CFD Analysis of the Fluid Flow, Heat Transfer and Cladding Oxidation in a PWR Fuel Bundle

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Veröffentlicht in:NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 5 of 9
1. Verfasser: Sheng, Dong-Yuan (VerfasserIn)
Weitere Verfasser: Seidl, Marcus (VerfasserIn), Du, Zhouqi (VerfasserIn)
Pages:18
Format: UnknownFormat
Sprache:eng
Veröffentlicht: 2020
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