Now showing items 1-6 of 6
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 ...
Assessment of FLUENT CFD code as an analysis tool for SCW applications
Chosen as one of six Generation‒IV nuclear-reactor concepts, SuperCritical Water-cooled Reactors (SCWRs) are expected to have high thermal efficiencies within the range of 45 ‒ 50% owing to the reactor‟s high pressures and ...
Electrohydrodynamic enhancement of extraterrestrial capilliary pumped loops for nuclear applications
This work examines electrohydrodynamic enhancement of capillary pump loops (CPL) for use in extraterrestrial nuclear applications. A capillary pump uses capillary action through a porous wick to transport heat and mass. ...
Conceptual design for a re-entrant type fuel channel for supercritical water-cooled nuclear reactors
Current CANDU-type nuclear reactors use a once-through fuel-channel with an annulus gas insulating it from the moderator. The current reference design for a CANDU-type SuperCritical Water-Cooled Reactor (SCWR) is to eliminate ...
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 ...
CFD determination of fluid and geometry related localized heat transfer phenomena for supercritical water flow
The proposed concept of Supercritical Water-cooled Reactor (SCWR) as part of the Generation IV International Forum aims to improve the thermal efficiency over current power plants by utilizing cooling water at pressures ...