Prediction and Analysis of Onset of Turbulent Convective Heat Transfer Deterioration in Supercritical Water Flows
2007 (English)In: Proceedings of the International Congress on Advances in Nuclear Power Plants, 2007, 1552-1558 p.Conference paper (Refereed)
Supercritical water is considered as a coolant in one of the six systems defined as Generation IV reactors. Such reactor will operate at pressures higher than the thermodynamic critical point of water (374 °C and 22.1 MPa), allowing for a significant increase of the system thermal efficiency. During normal operation no boiling crisis will occur, thereby sudden temperature excursions will be avoided. However, since the physical properties of supercritical fluids change rapidly with temperature in the pseudocritical region, the local heat transfer coefficient may still show unusual behaviour depending upon the heat flux. It can be either enhanced or deteriorated, depending on flow conditions and heat flux. This phenomenon has to be properly modelled in order to correctly predict the cladding temperatures in the core of the nuclear reactor.
Place, publisher, year, edition, pages
2007. 1552-1558 p.
Boiling crisis, Cladding temperatures, Convective heat-transfer, Critical point, Generation IV reactors, International Congress on Advances in Nuclear Power Plants, Local heat transfer coefficient, Normal operation, Nuclear renaissance, On flow, Physical Properties, Prediction and analysis, Supercritical water, Temperature excursions
Research subject SRA - Energy
IdentifiersURN: urn:nbn:se:kth:diva-80443ScopusID: 2-s2.0-52349085119ISBN: 978-160423871-6OAI: oai:DiVA.org:kth-80443DiVA: diva2:496332
QC 201202282012-02-092012-02-092014-10-21Bibliographically approved