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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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Principais autores: Efrizon Umar, Nathanael Panagung Tandian, Ahmad Ciptadi Syuryavin, Anwar Ilmar Ramadhan, Joko Hadi Prayitno
Format: Artigo
Sprog:Inglês
Udgivet: MDPI AG 2022-06-01
Serier:Fluids
Fag:
CFD code
developing regime
convection
sub-channel
vertical cylinder
Online adgang:https://www.mdpi.com/2311-5521/7/6/207
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