Table of Contents
70 relations: Actinide, Argonne National Laboratory, ASTRID (reactor), BN-1200 reactor, BN-350 reactor, BN-600 reactor, BN-800 reactor, Boiling point, Breeder reactor, CFR-600, China Experimental Fast Reactor, Clinch River Breeder Reactor Project, Collision, CTV Television Network, Decay heat, Depleted uranium, Dounreay, Electromagnetic pump, Enriched uranium, Eutectic system, Experimental Breeder Reactor I, Experimental Breeder Reactor II, Fast Breeder Test Reactor, Fast Flux Test Facility, Fast-neutron reactor, Gas-cooled fast reactor, Generation IV reactor, Heat capacity, Heat exchanger, Integral fast reactor, International Atomic Energy Agency, Isotopes of magnesium, Isotopes of sodium, Jōyō (nuclear reactor), Kemmerer, Wyoming, Lanthanum, Lead-cooled fast reactor, Liquid metal cooled reactor, Magnesium oxide, Monju Nuclear Power Plant, MOX fuel, Neutron, Neutron moderator, New Brunswick, Nitrogen, Nuclear fission product, Nuclear fuel cycle, Ontario, Operating temperature, Phénix, ... Expand index (20 more) »
- Liquid metal fast reactors
Actinide
The actinide or actinoid series encompasses at least the 14 metallic chemical elements in the 5f series, with atomic numbers from 89 to 102, actinium through nobelium.
See Sodium-cooled fast reactor and Actinide
Argonne National Laboratory
Argonne National Laboratory is a federally funded research and development center in Lemont, Illinois, United States.
See Sodium-cooled fast reactor and Argonne National Laboratory
ASTRID (reactor)
ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) was a proposal for a 600 MW sodium-cooled fast breeder reactor (Generation IV), proposed by the Commissariat à l'énergie atomique (CEA). Sodium-cooled fast reactor and ASTRID (reactor) are liquid metal fast reactors.
See Sodium-cooled fast reactor and ASTRID (reactor)
BN-1200 reactor
The BN-1200 reactor is a sodium-cooled fast breeder reactor project, under development by OKBM Afrikantov in Zarechny, Russia. Sodium-cooled fast reactor and bN-1200 reactor are liquid metal fast reactors.
See Sodium-cooled fast reactor and BN-1200 reactor
BN-350 reactor
The BN-350 was a sodium-cooled, fast reactor located at the Mangyshlak Nuclear Power Plant, located in Aktau (formerly known as Shevchenko), Kazakhstan, on the shore of the Caspian Sea. Sodium-cooled fast reactor and BN-350 reactor are liquid metal fast reactors.
See Sodium-cooled fast reactor and BN-350 reactor
BN-600 reactor
The BN-600 reactor is a sodium-cooled fast breeder reactor, built at the Beloyarsk Nuclear Power Station, in Zarechny, Sverdlovsk Oblast, Russia. Sodium-cooled fast reactor and bN-600 reactor are liquid metal fast reactors.
See Sodium-cooled fast reactor and BN-600 reactor
BN-800 reactor
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 Oblast, Russia. Sodium-cooled fast reactor and bN-800 reactor are liquid metal fast reactors.
See Sodium-cooled fast reactor and BN-800 reactor
Boiling point
The boiling point of a substance is the temperature at which the vapor pressure of a liquid equals the pressure surrounding the liquid and the liquid changes into a vapor.
See Sodium-cooled fast reactor and Boiling point
Breeder reactor
A breeder reactor is a nuclear reactor that generates more fissile material than it consumes.
See Sodium-cooled fast reactor and Breeder reactor
CFR-600
The CFR-600 (Xiapu fast reactor pilot project) is a sodium-cooled pool-type fast-neutron nuclear reactor under construction in Xiapu County, Fujian province, China, on Changbiao Island.
See Sodium-cooled fast reactor and CFR-600
China Experimental Fast Reactor
The China Experimental Fast Reactor (CEFR) is China's first fast nuclear reactor, and is located outside Beijing at the China Institute of Atomic Energy.
See Sodium-cooled fast reactor and China Experimental Fast Reactor
Clinch River Breeder Reactor Project
The Clinch River Breeder Reactor Project was a nuclear reactor project that aimed to build the USA's first large-scale demonstration breeder reactor plant.
See Sodium-cooled fast reactor and Clinch River Breeder Reactor Project
Collision
In physics, a collision is any event in which two or more bodies exert forces on each other in a relatively short time.
See Sodium-cooled fast reactor and Collision
CTV Television Network
The CTV Television Network, commonly known as CTV, is a Canadian English-language terrestrial television network.
See Sodium-cooled fast reactor and CTV Television Network
Decay heat
Decay heat is the heat released as a result of radioactive decay.
