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Thermal-hydraulic analysis of a representative Westinghouse lead-cooled fast reactor fuel bundle using CFD.

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Title: Thermal-hydraulic analysis of a representative Westinghouse lead-cooled fast reactor fuel bundle using CFD.
Authors: Wilson, D.1, dean.wilson@manchester.ac.uk, Iacovides, H.1, Tatli, E.2,3, Stansbury, C.2, Ferroni, P.2
Source: Nuclear Engineering & Design; Aug2025, Vol. 439, pN.PAG-N.PAG, 1p
Database: Applied Science & Technology Source
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  Availability: 0
Header DbId: aci
DbLabel: Applied Science & Technology Source
An: 185200615
AccessLevel: 2
PubType: Academic Journal
PubTypeId: academicJournal
PreciseRelevancyScore: 0
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  Data: Thermal-hydraulic analysis of a representative Westinghouse lead-cooled fast reactor fuel bundle using CFD.
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  Data: <searchLink fieldCode="AU" term="%22Wilson%2C+D%2E%22">Wilson, D.</searchLink><relatesTo>1</relatesTo>, <i>dean.wilson@manchester.ac.uk</i><br /><searchLink fieldCode="AU" term="%22Iacovides%2C+H%2E%22">Iacovides, H.</searchLink><relatesTo>1</relatesTo><br /><searchLink fieldCode="AU" term="%22Tatli%2C+E%2E%22">Tatli, E.</searchLink><relatesTo>2,3</relatesTo><br /><searchLink fieldCode="AU" term="%22Stansbury%2C+C%2E%22">Stansbury, C.</searchLink><relatesTo>2</relatesTo><br /><searchLink fieldCode="AU" term="%22Ferroni%2C+P%2E%22">Ferroni, P.</searchLink><relatesTo>2</relatesTo>
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  Data: <searchLink fieldCode="JN" term="%22Nuclear+Engineering+%26+Design%22">Nuclear Engineering & Design</searchLink>; Aug2025, Vol. 439, pN.PAG-N.PAG, 1p
PLink https://search.ebscohost.com/login.aspx?direct=true&site=eds-live&db=aci&AN=185200615
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      – Type: doi
        Value: 10.1016/j.nucengdes.2025.114117
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      – Code: eng
        Text: English
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      – TitleFull: Thermal-hydraulic analysis of a representative Westinghouse lead-cooled fast reactor fuel bundle using CFD.
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              Text: Aug2025
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              Y: 2025
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              Value: 439
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