Experimental identification of pressure drop characteristics at the shell side of an intermediate heat exchanger inside a prototype generation-IV sodium-cooled fast reactor
DC Field | Value | Language |
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dc.contributor.author | Kong, Minsuk | - |
dc.contributor.author | Kim, Woo Shik | - |
dc.contributor.author | Chung, Heung June | - |
dc.contributor.author | Choi, HaeSeob | - |
dc.contributor.author | Kim, Joongwoon | - |
dc.contributor.author | Lee, Tae Ho | - |
dc.contributor.author | Euh, Dong-Jin | - |
dc.date.available | 2020-10-20T06:43:58Z | - |
dc.date.created | 2020-06-10 | - |
dc.date.issued | 2019-07 | - |
dc.identifier.issn | 0029-5493 | - |
dc.identifier.uri | https://scholarworks.bwise.kr/gachon/handle/2020.sw.gachon/78557 | - |
dc.description.abstract | The flow characteristics at the shell side of a prototype intermediate heat exchanger (p-IHX) in a prototype generation-IV sodium-cooled fast reactor (PGSFR) were investigated experimentally in this study. The shell side of the p-IHX consisted of an inlet window, tube bundles, grid plates, and an exit flow channel. Two different test facilities were newly constructed to identify the pressure drop characteristics due to the complicated configuration with minimized scaling distortion. An intermediate heat exchanger test loop for PGSFR (iHELP) was constructed to characterize the flow resistance of the tube bundle regions with the grid plates and inlet window. The iHELP test section with a slab-shaped cross section was manufactured with a 1/29.6 vol scale ratio by preserving the height of the p-IHX. The hydraulic diameter at the tube bundle regions, the porosity of the grid plates, and the configuration of the tube bundles were conserved. In addition, the Reynolds number was preserved, which determined the flow rate conditions for the iHELP experiments. To investigate the pressure drop characteristics of the exit flow channel (EC), an intermediate heat exchanger test loop for the exit flow channel (IEC) was built with a 1/5 linearly reduced length scale by preserving the geometry of the flow path based on the EC of the p-IHX. The Euler number was conserved with a 1/8 Reynolds number ratio corresponding to a 1/1 flow velocity ratio to the p-IHX for dynamic similarity. By using each test facility the experimental pressure drop data satisfying the experimental uncertainty requirements were obtained separately for the bundle and exit channel regions. The pressure drop at the shell side of the p-IHX under a wide range of flow rate conditions was determined by using the pressure drop results from the iHELP and the IEC test facilities, which would be useful in improving and validating the pressure drop correlations in the IHX design computational code (SHXSA). | - |
dc.language | 영어 | - |
dc.language.iso | en | - |
dc.publisher | ELSEVIER SCIENCE SA | - |
dc.relation.isPartOf | NUCLEAR ENGINEERING AND DESIGN | - |
dc.title | Experimental identification of pressure drop characteristics at the shell side of an intermediate heat exchanger inside a prototype generation-IV sodium-cooled fast reactor | - |
dc.type | Article | - |
dc.type.rims | ART | - |
dc.description.journalClass | 1 | - |
dc.identifier.wosid | 000466406100016 | - |
dc.identifier.doi | 10.1016/j.nucengdes.2019.03.013 | - |
dc.identifier.bibliographicCitation | NUCLEAR ENGINEERING AND DESIGN, v.348, pp.177 - 186 | - |
dc.description.isOpenAccess | N | - |
dc.citation.endPage | 186 | - |
dc.citation.startPage | 177 | - |
dc.citation.title | NUCLEAR ENGINEERING AND DESIGN | - |
dc.citation.volume | 348 | - |
dc.contributor.affiliatedAuthor | Kong, Minsuk | - |
dc.type.docType | Article | - |
dc.subject.keywordAuthor | Sodium-cooled fast reactor | - |
dc.subject.keywordAuthor | Intermediate heat exchanger | - |
dc.subject.keywordAuthor | Pressure drop | - |
dc.subject.keywordAuthor | Tube bundle region | - |
dc.subject.keywordAuthor | Grid plate | - |
dc.subject.keywordAuthor | Exit flow channel | - |
dc.relation.journalResearchArea | Nuclear Science & Technology | - |
dc.relation.journalWebOfScienceCategory | Nuclear Science & Technology | - |
dc.description.journalRegisteredClass | scie | - |
dc.description.journalRegisteredClass | scopus | - |
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