Now showing items 1-5 of 5
Conceptual design of a thermal hydraulic loop for multiple test geometries at supercritical conditions named supercritical phenomena experimental test apparatus (SPETA)
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. ...
Developing 1-D heat transfer correlations for supercritical water and carbon dioxide in vertical tubes
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 ...
Development of a heat-transfer correlation for supercritical water in supercritical water-cooled reactor applications
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 ...
Study on supercritical fluids in an intermediate heat exchanger for an SCWR hydrogen cogeneration system
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
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 ...