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Type of nuclear reactor cooled by a gas
The gas-cooled fast reactor (GFR) system is a nuclear reactor design in development. Classed as a Generation IV reactor, it features a fast-neutron spectrum
Gas-cooled_fast_reactor
Type of nuclear reactor that operates at high temperatures as part of normal operation
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
High-temperature gas-cooled reactor
High-temperature_gas-cooled_reactor
Type of nuclear reactor, CO2 or He cooled
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. The GCR
Gas-cooled_reactor
Fast-neutron nuclear reactor cooled by molten lead
The lead-cooled fast reactor is a nuclear reactor design that uses molten lead or lead-bismuth eutectic as its coolant. These materials can be used as
Lead-cooled_fast_reactor
Type of nuclear reactor cooled by molten sodium
A sodium-cooled fast reactor (SFR) is a fast neutron reactor cooled by liquid sodium. It offers several advantages over light-water reactors (LWRs), including
Sodium-cooled_fast_reactor
Nuclear reactor where fast neutrons maintain a fission chain reaction
plutonium. As of 2025[update], every fast reactor has used a liquid metal coolant, typically sodium-cooled or lead-cooled. This allows high thermal efficiency
Fast-neutron_reactor
New nuclear reactor technologies under development
were: the gas-cooled fast reactor (GFR), the lead-cooled fast reactor (LFR), the molten salt reactor (MSR), the sodium-cooled fast reactor (SFR), the
Generation_IV_reactor
Nuclear reactor design
The IFR was a sodium-cooled fast reactor (SFR) is its closest surviving fast breeder reactor, a type of Generation IV reactor. The U.S. Department of
Integral_fast_reactor
Type of British nuclear reactor
advanced gas-cooled reactor (AGR) is a type of nuclear reactor designed and operated by the United Kingdom. These are the second generation of British gas-cooled
Advanced_gas-cooled_reactor
Nuclear reactor generating more fissile material than it consumes
proposed generation IV reactor types use a fast-neutron spectrum: Gas-cooled fast reactor cooled by helium. Sodium-cooled fast reactor based on the existing
Breeder_reactor
Device for controlled nuclear reactions
such plants. Gas-cooled fast reactor Lead-cooled fast reactor Molten-salt reactor Sodium-cooled fast reactor Supercritical water reactor Very-high-temperature
Nuclear_reactor
Nuclear reactor where the coolant is liquid metal
liquid metal cooled nuclear reactor (LMR) is a type of nuclear reactor where the primary coolant is a liquid metal. Liquid metal cooled reactors were first
Liquid_metal_cooled_reactor
US/Russian design concept ~1997 - never built
a gas-cooled fast reactor, enabling it to reduce nuclear waste considerably by transmutation. Gas-cooled fast reactor Pebble bed reactor Very high temperature
Gas turbine modular helium reactor
Gas_turbine_modular_helium_reactor
Lead-cooled reactor family designed in Russia
Teplonositelem, 'Naturally Safe Lead-Cooled Fast Reactor') is a generation IV lead-cooled fast nuclear reactor. BREST-300 model is under construction
BREST_(reactor)
Type of very-high-temperature reactor
Pebble-bed reactors are typically high temperature gas-cooled reactors (HTGRs), and are capable of being refueled during operation. The helium-cooled PBR design
Pebble-bed_reactor
Russian sodium-cooled fast breeder reactor
The BN-600 reactor is a sodium-cooled fast breeder reactor, built at the Beloyarsk Nuclear Power Station, in Zarechny, Sverdlovsk Oblast, Russia. It has
BN-600_reactor
Russian fast breeder nuclear reactor, operating since 2016
The BN-800 reactor (Russian: реактор БН–800) is a sodium-cooled fast breeder reactor, built at the Beloyarsk Nuclear Power Station, in Zarechny, Sverdlovsk
BN-800_reactor
Type of nuclear reactor cooled by molten salt
tube reactors like the heavy water CANDU or the Atucha-class PHWRs, light water cooled graphite moderated RBMK, and British-built gas-cooled reactors such
Molten-salt_reactor
Type of nuclear fission reactor
various reactor types, including generation IV, thermal-neutron reactors, fast-neutron reactors, molten salt reactor, and gas-cooled reactor models. Many
Small_modular_reactor
Device that achieves nuclear fission without triggering a chain reaction
MYRRHA (Belgium) GEM STAR Reactor, ADNA Corporation Multiple authors. "A Subcritical, Gas-Cooled Fast Transmutation Reactor with a Fusion Neutron Source"
Subcritical_reactor
Concept nuclear reactor whose water operates at supercritical pressure
