研究開発段階発電用原子炉の特徴を考慮した保守管理の提案 (3) 配管支持構造物への適用事例
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features (3) Application to piping support
相澤 康介 Kosuke AIZAWA 髙屋 茂 Shigeru TAKAYA 近澤 佳隆 Yoshitaka CHIKAZAWA 田川 明広 Akihiro TAGAWA 久保 重信 Shigenobu KUBO
maintenance management piping support reactor at R&D stage sodium cooled reactor
One of important mission of nuclear power plants (NPP) at R&D stage is to develop maintenance program for commercial reactors step by step securing safety. Basic principles of maintenance management for NPP at R&D stage were proposed. In this paper, applications for maintenance program on piping support of prototype sodium cooled fast breeder reactor Monju are studied on the basis of the proposed basic principles of maintenance management for NPP at R&D stage.