Browsing Faculty of Energy Systems & Nuclear Science by Subject "Heat-transfer coefficient"
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Steam-reheat option for supercritical-water-cooled reactors
(2010-12-01)SuperCritical-Water-cooled Reactors (SCWRs) are being developed as one of the Generation-IV nuclear-reactor concepts. Main objectives of the development are to increase thermal efficiency of a Nuclear Power Plant (NPP) and ...