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,2; 適用事例

Proposal of maintenance management of nuclear power plants at R&D stage by taking account of their features, 2; Case study

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施設(以下、「研開炉」という。)の特徴を考慮して、原子炉施設の安全性確保を最優先としつつ、炉型に適した保守管理技術体系を構築するために実施すべき保守管理に関する検討結果を行った。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 were 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, requirements on maintenance program of NPP at R&D stage were clarified and an example that the proposal was applied to setting maintenance program of sodium-cooled fast reactor was presented.