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dc.contributor.authorOsigwe, Emmanuel O.
dc.contributor.authorGad-Briggs, Arnold
dc.contributor.authorNikolaidis, Theoklis
dc.contributor.authorPilidis, Pericles
dc.contributor.authorSampath, Suresh
dc.date.accessioned2022-02-04T14:26:00Z
dc.date.available2022-02-04T14:26:00Z
dc.date.copyright2020/01/29/
dc.date.issued2020
dc.identifier.issn2332-8983
dc.identifier.otherners_006_02_021101.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4273646
dc.description.abstractA significant hurdle in the development of performance simulation tools to analyze and evaluate nuclear power plants (NPP) is finding data relating to component performance maps. As a result, engineers often rely on an estimation approach using various scaling techniques. The purpose of this study is to determine the component characteristics of a closed-cycle gas turbine NPP using the existing component maps with the corresponding design data. The design data are applied for different working fluids using a multifluid scaling approach to adapt data from one component map into another. The multifluid scaling technique described herein was developed as an in-house computer simulation tool. This approach makes it easy to theoretically scale the existing maps using similar or different working fluids without carrying out a full experimental test or repeating the whole design and development process. The results of selected case studies show a reasonable agreement with the available data. The analyses intend to aid the development of cycles for Generation IV NPPs specifically gas-cooled fast reactors (GFRs) and very high-temperature reactors (VHTRs).
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titlePerformance Simulation to Understand the Effects of Multifluid Scaling of Gas Turbine Components for Generation IV Nuclear Power Plants
dc.typeJournal Paper
dc.journal.volume6
dc.journal.issue2
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4044406
dc.page21101
dc.treeJournal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 002
dc.contenttypeFulltext


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