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
著者:
髙屋 茂 Shigeru TAKAYA 近澤 佳隆 Yoshitaka CHIKAZAWA 田中 正暁 Masaaki TANAKA
発刊日:
公開日:
Degradation MechanismGraded ApproachOperational ExperienceSodium-Cooled Fast Reactor
概要
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.
