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  2. 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]

  3. 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.

  4. 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.

  5. Davis–Besse Nuclear Power Station - Wikipedia

    en.wikipedia.org/wiki/Davis–Besse_Nuclear_Power...

    The reactor head under inspection. Unit One is an 879 MWe pressurized water reactor supplied by Babcock & Wilcox. The reactor was shut down from 2002 until early 2004 for safety repairs and upgrades. In 2012 the reactor supplied 7101.700 GWh of electricity. [14] In 1973, two more reactors were also ordered from Babcock & Wilcox.

  6. Nuclear reactor safety system - Wikipedia

    en.wikipedia.org/wiki/Nuclear_reactor_safety_system

    A reactor protection system is designed to immediately terminate the nuclear reaction. By breaking the nuclear chain reaction, the source of heat is eliminated.Other systems can then be used to remove decay heat from the core.

  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. Nuclear fuel cycle - Wikipedia

    en.wikipedia.org/wiki/Nuclear_fuel_cycle

    A number of reactor designs, like the Integral Fast Reactor, have been designed for this rather different fuel cycle. In principle, it should be possible to derive energy from the fission of any actinide nucleus. With a careful reactor design, all the actinides in the fuel can be consumed, leaving only lighter elements with short half-lives ...

  9. 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 ...