liquid metal cooled reactors). A fast SCWR could be a breeder reactor, like the proposed Clean and Environmentally Safe Advanced Reactor and could burn
Supercritical_water_reactor
Type of Soviet nuclear power reactor
graphite-moderated reactors. A graphite-moderated Magnox reactor exists in North Korea at the Yongbyon Nuclear Scientific Research Center. While the gas cooled Magnox
RBMK
Type of nuclear reactor that uses molten material as fuel
efficiency. These gas cycles offer numerous potential advantages for use with molten salt-fueled or molten salt-cooled reactors. These closed gas cycles face
Liquid fluoride thorium reactor
Liquid_fluoride_thorium_reactor
Breeder reactor in Tamil Nadu, India
/ 12.5623504; 80.1645415 The Fast Breeder Test Reactor (FBTR) is a 40 MWt loop type, sodium cooled fast breeder reactor located at Kalpakkam, Tamil Nadu
Fast_Breeder_Test_Reactor
Nuclear reactor cooled or moderated by an organic liquid
An Organic nuclear reactor or Organic-cooled reactor (OCR) is a class of nuclear reactor in which the primary coolant or neutron moderator is an organic
Organic_nuclear_reactor
Design project of a nuclear reactor coupled to a proton accelerator
an accelerator-driven system (ADS). MYRRHA will be a lead-bismuth cooled fast reactor with two possible configurations: sub-critical or critical. The project
MYRRHA
Reactor accident due to core overheating
so that the emergency core cooling system may be turned on). In a depressurization fault, a gas-cooled reactor loses gas pressure within the core, reducing
Nuclear_meltdown
Material in core during nuclear meltdown
transfer. The molten reactor core releases volatile elements and compounds. These may be gas phase, such as molecular iodine or noble gases, or condensed aerosol
Corium_(nuclear_reactor)
Type of nuclear reactor
reactors have been used in commercial electricity generation: Gas-cooled reactors Magnox UNGG reactor Advanced gas-cooled reactor (AGR) Water-cooled reactors
Graphite-moderated_reactor
Part of a reactor containing the fuel
Soviet-made RBMK nuclear-power reactor. This was the type of reactor involved in the Chernobyl disaster. In the Advanced Gas-cooled Reactor, a British design, the
Nuclear_reactor_core
Type of nuclear reactor
on gas cooled reactors, D Bastien, IAEA-TECDOC—899, pp:51-53, 30 Oct - 2 Nov 1995 Twenty-nine years of French experience in operating gas-cooled reactors
UNGG_reactor
sodium cooled, fast-flux, pool-type reactor with metallic fuel based on the 30-year successful operation of the Experimental Breeder Reactor II in Idaho
List of small modular reactor designs
List_of_small_modular_reactor_designs
Nuclear reactor that uses moderated neutrons
A gas-cooled reactor (GCR) is a that uses as a and a gas ( or in extant designs) as . Although there are many other types of reactor cooled by gas, the
Thermal-neutron_reactor
Material fuelling nuclear reactors
interest as a fuel candidate for gas-cooled fast reactors. Development of carbide fuels initially focused on fast reactors, due to their favorable breeding
Nuclear_fuel
Nuclear reactor design
of the Integral Fast Reactor developed by Argonne National Laboratory between 1984 and 1994. It is a sodium-cooled fast breeder reactor, based on the Experimental
PRISM_(reactor)
Proposed nuclear reactor design
current reactors in that it does not use water coolant but is instead a gas-cooled fast reactor, which uses helium as a coolant. The reactor uses a composite
Energy_Multiplier_Module
Topics referred to by the same term
GFR may refer to: Gas-cooled fast reactor Gefreiter General fertility rate Glomerular filtration rate Government Flight Representative Grand Forks Railway
GFR
American defense and energy company
GT-MHR, the Energy Multiplier Module (EM2), which uses fast neutrons and is a Gas-cooled fast reactor. General Atomics, including its affiliate, General Atomics
General_Atomics
Decommissioned experimental nuclear reactor in Idaho, USA
Breeder Reactor-II (EBR-II) was a sodium-cooled fast reactor designed, built and operated by Argonne National Laboratory at the National Reactor Testing
Experimental Breeder Reactor II
Experimental_Breeder_Reactor_II
Topics referred to by the same term
Allegro gravitational-wave detector ALLEGRO, European experimental gas-cooled fast reactor Allegro (software library), a multi-platform software library for
Allegro
Thorium nuclear reactor in Germany
