PIRT手法を用いた研究開発段階発電用原子炉の保守管理における要検証劣化メカニズムの抽出方法に関する検討

Study on a method for identifying degradation mechanisms to be validated in maintenance management of R&D-level nuclear power plants using the PIRT process

高屋 茂  ; 近澤 佳隆  ; 田中 正暁  

Takaya, Shigeru; Chikazawa, Yoshitaka; Tanaka, Masaaki

研開炉の保守管理においては、実際のプラント環境でR&D知見等の検証を行うことが重要である。本研究では、PIRT手法を用いて、検証対象とすべき劣化メカニズムの抽出方法を提案するとともに、研開炉のひとつである「もんじゅ」の一次主冷却系配管に試適用した例を紹介する。

In a previous paper, the authors discussed maintenance management suitable to R&D-level nuclear power plants, and made proposals. One of key proposals was to enhance knowledge on potential degradation mechanisms specific to a new reactor type by accumulating operational experience. It was noted that validation of R&D knowledge in actual plant conditions is important. In this study, a method for identifying degradation mechanisms to be validated by the PIRT (Phenomena Identification and Ranking Table) process is proposed to develop effective maintenance plans of R&D-level nuclear power plants based on the graded approach. Furthermore, the applicability of the proposed method is illustrated by an example of application to MONJU that is an R&D-level nuclear power plant of sodium-cooled fast reactors.