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Pressurized water reactors

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pressurized water reactor
nuclear reactor with a water cooling system that operates under high pressure
water-water energetic reactor
The water-water energetic reactor (WWER), or VVER (from ) is a series of pressurized water reactor designs originally developed in the Soviet Union, and now Russia, by OKB Gidropress. The idea of such a reactor was proposed at the Kurchatov Institute by Savely Moiseevich Feinberg. VVER were originally developed before the 1970s, and have been continually updated. They were one of the initial reactors developed by the USSR, the other being the infamous RBMK. As a result, the name VVER is associated with a wide variety of reactor designs spanning from generation I reactors to modern generation I
control rod
nuclear reactor component
European Pressurized Reactor
third generation nuclear reactor
APR-1400
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A4W reactor
naval reactor used by the United States Navy
CPR-1000
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.
OK-650 reactor
nuclear fission reactor
RITM-200
The RITM-200 is an integrated Generation III+ pressurized water reactor developed by OKBM Afrikantov and designed to produce 55 MWe. 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. If installed in a stationary power plant, the fuel cycle is 6 years.
OPR-1000
__NOTOC__ The OPR-1000 is a South Korean-designed two-loop 1000 MWe PWR Generation II nuclear reactor, developed by KHNP and KEPCO. 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. It was developed based on the Combustion Engineering (C-E)'s system 80 design, through a technology transfer agreement. The reactor core design was derived from the C-E designed Arkansas Nuclear One Unit 2, the nuclear steam supply system (NSSS) was derived from the C-E designed units at Palo Verde Nuclear Gener
A2W reactor
naval nuclear reactor used by the United States Navy
pressurizer
device to prevent coolant in nuclear reactor from boiling
OK-150 reactor
Soviet marine nuclear reactor
VM reactor
Russian nuclear pressurized water reactors
A1W reactor
American naval nuclear reactor
S3W reactor
type of naval reactor used by the United States Navy
CNP-300
The CNP-300 is a pressurized water nuclear reactor developed by the China National Nuclear Corporation (CNNC).
Atmea
Atmea was a joint venture between Mitsubishi Heavy Industries (MHI) and EDF Group set up in 2006 to develop, market, license and sell the ATMEA1 reactor, a new generation III+, medium-power pressurized water reactor (PWR). The company was headquartered in Paris. The joint venture was abandoned in 2019.