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High-flux research nuclear reactor
A materials testing reactor (MTR) is a high-flux research nuclear reactor aimed at studying materials exposed to a high neutron flux. The first Materials
Materials_testing_reactor
Early nuclear reactor that provided essential research for future reactors
The Materials Testing Reactor (MTR) was an early nuclear reactor specifically designed to facilitate the conception and the design of future reactors. It
Materials_Testing_Reactor
Location of two former nuclear research establishments in northern Scotland
development of civil fast breeder reactors, and the Vulcan Naval Reactor Test Establishment (NRTE), a military submarine reactor testing facility. Both have ended
Dounreay
Laboratory in Idaho Falls, Idaho, United States
Center. The Materials Test Area tested materials' exposure to reactor conditions. The Materials Test Area is part of the Advanced Test Reactor Complex. The
Idaho_National_Laboratory
Research reactor planned for operation by 2028 in France
The Jules Horowitz Reactor (Réacteur Jules Horowitz, RJH) is a materials testing reactor (MTR) cooled and moderated with water. It is under construction
Jules_Horowitz_Reactor
Materials testing nuclear reactor housed at Harwell, Oxfordshire, United Kingdom
DIDO was a materials testing nuclear reactor at the Atomic Energy Research Establishment at Harwell, Oxfordshire in the United Kingdom. It used enriched
DIDO_(nuclear_reactor)
Idaho National Laboratory research neutron source
Test Reactor (ATR) is a research reactor at the Idaho National Laboratory, located east of Arco, Idaho. This reactor was designed and is used to test
Advanced_Test_Reactor
Fast-neutron nuclear reactor cooled by molten lead
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 the
Lead-cooled_fast_reactor
Type of nuclear reactor that uses normal water
reactor whose purpose was to test the behavior of materials under neutron flux. This reactor, the Material Testing Reactor (MTR), was built in Idaho at
Light-water_reactor
OPAL reactor are: Irradiation of target materials to produce radioisotopes for medical and industrial applications Research in the fields of materials science
List of nuclear research reactors
List_of_nuclear_research_reactors
Topics referred to by the same term
railroad in Pennsylvania, US Materials testing reactor, a research reactor type Materials Testing Reactor, Idaho, US Mill test report (metals industry) Methionine
MTR_(disambiguation)
Device for controlled nuclear reactions
dating[clarification needed]) Research reactor: Typically reactors used for research and training, materials testing, or the production of radioisotopes
Nuclear_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
X-10 Graphite Reactor. Like these, it was also natural uranium-fuelled, graphite-moderated. It was the world's first materials testing reactor. Specifically
305_Test_Pile
Materials testing nuclear reactor at Harwell, Oxfordshire, United Kingdom
PLUTO was a materials testing nuclear reactor housed at the Atomic Energy Research Establishment, a former Royal Air Force airfield at Harwell, Oxfordshire
PLUTO_reactor
Nuclear power plant in California, US
gas above the reactor. The researchers determined the amount of radioactive materials released into the sodium, and noted the materials were removed with
Sodium_Reactor_Experiment
US nuclear ramjet project, 1957–1964
technological advances in metallurgy and materials science. Pneumatic motors necessary to control the reactor in flight had to operate while red-hot and
Project_Pluto
Nuclear reactor that killed 3 people in 1961
a United States Army experimental nuclear reactor at the National Reactor Testing Station (NRTS) in Idaho about forty miles (65 km) west of Idaho Falls
SL-1
Type of nuclear reactor
"Graphite reactor" directs here. For the graphite reactor at Oak Ridge National Laboratory, see X-10 Graphite Reactor. A graphite-moderated reactor is a nuclear
Graphite-moderated_reactor
Type of nuclear reactor cooled by molten salt
fuel is a mixture of molten salt with a fissile material. Only some small molten-salt test reactors have been built. As of 2026, no commercial MSR exists
Molten-salt_reactor
Nuclear reactor design
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
Integral_fast_reactor
Test sodium-cooled fast reactor in Ōarai, Ibaraki, Japan
doing tests on and advancing the development of that type of reactor, as an irradiation test facility for construction materials. It also does tests with
Jōyō_(nuclear_reactor)
Nuclear reactor generating more fissile material than it consumes
