The concept of an innovative plate-type steam generator (SG) for a fast reactor, fabricated using hot isostatic pressing (HIP), was presented. The heat transfer plate, which is assembled with rectangular tubes and fabricated using HIP, is surrounded by a leak-detection layer. The optimum form for the detection layer was determined by crack extension analysis. The concept can be applied in both pool-type and loop-type liquid-metal cooled fast reactors (LMFR). In this report, the fabrication technique is described as applied to a loop-type LMFR. Optimum HIP conditions of [1423K (1150°C), 1200kgf/cm2 (117MPa), 3hours] for modified 9Cr-1Mo steel were determined from HIP tests, tensile tests, and structural inspection. Nickel-type solder (BNi-5) and gold-type solder (BAu-4) were examined as potential joining materials to laminate the heat transfer plates. Tensile test comparisons showed that BAu-4 was superior, so it was used. No problems were observed in the fabrication of a partial model of an SG (HIP of the rectangular tubes, brazing the plates, welding the header, etc.).
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16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4817-5
PROCEEDINGS PAPER
Development of an Innovative Plate-Type SG for Sodium Cooled Fast Reactor: Concept and Test Fabrication
Yoshihisa Nishi,
Yoshihisa Nishi
Central Research Institute of Electric Power Industry, Komae, Tokyo, Japan
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Izumi Kinoshita
Izumi Kinoshita
Central Research Institute of Electric Power Industry, Komae, Tokyo, Japan
Search for other works by this author on:
Yoshihisa Nishi
Central Research Institute of Electric Power Industry, Komae, Tokyo, Japan
Izumi Kinoshita
Central Research Institute of Electric Power Industry, Komae, Tokyo, Japan
Paper No:
ICONE16-48120, pp. 309-317; 9 pages
Published Online:
June 24, 2009
Citation
Nishi, Y, & Kinoshita, I. "Development of an Innovative Plate-Type SG for Sodium Cooled Fast Reactor: Concept and Test Fabrication." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance. Orlando, Florida, USA. May 11–15, 2008. pp. 309-317. ASME. https://doi.org/10.1115/ICONE16-48120
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