研究開発段階発電用原子炉に適した保守管理に関する検討,2; 配管保全の事例検討

Study on maintenance management suitable for NPP at R&D stage, 2; Case study on piping maintenance

近澤 佳隆  ; 高屋 茂  ; 林田 貴一*; 田川 明広 ; 久保 重信 ; 山下 厚*

Chikazawa, Yoshitaka; Takaya, Shigeru; Hayashida, Kiichi*; Tagawa, Akihiro; Kubo, Shigenobu; Yamashita, Atsushi*

研究開発段階発電用原子炉(研開炉)の特徴を考慮した保守管理の基本要件について検討した。「原子炉発電所の保守管理規程」の研開炉への適用性を検討し、研開炉での要求事項や考慮事項をまとめた。本報告では提案した研開炉の保守管理の考え方に基づき、ナトリウム冷却高速炉の特有な機器である原子炉冷却材バウンダリの保全計画(点検計画)を検討した例を示す。

A maintenance management suitable to nuclear power plants (NPP) at R&D stage was discussed. Objectives of maintenance management of NPP at R&D stage was first clarified. Next, applicability of codes for maintenance management of commercial NPP to NPP at R&D stage was discussed. Then, requirements and consideration for maintenance management of NPP at R&D stage was proposed. In this paper, an example that the proposal was applied to setting maintenance program of sodium-cooled fast reactor was presented.