Development of the pump-integrated intermediate heat exchanger in advanced loop-type sodium-cooled fast reactor for demonstration

革新的ループ型ナトリウム冷却高速炉のポンプ組込型IHXの開発

天野 克則; 江沼 康弘  ; 二神 敏  ; 井上 智之*; 渡邊 壮太*

Amano, Katsunori; Enuma, Yasuhiro; Futagami, Satoshi; Inoue, Tomoyuki*; Watanabe, Sota*

GIFにおいてSFRのSDC, SDGの検討が進められている。原子力機構と三菱FBRシステムズは革新的ループ型ナトリウム冷却高速炉の設計を行っており、この中でポンプ組込型IHXの安全対策について評価してきた。更に、保守・補修についても検討されている。ポンプ組込型IHXはこれら要求を満足するために最適化されてきた。本稿では耐震性、Naリーク時のGVの信頼性、Na-水反応時のCSEJの信頼性確保のための最適化検討について述べる。また、この最適化により影響が出る熱過渡、ポンプとの共振、伝熱管摩耗それぞれの評価についても述べる。

In the framework of GIF, SDC and SDG for the generation IV SFRs have been developed in the circumstance of worldwide deployment of SFRs. JAEA and MFBR have been investigating design study of an advanced loop-type SFR to satisfy SDC in the feasibility study of SDG for SFR. In this study, the ability of the pump/IHX in the advanced loop-type SFR for the safety measures has been evaluated. In addition to the safety measures, maintainability and reparability are taken into account in the advanced loop-type SFR design study. The pump/IHX has been modified to satisfy these requirements. This paper describes the modifications for the ability to withstand a severe earthquake, the reliability of the guard vessel in the primary coolant leak, and the reliability of expansion joints in a sodium-water reaction. The evaluations of thermal transient, structural vibration with pump rotation and wear-out of IHX tubes, that has been adversely effected by the modifications, were described as well.