See Sodium-cooled fast reactor and Decay heat
Depleted uranium
Depleted uranium (DU; also referred to in the past as Q-metal, depletalloy or D-38) is uranium with a lower content of the fissile isotope 235U than natural uranium.
See Sodium-cooled fast reactor and Depleted uranium
Dounreay
Dounreay (Dùnrath) is a small settlement and the site of two large nuclear establishments on the north coast of Caithness in the Highland area of Scotland. Sodium-cooled fast reactor and Dounreay are liquid metal fast reactors.
See Sodium-cooled fast reactor and Dounreay
Electromagnetic pump
An electromagnetic pump is a pump that moves liquid metal, molten salt, brine, or other electrically conductive liquid using electromagnetism.
See Sodium-cooled fast reactor and Electromagnetic pump
Enriched uranium
Enriched uranium is a type of uranium in which the percent composition of uranium-235 (written 235U) has been increased through the process of isotope separation.
See Sodium-cooled fast reactor and Enriched uranium
Eutectic system
A eutectic system or eutectic mixture is a homogeneous mixture that has a melting point lower than those of the constituents.
See Sodium-cooled fast reactor and Eutectic system
Experimental Breeder Reactor I
Experimental Breeder Reactor I (EBR-I) is a decommissioned research reactor and U.S. National Historic Landmark located in the desert about southeast of Arco, Idaho.
See Sodium-cooled fast reactor and Experimental Breeder Reactor I
Experimental Breeder Reactor II
Experimental Breeder Reactor-II (EBR-II) was a sodium-cooled fast reactor designed, built and operated by Argonne National Laboratory at the National Reactor Testing Station in Idaho.
See Sodium-cooled fast reactor and Experimental Breeder Reactor II
Fast Breeder Test Reactor
The Fast Breeder Test Reactor (FBTR) is a breeder reactor located at Kalpakkam, Tamil Nadu, India. Sodium-cooled fast reactor and Fast Breeder Test Reactor are liquid metal fast reactors.
See Sodium-cooled fast reactor and Fast Breeder Test Reactor
Fast Flux Test Facility
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.
See Sodium-cooled fast reactor and Fast Flux Test Facility
Fast-neutron reactor
A fast-neutron reactor (FNR) or fast-spectrum reactor or simply a fast reactor is a category of nuclear reactor in which the fission chain reaction is sustained by fast neutrons (carrying energies above 1 MeV, on average), as opposed to slow thermal neutrons used in thermal-neutron reactors.
See Sodium-cooled fast reactor and Fast-neutron reactor
Gas-cooled fast reactor
The gas-cooled fast reactor (GFR) system is a nuclear reactor design which is currently in development.
See Sodium-cooled fast reactor and Gas-cooled fast reactor
Generation IV reactor
Generation IV (Gen IV) reactors are nuclear reactor design technologies that are envisioned as successors of generation III reactors.
See Sodium-cooled fast reactor and Generation IV reactor
Heat capacity
Heat capacity or thermal capacity is a physical property of matter, defined as the amount of heat to be supplied to an object to produce a unit change in its temperature.
See Sodium-cooled fast reactor and Heat capacity
Heat exchanger
A heat exchanger is a system used to transfer heat between a source and a working fluid.
See Sodium-cooled fast reactor and Heat exchanger
Integral fast reactor
The integral fast reactor (IFR), originally the advanced liquid-metal reactor (ALMR), is a design for a nuclear reactor using fast neutrons and no neutron moderator (a "fast" reactor).
See Sodium-cooled fast reactor and Integral fast reactor
International Atomic Energy Agency
The International Atomic Energy Agency (IAEA) is an intergovernmental organization that seeks to promote the peaceful use of nuclear energy and to inhibit its use for any military purpose, including nuclear weapons.
See Sodium-cooled fast reactor and International Atomic Energy Agency
Isotopes of magnesium
Magnesium (12Mg) naturally occurs in three stable isotopes:,, and.
See Sodium-cooled fast reactor and Isotopes of magnesium
Isotopes of sodium
There are 20 isotopes of sodium (11Na), ranging from to (except for the still-unknown 36Na and 38Na), and two isomers (and). is the only stable (and the only primordial) isotope.
See Sodium-cooled fast reactor and Isotopes of sodium
Jōyō (nuclear reactor)
is a test sodium-cooled fast reactor located in Ōarai, Ibaraki, Japan, operated by the Japan Atomic Energy Agency. Sodium-cooled fast reactor and Jōyō (nuclear reactor) are liquid metal fast reactors.
See Sodium-cooled fast reactor and Jōyō (nuclear reactor)
Kemmerer, Wyoming
Kemmerer is the largest city in and the county seat of Lincoln County, Wyoming, United States.
