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Determination of in-service inspection requirements for fast reactor components using System Based Code concept

システム化規格概念を用いた高速炉機器の供用期間中検査要求の設定

高屋 茂; 神島 吉郎*; 町田 秀夫*; 渡辺 大剛*; 浅山 泰

Takaya, Shigeru; Kamishima, Yoshio*; Machida, Hideo*; Watanabe, Daigo*; Asayama, Tai

著者らは、これまでの研究でシステム化規格概念を用いた供用期間中検査(ISI)要求の設定方法を提案した。提案方法は、二つの補完的な評価から成り、一つは構造健全性に着目し、もう一方は安全性に着目している。本研究では、提案手法を用いて、もんじゅのガードベッセル及び炉心支持構造のISI要求について評価した。その結果、非現実的に厳しい想定を課しても、いずれの機器も十分な信頼度を有することが示され、ISI要求の必要はないと判定された。この結果から、提案手法は、プラントの特徴を考慮した効果的で合理的なISIの実現に寄与するものと期待される。

In our previous study, we proposed a new process for determining the in-service inspection (ISI) requirements using the System Based Code concept. The proposed process consists of two complementary evaluations, one focusing on structural integrity and the other on plant safety. In this study, the ISI requirements for a reactor guard vessel (RGV) and core support structure (CSS) of a prototype sodium-cooled fast breeder reactor in Japan (Monju) were investigated using the proposed process. It was shown that both components had sufficient reliability even assuming unrealistic severe conditions. The failure occurrences of these components were practically eliminated. Hence, it was concluded that no ISI requirements were needed for these components. The proposed process is expected to contribute to the realization of effective and rational ISI by properly taking into account plant-specific features.

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パーセンタイル:76.09

分野:Nuclear Science & Technology

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