Detailed Information

Cited 0 time in webofscience Cited 0 time in scopus
Metadata Downloads

Design evaluation of serpentine-tube integrated steam generator for sodium-cooled fast reactor

Full metadata record
DC Field Value Language
dc.contributor.authorLee, Jewhan-
dc.contributor.authorKim, Namhyeong-
dc.contributor.authorYoon, Jung-
dc.contributor.authorIm, Gyeongseo-
dc.contributor.authorEoh, Jaehyuk-
dc.contributor.authorJo, HangJin-
dc.contributor.authorKim, Hyungmo-
dc.date.accessioned2024-12-30T01:30:17Z-
dc.date.available2024-12-30T01:30:17Z-
dc.date.issued2025-04-
dc.identifier.issn0306-4549-
dc.identifier.issn1873-2100-
dc.identifier.urihttps://scholarworks.gnu.ac.kr/handle/sw.gnu/75265-
dc.description.abstractThe 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-
dc.language영어-
dc.language.isoENG-
dc.publisherElsevier Ltd.-
dc.titleDesign evaluation of serpentine-tube integrated steam generator for sodium-cooled fast reactor-
dc.typeArticle-
dc.publisher.location영국-
dc.identifier.doi10.1016/j.anucene.2024.111133-
dc.identifier.scopusid2-s2.0-85212445541-
dc.identifier.wosid001392659600001-
dc.identifier.bibliographicCitationAnnals of Nuclear Energy, v.213-
dc.citation.titleAnnals of Nuclear Energy-
dc.citation.volume213-
dc.type.docTypeArticle-
dc.description.isOpenAccessN-
dc.description.journalRegisteredClassscie-
dc.description.journalRegisteredClassscopus-
dc.relation.journalResearchAreaNuclear Science & Technology-
dc.relation.journalWebOfScienceCategoryNuclear Science & Technology-
dc.subject.keywordAuthorComputational fluid dynamics-
dc.subject.keywordAuthorHeat transfer-
dc.subject.keywordAuthorNuclear reactor safety-
dc.subject.keywordAuthorSerpentine-tube integrated steam generator-
dc.subject.keywordAuthorSodium-cooled fast reactor-
dc.subject.keywordAuthorStructural integrity-
Files in This Item
There are no files associated with this item.
Appears in
Collections
공학계열 > 기계항공우주공학부 > Journal Articles

qrcode

Items in ScholarWorks are protected by copyright, with all rights reserved, unless otherwise indicated.

Related Researcher

Researcher Kim, Hyung Mo photo

Kim, Hyung Mo
대학원 (기계항공우주공학부)
Read more

Altmetrics

Total Views & Downloads

BROWSE