temperature reactor research eventually merged with the AVR consortium. Germany portal Energy portal Nuclear technology portal Gas cooled fast reactor Pebble
THTR-300
Small nuclear fission reactor for naval propulsion cooled by a liquid metal
part of the Soviet Navy's Project 645 Кит-ЖМТ. It is a liquid metal cooled reactor (LMR), using highly enriched uranium-235 fuel to produce 73 MW of power
VT-1_reactor
Nuclear reactor where water boils in core
fluid back into liquid form before it is sent back into the reactor. The condenser is then cooled by a secondary coolant cycle which is fed by the power plant's
Boiling_water_reactor
Naturally occurring uranium self-sustaining nuclear chain reactions
by fast-neutron-induced (n,2n) reactions in nuclear reactors. In Oklo, any possible deviation of 234 U concentration present at the time the reactor was
Natural nuclear fission reactor
Natural_nuclear_fission_reactor
Fast neutron research reactor
reactor BN-800 reactor – generation IV sodium-cooled fast breeder reactor, operational since 2016 BREST-300 – generation IV lead-cooled fast reactor,
MBIR
Nuclear energy extracted from thorium isotopes
several other commercial reactors have been fueled using thorium, including light-water reactors and high-temperature gas-cooled reactors. The feasibility of
Thorium-based_nuclear_power
Type of nuclear reactor
heavy‑water reactors and gas‑cooled reactors respectively) while others, including Japan and India, operate a mix of PWRs and other reactor types (notably
Pressurized_water_reactor
Type of nuclear reactor that uses normal water
water reactor capable of producing 300 MWth/100 MWe of energy called OPEN100. The family of nuclear reactors known as light-water reactors (LWR), cooled and
Light-water_reactor
LWGRs. Reactors used for plutonium production in the nuclear weapons programs of the United Kingdom, France, and North Korea used gas-cooled reactors (GCRs)
Light_water_graphite_reactor
Type of British nuclear reactor
carbon dioxide gas as the coolant. It belongs to the wider class of gas-cooled reactors. The name comes from the magnesium-aluminium alloy (called magnesium
Magnox
Possible future technology
cylinder Tractor beam Cold fusion Fission fragment reactor Fusion torch Gas-cooled fast reactor Gas core reactor High-temperature superconducting stellarator
List of hypothetical technologies
List_of_hypothetical_technologies
Rocket-propelled by exhausted coolant of a gas-cooled nuclear reactor
Gas core reactor rockets are a conceptual type of rocket that is propelled by the exhausted coolant of a gaseous fission reactor. The nuclear fission reactor
Gas_core_reactor_rocket
Russian nuclear fission reactor for use in submarines
NATO designation) fourth generation submarines. It is a liquid metal cooled reactor (LMR), using highly enriched uranium-235 fuel to produce 155 MWt of
BM-40A_reactor
Nuclear power plant component
world. Gas cooled thermal reactor - Includes the Advanced Gas-cooled Reactor, the gas cooled fast breeder reactor, and the high temperature gas cooled reactor
Reactor_pressure_vessel
Deactivated nuclear test reactor in US
The Fast Flux Test Facility (FFTF) is a 400 MW thermal, liquid sodium cooled, nuclear test reactor owned by the U.S. Department of Energy. It does not
Fast_Flux_Test_Facility
Type of nuclear reactor cooled by heat pipes
A heat pipe-cooled reactor (HPR) is a type of nuclear reactor cooled by heat pipes. Using passive heat pipes instead of a pumped nuclear coolant eliminates
Heat_pipe-cooled_reactor
Nuclear power system
carbon dioxide gas as the coolant. The original Magnox was designed to run on natural uranium but the subsequent Advanced Gas-cooled Reactor (AGR) abandoned
Steam-Generating Heavy Water Reactor
Steam-Generating_Heavy_Water_Reactor
Type of nuclear reactor
Aqueous homogeneous reactors (AHR) is a two-chamber reactor consisting of an interior reactor chamber and an outside cooling and moderating jacket chamber
Aqueous_homogeneous_reactor
German nuclear reactor design proposal with liquid metal cooling loops
reactors (MSR) and liquid metal cooled reactors. In contrast to classical molten salt reactor designs, the Dual Fluid Reactor employs a liquid metallic actinide
Dual_fluid_reactor
Nuclear reactor, Oak Ridge 1965–1969
The Molten-Salt Reactor Experiment (MSRE) was an experimental molten-salt reactor research reactor at the Oak Ridge National Laboratory (ORNL) in Oak Ridge
Molten-Salt Reactor Experiment
Molten-Salt_Reactor_Experiment
semiconductor devices GUINEVERE – fast, accelerator driven, lead-cooled reactor at SCK•CEN, Mol Paldiski – 2 PWR naval training reactors (dismantled) Working: Azur
