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Nuclear power reactor types

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nuclear reactor
device to initiate and control a sustained nuclear chain reaction
pressurized water reactor
nuclear reactor with a water cooling system that operates under high pressure
RBMK
The RBMK (, РБМК; reaktor bolshoy moshchnosti kanalnyy, "high-power channel-type reactor") is a class of graphite-moderated nuclear power reactor designed and built by the Soviet Union. It is somewhat like a boiling water reactor as water boils in the pressure tubes. It is one of two power reactor types to enter serial production in the Soviet Union during the 1970s, the other being the VVER reactor. The name refers to its design where instead of a large steel pressure vessel surrounding the entire core, the core is surrounded by a cylindrical annular steel tank inside a concrete vault and eac
breeder reactor
nuclear reactor generating more fissile material than it consumes
CANDU reactor
Canadian PHWR nuclear reactor design
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
small modular reactor
nuclear reactor with a modular design and an electricity output of less than 300 MWe
light-water reactor
type of nuclear reactor using normal water as coolant and neutron moderator
Magnox
thumb|350px|Schematic diagram of a magnox nuclear reactor showing gas flow. The heat exchanger is outside the concrete radiation shielding. This represents an early Magnox design with a cylindrical, steel, pressure vessel.
advanced gas-cooled reactor
type of nuclear reactor
Supercritical water reactor
type of nuclear reactor (hypothetical)
Generation IV reactor
classification of nuclear reactors
high-temperature gas-cooled reactor
class of nuclear reactor
Generation III reactor
class of nuclear reactors with improved safety over its predecessors
pressurized heavy water reactor
type of nuclear reactor
heavy water reactor
type of nuclear reactor
pebble bed reactor
graphite-moderated, gas-cooled nuclear reactor
advanced boiling water reactor
type of generation III nuclear reactor
AP1000
thumb|upright=1.3|Computer generated image of AP1000
TerraPower
TerraPower, LLC is an American nuclear reactor design and development engineering company headquartered in Bellevue, Washington.
Generation II reactor
design classification for nuclear reactors
reactor vessel
pressure vessel containing the nuclear reactor coolant, core shroud, and the reactor core
APR-1400
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gas-cooled reactor
type of nuclear reactor
traveling wave reactor
type of nuclear fission reactor
graphite moderated reactor
type of nuclear reactor
KRUSTY
Kilopower is an experimental U.S. project to make new nuclear reactors for space travel. The project started in October 2015, led by NASA and the DoE’s National Nuclear Security Administration (NNSA). As of 2017, the Kilopower reactors were intended to come in four sizes, able to produce from one to ten kilowatts of electrical power (1–10&nbsp;kWe) continuously for twelve to fifteen years. The fission reactor uses uranium-235 to generate heat that is carried to the Stirling converters with passive sodium heat pipes. In 2018, positive test results for the Kilopower Reactor Using Stirling Techno
liquid fluoride thorium reactor
type of nuclear reactor that uses molten material as fuel
SNAP-10A
SNAP-10A (Systems for Nuclear Auxiliary Power, aka Snapshot for Space Nuclear Auxiliary Power Shot, also known as OPS 4682) was a US experimental nuclear powered satellite launched into space in 1965 as part of the SNAPSHOT program. The test marked both the world's first operation of a nuclear reactor in orbit, and the first operation of an ion thruster system in orbit. It is the only fission reactor power system launched into space by the United States. The reactor stopped working after just 43 days due to a non-nuclear electrical component failure. The Systems Nuclear Auxiliary Power Program
UNGG reactor
type of nuclear reactor
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.
Hualong One
Chinese nuclear reactor design
Economic Simplified Boiling Water Reactor
nuclear reactor design
gas-cooled fast reactor
type of nuclear reactor cooled by a gas
EGP-6
The EGP-6 is a Russian small nuclear reactor design. It is a scaled down version of the RBMK design. As the RBMK, the EGP-6 uses water for cooling and graphite as a neutron moderator, but uses natural circulation instead of pumping. EGP is a Russian acronym but translated into English it stands for Power Heterogenous Loop reactor. It is the world's smallest running commercial nuclear reactor, however smaller reactors are currently in development. The EGP-6 reactors are the only reactors to be built on permafrost.
accelerator-driven sub-critical reactor
type of nuclear reactor design
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
Steam-generating heavy water reactor
Nuclear power system
Toshiba 4S
nuclear reactor design
Advanced CANDU reactor
Canadian third generation nuclear reactor design
BWRX-300
The BWRX-300 is a design for a small modular nuclear reactor proposed by GE Vernova Hitachi Nuclear Energy (GVH). The BWRX-300 would feature passive safety, in that neither external power nor operator action would be required to maintain a safe state, even in extreme circumstances.
MKER
Advanced Heavy Water Reactor
Indian design for a next-generation nuclear reactor fueleld by thorium
aqueous homogeneous reactor
type of nuclear reactor
Integral Fast Reactor
nuclear reactor design
BREST
Lead-cooled reactor family designed in Russia
System 80
American nuclear reactor design
Gas turbine modular helium reactor
Alighaiment
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.
dual fluid reactor
nuclear reactor concept
nuclear reactor physics
physics branch
N4
French nuclear reactor type
Mitsubishi APWR
Japanese nuclear reactor design
IMSR
nuclear power plant design
Small, sealed, transportable, autonomous reactor
proposed nuclear reactor currently undergoing development in the U.S