See Sodium-cooled fast reactor and Kemmerer, Wyoming
Lanthanum
Lanthanum is a chemical element; it has symbol La and atomic number 57.
See Sodium-cooled fast reactor and Lanthanum
Lead-cooled fast reactor
The lead-cooled fast reactor is a nuclear reactor design that use molten lead or lead-bismuth eutectic coolant. Sodium-cooled fast reactor and lead-cooled fast reactor are liquid metal fast reactors.
See Sodium-cooled fast reactor and Lead-cooled fast reactor
Liquid metal cooled reactor
A liquid metal cooled nuclear reactor, or LMR is a type of nuclear reactor where the primary coolant is a liquid metal. Sodium-cooled fast reactor and liquid metal cooled reactor are liquid metal fast reactors.
See Sodium-cooled fast reactor and Liquid metal cooled reactor
Magnesium oxide
Magnesium oxide (MgO), or magnesia, is a white hygroscopic solid mineral that occurs naturally as periclase and is a source of magnesium (see also oxide).
See Sodium-cooled fast reactor and Magnesium oxide
Monju Nuclear Power Plant
was a Japanese sodium-cooled fast reactor, located near the Tsuruga Nuclear Power Plant, Fukui Prefecture. Sodium-cooled fast reactor and Monju Nuclear Power Plant are liquid metal fast reactors.
See Sodium-cooled fast reactor and Monju Nuclear Power Plant
MOX fuel
Mixed oxide fuel, commonly referred to as MOX fuel, is nuclear fuel that contains more than one oxide of fissile material, usually consisting of plutonium blended with natural uranium, reprocessed uranium, or depleted uranium.
See Sodium-cooled fast reactor and MOX fuel
Neutron
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See Sodium-cooled fast reactor and Neutron
Neutron moderator
In nuclear engineering, a neutron moderator is a medium that reduces the speed of fast neutrons, ideally without capturing any, leaving them as thermal neutrons with only minimal (thermal) kinetic energy.
See Sodium-cooled fast reactor and Neutron moderator
New Brunswick
New Brunswick (Nouveau-Brunswick) is one of the thirteen provinces and territories of Canada.
See Sodium-cooled fast reactor and New Brunswick
Nitrogen
Nitrogen is a chemical element; it has symbol N and atomic number 7.
See Sodium-cooled fast reactor and Nitrogen
Nuclear fission product
Nuclear fission products are the atomic fragments left after a large atomic nucleus undergoes nuclear fission.
See Sodium-cooled fast reactor and Nuclear fission product
Nuclear fuel cycle
The nuclear fuel cycle, also called nuclear fuel chain, is the progression of nuclear fuel through a series of differing stages. Sodium-cooled fast reactor and nuclear fuel cycle are radioactive waste.
See Sodium-cooled fast reactor and Nuclear fuel cycle
Ontario
Ontario is the southernmost province of Canada.
See Sodium-cooled fast reactor and Ontario
Operating temperature
An operating temperature is the allowable temperature range of the local ambient environment at which an electrical or mechanical device operates.
See Sodium-cooled fast reactor and Operating temperature
Phénix
Phénix (French for phoenix) was a small-scale (gross 264/net 233 MWe) prototype fast breeder reactor, located at the Marcoule nuclear site, near Orange, France. Sodium-cooled fast reactor and Phénix are liquid metal fast reactors.
See Sodium-cooled fast reactor and Phénix
Plutonium
Plutonium is a chemical element; it has symbol Pu and atomic number 94.
See Sodium-cooled fast reactor and Plutonium
Prototype Fast Breeder Reactor
The Prototype Fast Breeder Reactor (PFBR) is a 500 MWe sodium-cooled, fast breeder reactor that is being constructed at Kokkilamedu, near Kalpakkam, in Tamil Nadu state, India. Sodium-cooled fast reactor and Prototype Fast Breeder Reactor are liquid metal fast reactors.
See Sodium-cooled fast reactor and Prototype Fast Breeder Reactor
Rapsodie
Rapsodie was an experimental nuclear reactor built in Cadarache in France.
See Sodium-cooled fast reactor and Rapsodie
Reduced moderation water reactor
The Reduced-Moderation Water Reactor (RMWR), also referred to as the Resource-renewable BWR, is a proposed type of light water moderated nuclear power reactor, featuring some characteristics of a fast neutron reactor, thereby combining the established and proven technology of light water reactors with the desired features of fast neutron reactors.
See Sodium-cooled fast reactor and Reduced moderation water reactor
S1G reactor
The S1G reactor is a naval reactor used by the United States Navy to provide electricity generation and propulsion on warships. Sodium-cooled fast reactor and S1G reactor are liquid metal fast reactors.
