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  2. Control rod - Wikipedia

    en.wikipedia.org/wiki/Control_rod

    1943 Reactor diagram using boron control rods. Control rods are inserted into the core of a nuclear reactor and adjusted in order to control the rate of the nuclear chain reaction and, thereby, the thermal power output of the reactor, the rate of steam production, and the electrical power output of the power station.

  3. Reactor pressure vessel - Wikipedia

    en.wikipedia.org/wiki/Reactor_pressure_vessel

    A reactor vessel head for a pressurized water reactor. This structure is attached to the top of the reactor vessel body. It contains penetrations to allow the control rod driving mechanism to attach to the control rods in the fuel assembly. The coolant level measurement probe also enters the vessel through the reactor vessel head.

  4. File:PWR nuclear power plant diagram.svg - Wikipedia

    en.wikipedia.org/wiki/File:PWR_nuclear_power...

    English: Nuclear reactor: pressurized water type. Water is heated through the splitting of uranium atoms in the reactor core. The water, held under high pressure to keep it from boiling, produces steam by transferring heat to a secondary source of water. The steam is used to generate electricity.

  5. File:RBMK reactor schematic.svg - Wikipedia

    en.wikipedia.org/wiki/File:RBMK_reactor...

    You are free: to share – to copy, distribute and transmit the work; to remix – to adapt the work; Under the following conditions: attribution – You must give appropriate credit, provide a link to the license, and indicate if changes were made.

  6. Nuclear reactor safety system - Wikipedia

    en.wikipedia.org/wiki/Nuclear_reactor_safety_system

    This system is often driven by a steam turbine to provide enough water to safely cool the reactor if the reactor building is isolated from the control and turbine buildings. Steam turbine driven cooling pumps with pneumatic controls can run at mechanically controlled adjustable speeds, without battery power, emergency generator, or off-site ...

  7. Containment building - Wikipedia

    en.wikipedia.org/wiki/Containment_building

    A BWR's containment consists of a drywell, where the reactor and associated cooling equipment is located, and a wetwell. The drywell is much smaller than a PWR containment and plays a larger role. During the theoretical leakage design basis accident, the reactor coolant flashes to steam in the drywell, pressurizing it rapidly.

  8. Wikipedia : Featured picture candidates/Diagram of the ...

    en.wikipedia.org/wiki/Wikipedia:Featured_picture...

    nuclear power, pressurized water reactor FP category for this image Wikipedia:Featured pictures/Diagrams, drawings, and maps/Diagrams Creator Tennessee Valley Authority (PD-USGov) Support as nominator – TomStar81 00:16, 22 May 2016 (UTC) Support A good educational video. Slightly weird at the end with the pipes coming from who-knows-where to ...

  9. OPR-1000 - Wikipedia

    en.wikipedia.org/wiki/OPR-1000

    The OPR-1000 is a South Korean-designed two-loop 1000 MWe PWR Generation II nuclear reactor, developed by KHNP and KEPCO. [1] The OPR-1000 was originally designated as the Korean Standard Nuclear Power Plant (KSNP), and was re-designated as the OPR-1000 in 2005 for foreign sales. [2]