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Similarity evaluation of the pump simulation loop in STELLA-2 for conservation of mechanical sodium pump characteristics

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dc.contributor.authorYoon, J.-
dc.contributor.authorLee, J.-
dc.contributor.authorEoh, J.-
dc.contributor.authorKim, H.-
dc.contributor.authorKim, D.E.-
dc.date.accessioned2023-01-04T07:31:01Z-
dc.date.available2023-01-04T07:31:01Z-
dc.date.issued2023-01-
dc.identifier.issn1738-5733-
dc.identifier.issn2234-358X-
dc.identifier.urihttps://scholarworks.gnu.ac.kr/handle/sw.gnu/29974-
dc.description.abstractThe STELLA-2 is a large-scale sodium thermal-hydraulic integral effect test facility and supports the development of PGSFR. The facility adopted Pump Simulation Loop System (PSLS) concept for the mechanical sodium pump in the reference reactor to control and to measure the primary sodium flow. Since the component (mechanical pump) is replaced by the loop, it is very important to evaluate the similarity between the pump and the loop. In this paper, to simulate the characteristic of the mechanical sodium pump, the pressure loss along the various options of the loop was evaluated and the comprehensive validity of each design options was analyzed. Using the similarity criteria based on the Richardson number and Euler number conservation, the PSLS design was finalized and the result was within the acceptable error range. Finally, the result of this study was used for construction of the overall facility, STELLA-2. © 2022 Korean Nuclear Society-
dc.format.extent11-
dc.language영어-
dc.language.isoENG-
dc.publisherKorean Nuclear Society-
dc.titleSimilarity evaluation of the pump simulation loop in STELLA-2 for conservation of mechanical sodium pump characteristics-
dc.title.alternativeSimilarity evaluation of the pump simulation loop in STELLA-2 for conservation of mechanical sodium pump characteristics-
dc.typeArticle-
dc.publisher.location대한민국-
dc.identifier.doi10.1016/j.net.2022.09.021-
dc.identifier.scopusid2-s2.0-85139272569-
dc.identifier.wosid000926669300001-
dc.identifier.bibliographicCitationNuclear Engineering and Technology, v.55, no.1, pp 353 - 363-
dc.citation.titleNuclear Engineering and Technology-
dc.citation.volume55-
dc.citation.number1-
dc.citation.startPage353-
dc.citation.endPage363-
dc.type.docTypeArticle-
dc.identifier.kciidART002921510-
dc.description.isOpenAccessY-
dc.description.journalRegisteredClassscie-
dc.description.journalRegisteredClassscopus-
dc.description.journalRegisteredClasskci-
dc.relation.journalResearchAreaNuclear Science & Technology-
dc.relation.journalWebOfScienceCategoryNuclear Science & Technology-
dc.subject.keywordPlusHEAT-
dc.subject.keywordPlusPERFORMANCE-
dc.subject.keywordPlusDESIGN-
dc.subject.keywordAuthorPGSFR-
dc.subject.keywordAuthorPressure loss similarity-
dc.subject.keywordAuthorPump simulation loop-
dc.subject.keywordAuthorSTELLA-2-
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