradation assessmentProactive materials degradation managementPWRStress Corrosion Cracking
概要
The predictive and preventive maintenance technologies are of increasingly importance for the long term operation (LTO) of Light Water Reactor (LWR) plants. In order for the realization of LTO, it is essential to prevent the degradation phenomena from emergence using proper maintenance programs on foreseeing the phenomena and evaluating their rates of development. In this paper, the research subjects which should be required for the aging degradation phenomenon in LWR structural materials which were discussed in the Proactive Aging Management Group Meeting of Tohoku-Hokkaido Research Cluster of NISA Project are introduced
