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  2. Pressurized water reactor - Wikipedia

    en.wikipedia.org/wiki/Pressurized_water_reactor

    A pressurized water reactor (PWR) is a type of light-water nuclear reactor. PWRs constitute the large majority of the world's nuclear power plants (with notable exceptions being the UK, Japan, India and Canada). In a PWR, water is used both as a neutron moderator and as coolant fluid for the reactor core.

  3. Advanced Test Reactor - Wikipedia

    en.wikipedia.org/wiki/Advanced_Test_Reactor

    Six of the test locations allow an experiment to be isolated from the primary cooling system, providing its own environment for temperature, pressure, flow and chemistry, replicating the physical environment while accelerating the nuclear conditions. The ATR is a pressurized light water reactor (LWR), using water as both coolant and moderator.

  4. Molten-salt reactor - Wikipedia

    en.wikipedia.org/wiki/Molten-salt_reactor

    MSRs can be refueled while operating (essentially online-nuclear reprocessing) while conventional reactors shut down for refueling (notable exceptions include pressure tube reactors like the heavy water CANDU or the Atucha-class PHWRs, light water cooled graphite moderated RBMK, and British-built gas-cooled reactors such as Magnox, AGR). MSR ...

  5. EPR (nuclear reactor) - Wikipedia

    en.wikipedia.org/wiki/EPR_(nuclear_reactor)

    Computer generated view of an EPR power station Reactor pressure vessel of the EPR. The EPR is a Generation III+ pressurised water reactor design. It has been designed and developed mainly by Framatome (part of Areva between 2001 and 2017) and Électricité de France (EDF) in France, and by Siemens in Germany. [1]

  6. Sodium Reactor Experiment - Wikipedia

    en.wikipedia.org/wiki/Sodium_Reactor_Experiment

    The Sodium Reactor Experiment design utilized sodium as a coolant so high-pressure water systems would not be required. [15] The reactor did not have a containment pressure vessel, because the maximum credible accident would not release enough gas volume to require pressure containment.

  7. Light-water reactor - Wikipedia

    en.wikipedia.org/wiki/Light-water_reactor

    The purpose of this experiment was to determine the feasibility of a nuclear reactor using light water as a moderator and coolant, and clad solid uranium as fuel. The results showed that, with a lightly enriched uranium, criticality could be reached. [4] This experiment was the first practical step toward the light-water reactor.

  8. IPHWR-700 - Wikipedia

    en.wikipedia.org/wiki/IPHWR-700

    The IPHWR-700 (Indian Pressurized Heavy Water Reactor-700) ... Heavy Water Reactor operating pressure, kg/cm 2 (g) 87 100 100 Active core height, cm 508.5 594

  9. Supercritical water reactor - Wikipedia

    en.wikipedia.org/wiki/Supercritical_water_reactor

    The SCWR operates at supercritical pressure. The reactor outlet coolant is supercritical water.Light water is used as a neutron moderator and coolant. Above the critical point, steam and liquid become the same density and are indistinguishable, eliminating the need for pressurizers and steam generators (), or jet/recirculation pumps, steam separators and dryers ().