Design of A scale-down experimental model for SFR reactor vault cooling system performance analyses
DC Field | Value | Language |
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dc.contributor.author | Kim K.M. | - |
dc.contributor.author | Hwang J.-H. | - |
dc.contributor.author | Wongwises S. | - |
dc.contributor.author | Jerng D.-W. | - |
dc.contributor.author | Ahn H.S. | - |
dc.date.available | 2020-04-03T04:55:34Z | - |
dc.date.issued | 2020-08 | - |
dc.identifier.issn | 1738-5733 | - |
dc.identifier.uri | https://scholarworks.bwise.kr/cau/handle/2019.sw.cau/37921 | - |
dc.description.abstract | We propose a scaled-down experimental model of vertical air-natural convection channels by applying the modified Ishii–Kataoka scaling method with the assistance of numerical analyses to the Reactor Vault Cooling System (RVCS) of the Proto-type Gen-IV Sodium-cooled fast reactor (PGSFR) being developed in Korea. Two major non-dimensional numbers (modified Richardson and Friction number) from the momentum equation and Stanton number from the energy balance equation were identified to design the scaled-down experimental model to assimilate thermal-hydraulic behaviors of the natural convective air-cooling channel of RVCS. The ratios of the design parameters in the PGSFR RVCS between the prototype and the scaled-down model were determined by setting Richardson and Stanton number to be unity. The friction number which cannot be determined by the Ishii-Kataoka method was estimated by numerical analyses using the MARS-KS system code. The numerical analyses showed that the friction number with the form loss coefficient of 2.0 in the scale-down model would result in an acceptable prediction of the thermal-hydraulic behavior in RVCS. We also performed experimental benchmarking using the scaled-down model with the MARS-KS simulations to verify the appropriateness of the scale-down model, which demonstrated that the temperature rises and the average air flow velocity measured in the scale-down model. © 2020 Korean Nuclear Society | - |
dc.format.extent | 15 | - |
dc.language | 영어 | - |
dc.language.iso | ENG | - |
dc.publisher | Korean Nuclear Society | - |
dc.title | Design of A scale-down experimental model for SFR reactor vault cooling system performance analyses | - |
dc.type | Article | - |
dc.identifier.doi | 10.1016/j.net.2020.01.005 | - |
dc.identifier.bibliographicCitation | Nuclear Engineering and Technology, v.52, no.8, pp 1611 - 1625 | - |
dc.identifier.kciid | ART002610932 | - |
dc.description.isOpenAccess | Y | - |
dc.identifier.wosid | 000548366800002 | - |
dc.identifier.scopusid | 2-s2.0-85078714734 | - |
dc.citation.endPage | 1625 | - |
dc.citation.number | 8 | - |
dc.citation.startPage | 1611 | - |
dc.citation.title | Nuclear Engineering and Technology | - |
dc.citation.volume | 52 | - |
dc.type.docType | Article | - |
dc.publisher.location | 대한민국 | - |
dc.subject.keywordAuthor | Asymmetric heating | - |
dc.subject.keywordAuthor | Natural convection | - |
dc.subject.keywordAuthor | RVCS | - |
dc.subject.keywordAuthor | Scaling analysis | - |
dc.subject.keywordAuthor | Vertical parallel plate | - |
dc.subject.keywordPlus | THERMAL-RADIATION | - |
dc.subject.keywordPlus | CONVECTION | - |
dc.subject.keywordPlus | EQUATIONS | - |
dc.relation.journalResearchArea | Nuclear Science & Technology | - |
dc.relation.journalWebOfScienceCategory | Nuclear Science & Technology | - |
dc.description.journalRegisteredClass | scie | - |
dc.description.journalRegisteredClass | scopus | - |
dc.description.journalRegisteredClass | kci | - |
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