<sod>The '''supercritical water reactor''' ('''SCWR''') is a [[Generation IV reactor]] concept that uses [[Supercritical fluid|supercritical water]] (referring to the [[Critical point (thermodynamics)|critical point]] of water, not the [[Critical mass (nuclear)|critical mass]] of the nuclear fuel) as the [[working fluid]].<ref>https://www.gen-4.org/gif/jcms/c_40679/technology-system-scwr|accessdate=7 Apr 2016</ref> SCWRs resemble [[light water reactors]] (LWRs) but operate above the thermodynamic critical point of water (374C, 22.1MPa), with a direct once-through cycle like a supercritical boiler. It is different from a [[boiling water reactor]] (BWR) operating at subcritical-pressure with steam-water separation and recirculation of the coolant. The water is always in a single, fluid state at supercritical pressure. The BWR, [[pressurized water reactor]] (PWR) and [[supercritical steam generator]] are all proven technologies. The SCWR is a promising advanced nuclear system because of its high [[thermal efficiency]] (~45% vs. ~33% for current LWRs) and simpler design, and is being investigated.<ref>{{citation |last=Buongiorno |first=Jacopo |title=The Supercritical Water Cooled Reactor: Ongoing Research and Development in the U.S |url=http://www.osti.gov/energycitations/product.biblio.jsp?osti_id=21160713 |work=2004 international congress on advances in nuclear power plants |publisher=American Nuclear Society - ANS, La Grange Park (United States) |osti=21160713 |accessdate=10 Nov 2012}}</ref> by 32 organizations in 13 countries.<eod>
<sod>The '''supercritical water reactor''' ('''SCWR''') is a [[Generation IV reactor]] concept that uses [[Supercritical fluid|supercritical water]] (referring to the [[Critical point (thermodynamics)|critical point]] of water, not the [[Critical mass (nuclear)|critical mass]] of the nuclear fuel) as the [[working fluid]].<ref>https://www.gen-4.org/gif/jcms/c_40679/technology-system-scwr |accessdate=7 Apr 2016</ref> SCWRs resemble [[light water reactors]] (LWRs) but operate above the thermodynamic critical point of water (374C, 22.1MPa), with a direct once-through cycle like a supercritical boiler. It is different from a [[boiling water reactor]] (BWR) operating at subcritical-pressure with steam-water separation and recirculation of the coolant. The water is always in a single, fluid state at supercritical pressure. The BWR, [[pressurized water reactor]] (PWR) and [[supercritical steam generator]] are all proven technologies. The SCWR is a promising advanced nuclear system because of its high [[thermal efficiency]] (~45% vs. ~33% for current LWRs) and simpler design, and is being investigated.<ref>{{citation |last=Buongiorno |first=Jacopo |title=The Supercritical Water Cooled Reactor: Ongoing Research and Development in the U.S |url=http://www.osti.gov/energycitations/product.biblio.jsp?osti_id=21160713 |work=2004 international congress on advances in nuclear power plants |publisher=American Nuclear Society - ANS, La Grange Park (United States) |osti=21160713 |accessdate=10 Nov 2012}}</ref> by 32 organizations in 13 countries.<eod>