See Sodium-cooled fast reactor and S1G reactor
S2G reactor
The S2G reactor was a naval reactor used by the United States Navy to provide electricity generation and propulsion on warships, and the only liquid metal cooled reactor yet deployed by the US Navy. Sodium-cooled fast reactor and S2G reactor are liquid metal fast reactors.
See Sodium-cooled fast reactor and S2G reactor
Saskatchewan
Saskatchewan is a province in Western Canada, bordered on the west by Alberta, on the north by the Northwest Territories, on the east by Manitoba, to the northeast by Nunavut, and to the south by the United States (Montana and North Dakota).
See Sodium-cooled fast reactor and Saskatchewan
SNR-300
The SNR-300 was a fast breeder sodium-cooled nuclear reactor built near the town of Kalkar, North Rhine-Westphalia, Germany. Sodium-cooled fast reactor and SNR-300 are liquid metal fast reactors.
See Sodium-cooled fast reactor and SNR-300
Sodium
Sodium is a chemical element; it has symbol Na (from Neo-Latin natrium) and atomic number 11.
See Sodium-cooled fast reactor and Sodium
Sodium Reactor Experiment
The Sodium Reactor Experiment was a pioneering nuclear power plant built by Atomics International at the Santa Susana Field Laboratory near Simi Valley, California.
See Sodium-cooled fast reactor and Sodium Reactor Experiment
Superphénix
Superphénix (Superphoenix, SPX) was a nuclear power station prototype on the Rhône river at Creys-Malville in France, close to the border with Switzerland. Sodium-cooled fast reactor and Superphénix are liquid metal fast reactors.
See Sodium-cooled fast reactor and Superphénix
TerraPower
TerraPower is an American nuclear reactor design and development engineering company headquartered in Bellevue, Washington.
See Sodium-cooled fast reactor and TerraPower
Thermal efficiency
In thermodynamics, the thermal efficiency (\eta_) is a dimensionless performance measure of a device that uses thermal energy, such as an internal combustion engine, steam turbine, steam engine, boiler, furnace, refrigerator, ACs etc.
See Sodium-cooled fast reactor and Thermal efficiency
Transuranic waste
Transuranic waste (TRU) is stated by U.S. regulations, and independent of state or origin, to be waste which has been contaminated with alpha emitting transuranic radionuclides possessing half-lives greater than 20 years and in concentrations greater than 100 nCi/g (3.7 MBq/kg). Sodium-cooled fast reactor and transuranic waste are radioactive waste.
See Sodium-cooled fast reactor and Transuranic waste
United States Department of Energy
The United States Department of Energy (DOE) is an executive department of the U.S. federal government that oversees U.S. national energy policy and energy production, the research and development of nuclear power, the military's nuclear weapons program, nuclear reactor production for the United States Navy, energy-related research, and energy conservation.
See Sodium-cooled fast reactor and United States Department of Energy
United States naval reactors
United States naval reactors are nuclear reactors used by the United States Navy aboard certain ships to generate the steam used to produce power for propulsion, electric power, catapulting airplanes in aircraft carriers, and a few more minor uses.
See Sodium-cooled fast reactor and United States naval reactors
Uranium
Uranium is a chemical element; it has symbol U and atomic number 92.
See Sodium-cooled fast reactor and Uranium
Water
Water is an inorganic compound with the chemical formula.
See Sodium-cooled fast reactor and Water
Xiapu
Xiapu (Foochow Romanized: Hà-puō) is a county in the municipal region of Ningde, Fujian, People's Republic of China, located along a stretch of East China Sea coast, with many harbours and islands.
See Sodium-cooled fast reactor and Xiapu
Zirconium
Zirconium is a chemical element; it has symbol Zr and atomic number 40.
See Sodium-cooled fast reactor and Zirconium
See also
Liquid metal fast reactors
- ALFRED (nuclear reactor)
- ASTRID (reactor)
- BM-40A reactor
- BN-1200 reactor
- BN-350 reactor
- BN-600 reactor
- BN-800 reactor
- BREST (reactor)
- Dounreay
- Dual fluid reactor
- FBR-600
- Fast Breeder Test Reactor
- Jōyō (nuclear reactor)
- Lead-cooled fast reactor
- Liquid metal cooled reactor
- MYRRHA
- Monju Nuclear Power Plant
- OK-550 reactor
- Phénix
- Prototype Fast Breeder Reactor
- S1G reactor
- S2G reactor
- SNR-300
- Sodium-cooled fast reactor
- Superphénix
- VT-1 reactor
References
Also known as Gen IV LMFR, Loop type LMFBR, Pool type LMFBR, Pool-type LMFBR, Sodium cooled fast reactor, Sodium fast reactor, Sodium reactor.