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Supercritical water reactor
The supercritical water reactor (SCWR) is a concept Generation IV reactor, designed as a light water reactor (LWR) that operates at supercritical pressure (i.e. greater than 22.1 megapascals [3,210 psi]). The term critical in this context refers to the critical point of water, and should not be confused with the concept of criticality of the nuclear reactor.
The water heated in the reactor core becomes a supercritical fluid above the critical temperature of 374 °C (705 °F), transitioning from a fluid more resembling liquid water to a fluid more resembling saturated steam (which can be used in a steam turbine), without going through the distinct phase transition of boiling.
The supercritical water reactor combines the established technologies of the supercritical steam generator (typically used to generate electricity from fossil fuels) with the boiling water reactor (BWR), to achieve a design that is simpler and more efficient than a BWR, by operating at a higher pressure. As with a BWR, the turbine and reactor pressure vessel are in the same coolant loop, in contrast to a pressurized water reactor (PWR).
Most SCWR plants are developed for power generation higher than 1000 MWe at operating pressures of about 25 MPa and reactor outlet temperatures ranging from 500 to 625 °C.
The development of SCWR systems is considered a promising advancement for nuclear power plants because of its high thermal efficiency (~45 % vs. ~33 % for current LWRs) and simpler design. As of 2012 the concept was being investigated by 32 organizations in 13 countries.
The super-heated steam cooled reactors operating at subcritical-pressure were experimented with in both Soviet Union and in the United States as early as the 1950s and 1960s such as Beloyarsk Nuclear Power Station, Pathfinder and Bonus of GE's Operation Sunrise program. These are not SCWRs. SCWRs were developed from the 1990s onwards. Both a LWR-type SCWR with a reactor pressure vessel and a CANDU-type SCWR with pressure tubes are being developed.[citation needed]
A 2010 book includes conceptual design and analysis methods such as core design, plant system, plant dynamics and control, plant startup and stability, safety, fast reactor design etc.
A 2013 document saw the completion of a prototypical fueled loop test in 2015. A Fuel Qualification Test was completed in 2014.
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Supercritical water reactor AI simulator
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Supercritical water reactor
The supercritical water reactor (SCWR) is a concept Generation IV reactor, designed as a light water reactor (LWR) that operates at supercritical pressure (i.e. greater than 22.1 megapascals [3,210 psi]). The term critical in this context refers to the critical point of water, and should not be confused with the concept of criticality of the nuclear reactor.
The water heated in the reactor core becomes a supercritical fluid above the critical temperature of 374 °C (705 °F), transitioning from a fluid more resembling liquid water to a fluid more resembling saturated steam (which can be used in a steam turbine), without going through the distinct phase transition of boiling.
The supercritical water reactor combines the established technologies of the supercritical steam generator (typically used to generate electricity from fossil fuels) with the boiling water reactor (BWR), to achieve a design that is simpler and more efficient than a BWR, by operating at a higher pressure. As with a BWR, the turbine and reactor pressure vessel are in the same coolant loop, in contrast to a pressurized water reactor (PWR).
Most SCWR plants are developed for power generation higher than 1000 MWe at operating pressures of about 25 MPa and reactor outlet temperatures ranging from 500 to 625 °C.
The development of SCWR systems is considered a promising advancement for nuclear power plants because of its high thermal efficiency (~45 % vs. ~33 % for current LWRs) and simpler design. As of 2012 the concept was being investigated by 32 organizations in 13 countries.
The super-heated steam cooled reactors operating at subcritical-pressure were experimented with in both Soviet Union and in the United States as early as the 1950s and 1960s such as Beloyarsk Nuclear Power Station, Pathfinder and Bonus of GE's Operation Sunrise program. These are not SCWRs. SCWRs were developed from the 1990s onwards. Both a LWR-type SCWR with a reactor pressure vessel and a CANDU-type SCWR with pressure tubes are being developed.[citation needed]
A 2010 book includes conceptual design and analysis methods such as core design, plant system, plant dynamics and control, plant startup and stability, safety, fast reactor design etc.
A 2013 document saw the completion of a prototypical fueled loop test in 2015. A Fuel Qualification Test was completed in 2014.
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