Search
Now showing items 1-3 of 3
Study on linking a SuperCritical water-cooled nuclear reactor to a hydrogen production facility
(2011-07-01)
The SuperCritical Water-cooled nuclear Reactor (SCWR) is one of six Generation-IV nuclear-reactor concepts currently being designed. It will operate at pressures of 25 MPa and temperatures up to 625°C. These operating ...
Heat-transfer analysis of double-pipe heat exchangers for indirect-cycle SCW NPP
(2012-04-01)
SuperCritical-Water-cooled Reactors (SCWRs) are being developed as one of the Generation-IV nuclear-reactor concepts. SuperCritical Water (SCW) Nuclear Power Plants (NPPs) are expected to have much higher operating parameters ...
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 ...