List of nuclear research reactors
List_of_nuclear_research_reactors
1986 nuclear accident in the Soviet Union
reactor that would make room for a cooling system. The final makeshift design for the cooling system incorporated a coiled formation of pipes cooled with
Chernobyl_disaster
Location of two former nuclear research establishments in northern Scotland
October 1962 until the reactor was taken offline for decommissioning in March 1977. DFR was a loop-type fast breeder reactor cooled by primary and secondary
Dounreay
Change in nuclear fission rate caused by voids in a reactor
the reactor is over-moderated). Reactors in which neither the moderator nor the coolant is a liquid (e.g., a graphite-moderated, gas-cooled reactor) will
Void_coefficient
Canadian heavy water nuclear reactor design
CANDU (Canada deuterium uranium) is a Canadian pressurized heavy-water reactor design used to generate electric power. The acronym refers to its deuterium
CANDU_reactor
Nuclear fission reactor
NATO designation) fourth generation submarines. It is a liquid metal cooled reactor (LMR), using highly enriched uranium-235 fuel to produce 155 MWt of
OK-550_reactor
Enclosed volume where interconversion of compounds takes place
in liquid or gas phase, are pumped through the catalyst bed. A chemical reactor may also be a fluidized bed; see Fluidized bed reactor. Chemical reactions
Chemical_reactor
The BN-reactor is a type of sodium-cooled fast breeder reactor built in Russia from the company OKBM Afrikantov. Two BN-reactors are to date (2015) the
BN-Reactor
Nuclear reactor concept
chain reaction with only its own neutron production, so coupling the gas-cooled fast-spectrum core with a moderated outer slow-neutron section is required
Clean and Environmentally Safe Advanced Reactor
Clean_and_Environmentally_Safe_Advanced_Reactor
Substance used to reduce or regulate the temperature of a system
Hydrogen-cooled turbogenerators are currently the most common electrical generators in large power plants. Inert gases are used as coolants in gas-cooled nuclear
Coolant
Coolant in a nuclear reactor
pressure. Current reactors stay under the critical point at around 374 °C and 218 bar where the distinction between liquid and gas disappears, which limits
Nuclear_reactor_coolant
Chinese small modular nuclear reactor
a Chinese small modular nuclear reactor. It is a high-temperature gas-cooled (HTGR) pebble-bed generation IV reactor evolved from the HTR-10 prototype
HTR-PM
Idaho National Laboratory research neutron source
The Advanced Test Reactor (ATR) is a research reactor at the Idaho National Laboratory, located east of Arco, Idaho. This reactor was designed and is
Advanced_Test_Reactor
Nuclear power plant in California, US
July 1959, the reactor experienced a partial meltdown when 13 of the reactor's 43 fuel elements partially melted, and radioactive gas was released into
Sodium_Reactor_Experiment
Feasibility experiment for aircraft nuclear propulsion
that enabled the broader development of molten-salt reactors as well as liquid metal cooled reactors. The concept of nuclear-powered aircraft was first
Aircraft_Reactor_Experiment
Nuclear fission reactor
The OK-650 reactor is the nuclear fission reactor used for powering the Soviet Navy's Project 685 Плавник/Plavnik (Mike), Project 971 Щука-Б/Shchuka-B
OK-650_reactor
programs exploring varied reactor designs such as gas-cooled fast reactors, pebble-bed reactors, high-conversion light-water reactors and finally configurations
Nuclear_power_in_Switzerland
Nuclear reactor in Fujian province, China
The CFR-600 (Xiapu fast reactor pilot project) is a sodium-cooled pool-type fast-neutron nuclear reactor in Xiapu County, Fujian province, China, on Changbiao
CFR-600
Overview of and topical guide to nuclear technology
reactor Fast breeder reactor Fast neutron reactor Gas-cooled fast reactor Generation IV reactor Integral Fast Reactor Lead-cooled fast reactor Liquid-metal-cooled
Outline_of_nuclear_technology
Magnox reactor, a Generation I gas cooled reactor(GCR) design, can rarely produce a fuel burnup of more than 2-5 GWd/tU. Therefore, the "reactor grade
Reactor-grade_plutonium
Type of nuclear propulsion method with an ultra high specific-inpulse
the most advanced gas-core engines, it corresponds to a specific impulse of about 7000 s. The temperature of a conventional reactor design is the average
Fission-fragment_rocket
Nuclear power station located near Kemmerer, WY
