In the framework of generation IV international forum (GIF), safety design criteria (SDC) and safety design guideline (SDG) for the generation IV sodium-cooled fast reactors (SFRs) have been developed as part of the worldwide deployment of SFRs. Japan Atomic Energy Agency (JAEA) and the Mitsubishi FBR Systems, Inc. (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-integrated Intermediate Heat Exchanger (IHX) is evaluated as a safety measure for the advanced loop-type SFR. Furthermore, maintainability and reparability of the safety measures are taken into account for the advanced loop-type SFR design study. The pump-integrated IHX has been modified to satisfy these requirements. This paper describes the modifications to withstand severe earthquake, primary coolant leak and sodium-water reaction. Also, this paper includes evaluations of thermal transient, structural vibration with pump rotation and wear-out of IHX tubes for they have been adversely affected by the modifications.
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2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5002-2
PROCEEDINGS PAPER
Development of the Pump-Integrated Intermediate Heat Exchanger in Advanced Loop-Type Sodium-Cooled Fast Reactor for Demonstration
Katsunori Amano,
Katsunori Amano
Japan Atomic Energy Agency, Oarai, Japan
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Yasuhiro Enuma,
Yasuhiro Enuma
Japan Atomic Energy Agency, Oarai, Japan
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Satoshi Futagami,
Satoshi Futagami
Japan Atomic Energy Agency, Oarai, Japan
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Tomoyuki Inoue,
Tomoyuki Inoue
Mitsubishi FBR Systems, Inc., Tokyo, Japan
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Sota Watanabe
Sota Watanabe
Mitsubishi FBR Systems, Inc., Tokyo, Japan
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Katsunori Amano
Japan Atomic Energy Agency, Oarai, Japan
Yasuhiro Enuma
Japan Atomic Energy Agency, Oarai, Japan
Satoshi Futagami
Japan Atomic Energy Agency, Oarai, Japan
Tomoyuki Inoue
Mitsubishi FBR Systems, Inc., Tokyo, Japan
Sota Watanabe
Mitsubishi FBR Systems, Inc., Tokyo, Japan
Paper No:
ICONE24-60064, V002T06A004; 7 pages
Published Online:
October 25, 2016
Citation
Amano, K, Enuma, Y, Futagami, S, Inoue, T, & Watanabe, S. "Development of the Pump-Integrated Intermediate Heat Exchanger in Advanced Loop-Type Sodium-Cooled Fast Reactor for Demonstration." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues. Charlotte, North Carolina, USA. June 26–30, 2016. V002T06A004. ASME. https://doi.org/10.1115/ICONE24-60064
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