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Showing 1 to 8 of 8 for “"Supercritical water-cooled reactors"”.

  1. Stability analysis of supercritical water cooled reactors

    The Supercritical Water-Cooled Reactor (SCWR) is a concept for an advanced reactor that will operate at high pressure (25MPa) and high temperature (500°C average core exit). The high coolant temperature as it leaves the reactor core gives the SCWR the potential for high thermal efficiency (45%). …

    mit Repository record for Stability analysis of supercritical water cooled reactors (opens in a new tab)

  2. Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs)

    … next generation (i.e., Generation IV) of nuclear reactors. Chosen as one of the six Generation‒IV nuclear-reactor concepts, the SCWRs are expected to have high thermal efficiencies within the range of 40 ‒ 50% owing to reactor’s high outlet temperatures. The Canadian pressure-tube-type SCWR is …

    uoit Repository record for Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs) (opens in a new tab)

  3. Heat transfer to supercritical water flowing in short vertical bare tube and rod-bundle geometries

    Water-cooled nuclear reactors have lower thermal efficiencies (26–38%) compared to thermal Power Pants (PPs) (up to 62%). To improve efficiency, SuperCritical Water-cooled Reactors (SCWRs) and SuperCritical-Pressure-Small Modular Reactors (SCP-SMRs) operate at supercritical pressures, requiring …

    uoit Repository record for Heat transfer to supercritical water flowing in short vertical bare tube and rod-bundle geometries (opens in a new tab)

  4. Heat-transfer analysis of double-pipe heat exchangers for indirect-cycle SCW NPP

    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 compared to current NPPs, i.e., pressure of about 25 MPa and outlet …

    uoit Repository record for Heat-transfer analysis of double-pipe heat exchangers for indirect-cycle SCW NPP (opens in a new tab)

  5. Assessment of FLUENT CFD code as an analysis tool for SCW applications

    … of six Generation‒IV nuclear-reactor concepts, SuperCritical Water-cooled Reactors (SCWRs) are expected to have high thermal efficiencies within the range of 45 ‒ 50% owing to the reactor‟s high pressures and outlet temperatures. The behaviour of supercritical water however, is not well …

    uoit Repository record for Assessment of FLUENT CFD code as an analysis tool for SCW applications (opens in a new tab)

  6. Thermal aspects of high efficiency channel with conventional and alternative fuels in SuperCritical water-cooled reactor (SCWR) applications

    … of six Generation‒IV nuclear-reactor concepts, SuperCritical Water-cooled Reactors (SCWRs) are expected to have high thermal efficiencies within the range of 45 ‒ 50% owing to reactor‘s high outlet temperatures. A generic pressure-channel (or pressure-tube)SCWR operates at a pressure of 25 MPa …

    uoit Repository record for Thermal aspects of high efficiency channel with conventional and alternative fuels in SuperCritical water-cooled reactor (SCWR) applications (opens in a new tab)

  7. Development of a heat-transfer correlation for supercritical water in supercritical water-cooled reactor applications

    … analyzed and a new heat-transfer correlation for supercritical water was developed. This experimental dataset was obtained within conditions similar to those for proposed SuperCritical Water-cooled nuclear Reactor (SCWR) concepts. Thus, this new correlation, for forced convective heat transfer in …

    uoit Repository record for Development of a heat-transfer correlation for supercritical water in supercritical water-cooled reactor applications (opens in a new tab)

  8. Study on heat transfer to supercritical water in application to SMRs

    … a small modular reactor (SMR) concept with a supercritical water coolant, was subjected to a thermalhydraulic analysis and an economic analysis of its Levelized Unit of Energy Cost (LUEC). Heat transfer data was examined for the onset of deteriorated heat transfer using three correlations that …

    uoit Repository record for Study on heat transfer to supercritical water in application to SMRs (opens in a new tab)