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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).

  3. Pressurizer (nuclear power) - Wikipedia

    en.wikipedia.org/wiki/Pressurizer_(nuclear_power)

    Water pressure in a closed system tracks water temperature directly; as the temperature goes up, pressure goes up and vice versa. To increase the pressure in the reactor coolant system, large electric heaters in the pressurizer are turned on, raising the coolant temperature in the pressurizer and thereby raising the pressure. To decrease ...

  4. VVER - Wikipedia

    en.wikipedia.org/wiki/VVER

    The water-water energetic reactor (WWER), [1] or VVER (from Russian: водо-водяной энергетический реактор; transliterates as vodo-vodyanoi enyergeticheskiy reaktor; water-water power reactor) is a series of pressurized water reactor designs originally developed in the Soviet Union, and now Russia, by OKB Gidropress. [2]

  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. Control rod - Wikipedia

    en.wikipedia.org/wiki/Control_rod

    Control rod assembly for a pressurized water reactor, above fuel element Control rods are used in nuclear reactors to control the rate of fission of the nuclear fuel – uranium or plutonium . Their compositions include chemical elements such as boron , cadmium , silver , hafnium , or indium , that are capable of absorbing many neutrons without ...

  7. AP1000 - Wikipedia

    en.wikipedia.org/wiki/AP1000

    The AP1000 design traces its history to two previous designs, the AP600 and the System 80.. The System 80 design was created by Combustion Engineering and featured a two-loop cooling system with a single steam generator paired with two reactor coolant pumps in each loop that makes it simpler and less expensive than systems which pair a single reactor coolant pump with a steam generator in each ...

  8. Steam generator (nuclear power) - Wikipedia

    en.wikipedia.org/wiki/Steam_generator_(nuclear...

    It is used in pressurized water reactors (PWRs), between the primary and secondary coolant loops. It is also used in liquid metal cooled reactors (LMRs), pressurized heavy-water reactors (PHWRs), and gas-cooled reactors (GCRs). In typical PWR designs, the primary coolant is high-purity water, kept under high pressure so it cannot boil.

  9. Pressurized heavy-water reactor - Wikipedia

    en.wikipedia.org/.../Pressurized_heavy-water_reactor

    A pressurized heavy-water reactor (PHWR) is a nuclear reactor that uses heavy water (deuterium oxide D 2 O) as its coolant and neutron moderator. [1] PHWRs frequently use natural uranium as fuel, but sometimes also use very low enriched uranium .