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A gas-cooled reactor (GCR) is a nuclear reactor that uses graphite as a neutron moderator and a gas (carbon dioxide or helium in extant designs) as coolant. [1] Although there are many other types of reactor cooled by gas, the terms GCR and to a lesser extent gas cooled reactor are particularly used to refer to this type of reactor.
This is a list of electricity-generating power stations in the U.S. state of Ohio, sorted by type and name.In 2022, Ohio had a total summer capacity of 27,447 MW and a net generation of 135,810 GWh. [2]
The William H. Zimmer Power Station, located near Moscow, Ohio, was a 1.35-gigawatt (1,351 MW) coal power plant.Planned by Cincinnati Gas and Electric (CG&E) (a forerunner of Duke Energy), with Columbus & Southern Ohio Electric (a forerunner of American Electric Power (AEP)) and Dayton Power & Light (DP&L) as its partners, it was originally intended to be a nuclear power plant. [1]
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Portsmouth Gaseous Diffusion Plant is a facility located in Scioto Township, Pike County, Ohio, just south of Piketon, Ohio, that previously produced enriched uranium, including highly enriched weapons-grade uranium, for the United States Atomic Energy Commission (AEC), the U.S. nuclear weapons program and Navy nuclear propulsion; in later years, it produced low-enriched uranium for fuel for ...
Chinese Experimental Fast Reactor (65 MW, 20 MWe, sodium cooled fast-spectrum neutron reactor). Located at CIAE Beijing, construction started May 2000, first criticality July 2010. MNSR-SZ Shenzhen: Mnsr Operational 30 1988-11-01 SPR IAE Beijing: Pool Operational 3,500 1964-12-20 CMRR (China Mianyang Research Reactor) Mianyang: Pool Operational ...
The reactor is a General Electric BWR-6 boiling water reactor design, with a Mark III containment design. The original core power level of 3,579 megawatts thermal was increased to 3,758 megawatts thermal in 2000, making Perry one of the largest BWRs in the United States.
A high-temperature gas-cooled reactor (HTGR) is a type of gas-cooled nuclear reactor which uses uranium fuel and graphite moderation to produce very high reactor core output temperatures. [1] All existing HTGR reactors use helium coolant. The reactor core can be either a "prismatic block" (reminiscent of a conventional reactor core) or a ...