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The following outline is provided as an overview of and topical guide to nuclear power: Nuclear power – the use of sustained nuclear fission to generate heat and electricity. Nuclear power plants provide about 6% of the world's energy and 13–14% of the world's electricity, [1] with the U.S., France, and Japan together accounting for about ...
Older nuclear power plants, like ones using second-generation reactors, produce approximately the same amount of carbon dioxide during the whole life cycle of nuclear power plants for an average of about 11g/kWh, as much power generated by wind, which is about 1/3 of solar and 1/45 of natural gas and 1/75 of coal. [64]
A fission nuclear power plant is generally composed of: a nuclear reactor, in which the nuclear reactions generating heat take place; a cooling system, which removes the heat from inside the reactor; a steam turbine, which transforms the heat into mechanical energy; an electric generator, which transforms the mechanical energy into electrical ...
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 .
A fission fragment reactor is a nuclear reactor that generates electricity by decelerating an ion beam of fission byproducts instead of using nuclear reactions to generate heat. By doing so, it bypasses the Carnot cycle and can achieve efficiencies of up to 90% instead of 40–45% attainable by efficient turbine-driven thermal reactors.
The APR-1400 (for Advanced Power Reactor 1400 MW electricity) is an advanced pressurized water nuclear reactor designed by the Korea Electric Power Corporation (KEPCO). Originally known as the Korean Next Generation Reactor (KNGR), [ 1 ] this Generation III reactor was developed from the earlier OPR-1000 design and also incorporates features ...
The IPHWR (Indian Pressurized Heavy Water Reactor) is a class of Indian pressurized heavy-water reactors designed by the Bhabha Atomic Research Centre. [1] The baseline 220 MWe design was developed from the CANDU based RAPS-1 and RAPS-2 reactors built at Rawatbhata , Rajasthan.
The NGNP, as a nuclear power facility design, is closely coupled with the United States Department of Energy (DOE) Next Generation Nuclear Plant Project (NGNP Project). The NGNP Project included participation by the DOE, Idaho National Laboratory , and the commercial utilities and reactor designers consortium NGNP Industry Alliance. [ 3 ]