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Preliminary Investigation of Heat-Transfer...
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Preliminary Investigation of Heat-Transfer Correlation for Upward Flow of CO2 at Supercritical Pressure

Abstract

The development of Generation IV nuclear reactors is an ongoing worldwide interdisciplinary effort. Canada is involved with the development of the SuperCritical Water-cooled Reactor (SCWR). One of the numerous engineering challenges associated with this development is to ensure intensive and stable heat transfer to SuperCritical Water (SCW) in a core. It is very important to develop sophisticated theoretical models to improving understanding of …

Authors

Saltanov E; Pioro I; Harvel G

Pagination

pp. v006t16a037-v006t16a037

Publisher

ASME International

Publication Date

July 29, 2013

DOI

10.1115/icone21-16399

Name of conference

Volume 6: Beyond Design Basis Events; Student Paper Competition