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 ; 高屋 茂  ; 近澤 佳隆  ; 田川 明広 ; 久保 重信 

Aizawa, Kosuke; Takaya, Shigeru; Chikazawa, Yoshitaka; Tagawa, Akihiro; Kubo, Shigenobu

研究開発段階発電用原子炉の特徴を考慮した保守管理が提案されている。本報告では、提案されている研開炉の保守管理の考え方をナトリウム冷却型の高速増殖原型炉「もんじゅ」の1次系主配管支持構造物に適用した検討結果を示す。

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.