Design evaluation of serpentine-tube integrated steam generator for sodium-cooled fast reactor
  • Lee, Jewhan
  • Kim, Namhyeong
  • Yoon, Jung
  • Im, Gyeongseo
  • Eoh, Jaehyuk
  • ... Kim, Hyungmo
  • 외 1명
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초록

The elimination of the intermediate heat transfer system (IHTS) in the sodium-cooled fast reactor (SFR) has long been a goal among researchers, who have extensively developed concepts for simplifying, replacing, or eliminating the IHTS. One such concept involves an integrated steam generator with an additional heat transfer fluid. This paper proposes a heat exchanger with a serpentine-tube arrangement that functions as an integrated steam generator in the primary pool of the SFR. The thermal–hydraulic performance and structural integrity are analyzed, and the transient characteristics under various accident conditions are evaluated. Finally, design improvements are suggested to enhance economic efficiency and applicability by reducing the total volume of hardware. © 2024 Elsevier Ltd

키워드

Computational fluid dynamicsHeat transferNuclear reactor safetySerpentine-tube integrated steam generatorSodium-cooled fast reactorStructural integrity
제목
Design evaluation of serpentine-tube integrated steam generator for sodium-cooled fast reactor
저자
Lee, JewhanKim, NamhyeongYoon, JungIm, GyeongseoEoh, JaehyukJo, HangJinKim, Hyungmo
DOI
10.1016/j.anucene.2024.111133
발행일
2025-04
유형
Article
저널명
Annals of Nuclear Energy
213