A Computational Investigation of Natural Circulation Effects on Heat Transfer Coefficient and Friction Factor

Graduate Thesis Or Dissertation

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Citeable URL: https://ir.library.oregonstate.edu/concern/graduate_thesis_or_dissertations/j67319578

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Attribute Name	Values
Creator	Buskirk, John
Abstract	The nuclear industry has shown a large interest in natural circulation driven passive cooling systems following the Fukushima nuclear accident. Despite this interest, there is no widely used heat transfer correlation or friction factor correlation developed for natural circulation driven flow. A CFD analysis including grid convergence testing using Fluent was performed to determine the applicable flow regimes for classic correlations. This analysis showed that classic heat transfer correlations cannot accurately predict local heat transfer unless heat flux is very small. When heat flux was high, heat transfer coefficients predicted by the Gnielinski correlation were overpredicted by 40+%. Friction factors fell between laminar and turbulent values as expected, but neither correlation was accurate for any condition.
License	Attribution-ShareAlike 4.0 (CC BY-SA 4.0)
Resource Type	Masters Thesis
Date Issued	2020
Degree Level	Master's
Degree Name	Master of Science (M.S.)
Degree Field	Nuclear Engineering
Degree Grantor	Oregon State University
Commencement Year	2020
Advisor	Wu, Qiao Gutowska, Izabela
Committee Member	Marcum, Wade Gess, Joshua
Academic Affiliation	Nuclear Science and Engineering
Declaração de direitos	In Copyright
Publisher	Oregon State University
Peer Reviewed	No
Language	English [eng]

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Miniatura	Título	Data de carga	Acesso	Ações
	BuskirkJohnM2020.pdf	2020-03-23	Público	Baixar