Neutronic and Thermalhydraulic Evaluation of Annular Fuel in PWR with Three Different Nanofluids

In pressurized nuclear reactors, one of the fuel design principles is the fuel centerline temperature limit. Since the thermal conductivity of UO2 is not high, the temperature increases rapidly from the fuel surface to the fuel center. To overcome this limitation, the use of annular type fuels inste...

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Bibliographic Details
Main Author: Ali Tiftikçi
Format: Article
Language:English
Published: Sakarya University 2022-08-01
Series:Sakarya Üniversitesi Fen Bilimleri Enstitüsü Dergisi
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Online Access:https://dergipark.org.tr/tr/download/article-file/2279735
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