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Study on supercritical fluids in an intermediate heat exchanger for an SCWR hydrogen cogeneration system
(2015-12-01)
SuperCritical Water-cooled Reactors (SCWRs) are one of six Generation-IV nuclear reactor concepts under development worldwide. SCWRs benefit from an increase in thermal efficiency due to the reactor coolant operating above ...
Specifics of forced-convection heat transfer to supercritical water flowing upward in annular and bundle flow geometries
(2016-08-01)
Since annulus- and bundle-flow geometries impede coolant flow, heat transfer to the coolant would occur differently than in bare tubes. The main objective of this work is to propose and verity a universal method to accurately ...
Developing 1-D heat transfer correlations for supercritical water and carbon dioxide in vertical tubes
(2014-03-01)
Taking into account the expected increase in global energy demands and increasing climate change issues, there is a pressing need to develop new environmentally sustainable energy systems. Nuclear energy will play a major ...
Conceptual design of a thermal hydraulic loop for multiple test geometries at supercritical conditions named supercritical phenomena experimental test apparatus (SPETA)
(2012-04-01)
The efficiency of nuclear reactors can be improved by increasing the operating pressure of current nuclear reactors. Current CANDU-type nuclear reactors use heavy water as coolant at an outlet pressure of up to 11.5 MPa. ...
Development of a heat-transfer correlation for supercritical water in supercritical water-cooled reactor applications
(2009-12-01)
A large set of experimental data, obtained in Russia, was analyzed and a new heat-transfer correlation for supercritical water was developed. This experimental dataset was obtained within conditions similar to those for ...