圧力容器の健全性評価に関する研究 ?照射脆化予測のあいまいさの一考察?


英字タイトル:
Integrity Assessment of Reactor Pressure Vessel Steel: Ambiguity of Predicting Irradiation Embrittlement
著者:
中筋 俊樹 森下 和功 (京都大)
発刊日:
公開日:
カテゴリ: 第15回
キーワードタグ:

概要

The reactor pressure vessel (RPV) has the function as the reactor coolant pressure boundary (RCPB) which is damaged by neutron irradiation embrittlement. In order to keep the function, maintenance activities should be done to manage irradiation embrittlement. In this study, we investigated the precision of the prediction model of irradiation embrittlement applied by Japan’s nuclear regulation. Finally, we discussed the precision required for adequate management.


全文掲載のPDFファイルダウンロード