Design evaluation of serpentine-tube integrated steam generator for sodium-cooled fast reactor
- Authors
- Lee, Jewhan; Kim, Namhyeong; Yoon, Jung; Im, Gyeongseo; Eoh, Jaehyuk; Jo, HangJin; Kim, Hyungmo
- Issue Date
- Apr-2025
- Publisher
- Elsevier Ltd.
- Keywords
- Computational fluid dynamics; Heat transfer; Nuclear reactor safety; Serpentine-tube integrated steam generator; Sodium-cooled fast reactor; Structural integrity
- Citation
- Annals of Nuclear Energy, v.213
- Indexed
- SCIE
SCOPUS
- Journal Title
- Annals of Nuclear Energy
- Volume
- 213
- URI
- https://scholarworks.gnu.ac.kr/handle/sw.gnu/75265
- DOI
- 10.1016/j.anucene.2024.111133
- ISSN
- 0306-4549
1873-2100
- Abstract
- 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
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