Browsing Faculty of Energy Systems & Nuclear Science by Subject "Generation IV reactor"
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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 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 ...