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CFD Analysis of Convective Heat Transfer in a Vertical Square Sub-Channel for Laminar Flow Regime

The development of new practices in nuclear research reactor safety aspects and optimization of recent nuclear reactors needs knowledge on forced convective heat transfer within sub-channels formed between several nuclear fuel rods or heat exchanger tubes, not only in the fully developed regime but...

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Autori principali: Efrizon Umar, Nathanael Panagung Tandian, Ahmad Ciptadi Syuryavin, Anwar Ilmar Ramadhan, Joko Hadi Prayitno
Natura: Artigo
Lingua:Inglês
Pubblicazione: MDPI AG 2022-06-01
Serie:Fluids
Soggetti:
CFD code
developing regime
convection
sub-channel
vertical cylinder
Accesso online:https://www.mdpi.com/2311-5521/7/6/207
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