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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). In a PWR, water is used both as a neutron moderator and as coolant fluid for the reactor core.
The Mitsubishi advanced pressurized water reactor (APWR) is a generation III nuclear reactor design developed by Mitsubishi Heavy Industries (MHI) based on pressurized water reactor technology. It features several design enhancements including a neutron reflector, improved efficiency and improved safety systems. It has safety features advanced ...
The CPR-1000, or CPR1000 (Chinese PWR) is a Generation II+ pressurized water reactor, based on the French 900 MWe three cooling loop design (M310) imported in the 1980s, improved to have a slightly increased net power output of 1,000 MWe (1080 MWe gross) and a 60-year design life.
The RITM-200 is an integrated Generation III+ pressurized water reactor developed by OKBM Afrikantov and designed to produce 55 MWe. [ 13 ] [ 14 ] The design is an improvement of KLT-40S reactor. It uses up to 20% enriched uranium-235 and can be refueled every 10 years for a 60 year planned lifespan in floating power plant installation. [ 15 ]
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 ...
The pressurized water reactor nuclear steam supply system (NSSS) for WNP-1 and -4 was being manufactured by Babcock & Wilcox. The B&W 205 design was ordered for WNP-1 and -4 as well as for the two units at Bellefonte Nuclear Generating Station and Mülheim-Kärlich Nuclear Plant , but only Mülheim-Kärlich was completed.
The two Westinghouse four-loop pressurized-water reactors each have an electrical output of over 1,000 MWe. Byron has 2 units capable of generating 2347 [14] net megawatts (MW) of electricity. In 2009 the reactors operated at 96.4% capacity and produced 19.7 million MWh of electricity; enough power for 2 million average American households. [15]
A steam generator (aka nuclear steam raising plant ('NSRP')) is a heat exchanger used to convert water into steam from heat produced in a nuclear reactor core. 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 ...