power station is the first Natrium reactor to be constructed, and the first commercial sodium-cooled fast reactor in the United States since Fermi 1 was
Kemmerer_Power_Station
Decommissioned nuclear reactor experiment in Idaho
Organic Moderated Reactor Experiment (OMRE) was a 16 MWt experimental organic nuclear reactor that operated at the National Reactor Testing Station from
Organic Moderated Reactor Experiment
Organic_Moderated_Reactor_Experiment
First industrial-scale reactor in the Soviet Union
second nuclear reactor to go critical in the Soviet Union, and the first geographically situated in Asia. It was designed as a light water-cooled, graphite-moderated
A-1_(nuclear_reactor)
Overview of and topical guide to nuclear power
Gas-cooled fast reactor Generation IV reactor Integral Fast Reactor Lead-cooled fast reactor Liquid-metal-cooled reactor Magnox reactor Molten salt reactor Pebble
Outline_of_nuclear_power
Substance that slows down particles with no electric charge
water-cooled supercritical water reactor, the proportion of fast fissions may exceed 50%, making it technically a fast-neutron reactor. A fast reactor uses
Neutron_moderator
Electricity generation by nuclear fusion
lithium surrounding the reactor core. When struck by a high-energy neutron, the blanket heats up. It is then actively cooled with a working fluid that
Fusion_power
commercial nuclear reactors in the world, sorted by country, with operational status. The list only includes civilian nuclear power reactors used to generate
List of commercial nuclear reactors
List_of_commercial_nuclear_reactors
Indian nuclear reactor design
plutonium for use with thorium. The AHWR is a pressure-tube reactor moderated by heavy water and cooled by boiling light water. Its core consists of a calandria
Advanced_heavy-water_reactor
Russian fast neutron research reactor
research sodium-cooled fast reactor designed to test nuclear fuels, structural materials and coolants, as well as scientific experiments under fast neutron irradiation
BOR-60
Power generated from nuclear reactions
by reactor-grade plutonium (with a half-life 24,000 years). Some proposed reactor designs, such as the integral fast reactor and molten salt reactors, can
Nuclear_power
Nuclear research reactor in Oak Ridge, Tennessee
high-temperature gas-cooled reactor irradiations; and irradiation of candidate fusion reactor materials. The latter type of experiment requires fast neutron flux
High_Flux_Isotope_Reactor
Third-generation pressurised water nuclear reactor design
In Europe, this reactor design was called European Pressurised Reactor, and the internationalised name was Evolutionary Power Reactor, but it has been
EPR_(nuclear_reactor)
American nuclear technology company
Kaleidos microreactor is a high-temperature, gas-cooled design using helium coolant and TRISO fuel. The reactor is designed to fit in a single shipping container
Radiant_Nuclear
Propulsion system for marine vessels utilizing a nuclear powerplant
which were powered by lead-bismuth cooled reactors, while the US military developed a sole liquid sodium-cooled reactor onboard the USS Seawolf. However
Nuclear_marine_propulsion
Nuclear reactor design
would be very little that could be released in an accident. In a water-cooled reactor, high internal pressures provide a driving force for dispersion of radioactive
Stable_salt_reactor
sodium cooled fast reactor in Russia, began commercial electricity generation, while plans for a BN-1200 were initially conceived the future of the fast reactor
History_of_nuclear_power
Theoretical design for a compact fusion reactor
The ARC fusion reactor (affordable, robust, compact) is a design for a compact 400 MW fusion reactor developed by the Massachusetts Institute of Technology
ARC_fusion_reactor
International nuclear fusion research and engineering megaproject
ITER (originally an acronym for International Thermonuclear Experimental Reactor, and also meaning "the way" or "the path" in Latin) is an international
ITER
Nuclear reactor
The KN-3 reactor (VM-16) is the nuclear reactor used in pairs to power the Kirov-class battlecruisers. The reactor was also intended to be used on the
KN-3_reactor
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GAS COOLED-FAST-REACTOR
GAS COOLED-FAST-REACTOR
GAS COOLED-FAST-REACTOR
GAS COOLED-FAST-REACTOR
GAS COOLED-FAST-REACTOR
GAS COOLED-FAST-REACTOR
GAS COOLED-FAST-REACTOR
GAS COOLED-FAST-REACTOR
GAS COOLED-FAST-REACTOR
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