conventional reactors. These materials are called fertile materials since they can be bred into fuel by these breeder reactors. Breeder reactors achieve this
Breeder_reactor
Nuclear research reactor in Oak Ridge, Tennessee
of any research reactor in the world. The thermal and cold neutrons produced by HFIR are used to study physics, chemistry, materials science, engineering
High_Flux_Isotope_Reactor
Uncontrolled nuclear fission chain reaction
should only occur inside a safely shielded location, such as a reactor core or a suitable test environment. A criticality accident occurs if the same reaction
Criticality_accident
Type of nuclear reactor that uses molten material as fuel
The liquid fluoride thorium reactor (LFTR; often pronounced lifter) is a type of molten salt reactor. LFTRs use the thorium fuel cycle with a fluoride-based
Liquid fluoride thorium reactor
Liquid_fluoride_thorium_reactor
Type of nuclear reactor cooled by molten sodium
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
New nuclear reactor technologies under development
Generation IV (Gen IV) reactors are nuclear reactor design technologies that are envisioned as successors of generation III reactors. The Generation IV International
Generation_IV_reactor
Classes of nuclear reactors used by the United States Navy
such reactors, but they have since been decommissioned also. Reactors are designed by a number of contractors,[who?] then developed and tested at one
United_States_naval_reactors
1986 nuclear accident in the Soviet Union
conducting a test to simulate the cooling of the reactor during a serious accident in blackout conditions. The operators carried out the test following an
Chernobyl_disaster
Nuclear reactor where water boils in core
A boiling water reactor (BWR) is a type of nuclear reactor used for the generation of electrical power. It is the second most common type of electricity-generating
Boiling_water_reactor
Reactor accident due to core overheating
core melt accident, meltdown or partial core melt) is a severe nuclear reactor accident that results in core damage from overheating. The term nuclear
Nuclear_meltdown
Small modular reactors (SMR) are much smaller than the current nuclear reactors (300 MWe or less) and have compact and scalable designs which propose
List of small modular reactor designs
List_of_small_modular_reactor_designs
NASA project aimed at producing a nuclear reactor for space
Laboratory, the DUFF experiment showed that "for low-power reactor systems, nuclear testing can be accomplished with reasonable cost and schedule within
Kilopower
Nuclear device not intended for power or weapons
non-destructive testing, analysis and testing of materials, production of radioisotopes, research and public outreach and education. Research reactors that produce
Research_reactor
Project by the U.S. Department of Energy
compatibility with other reactor materials, particularly the coolant. Testing that provides a fundamental understanding of materials performance, validation
Versatile_Test_Reactor
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 Station
Experimental Breeder Reactor II
Experimental_Breeder_Reactor_II
Type of nuclear research reactor
flux reactor is a type of nuclear research reactor designed to produce a high neutron flux for scientific research, isotope production, and materials testing
High_flux_reactor
Naturally occurring uranium self-sustaining nuclear chain reactions
A natural nuclear fission reactor is a uranium deposit where self-sustaining nuclear chain reactions occur through natural geological processes rather
Natural nuclear fission reactor
Natural_nuclear_fission_reactor
Nuclear reactor where fast neutrons maintain a fission chain reaction
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
Fast-neutron_reactor
Deactivated nuclear test reactor in US
fast neutron reactor, as the name suggests. It is stated on the site dedicated to the FFTF, that it tested "advanced nuclear fuels, materials, components
Fast_Flux_Test_Facility
US Nuclear thermal rocket engine project (1956–1973)
restarted. In September, tests were conducted with a Kiwi B4 engine and PARKA, a Kiwi reactor used for testing at LASL. The two reactors were run 4.9 meters
NERVA
Topics referred to by the same term
Shah Makhdum Airport, Bangladesh, by IATA code Jules Horowitz Reactor, material test reactor in France This disambiguation page lists articles associated
RJH
Emergency shutdown of a nuclear reactor
A scram or SCRAM is an emergency shutdown of a nuclear reactor effected by terminating the fission reaction. It is also the name that is given to the
Scram
Tokamak
Engineering Test Reactor (Chinese: 中国聚变工程实验堆; pinyin: Zhōngguó Jùbiàn Gōngchéng Shíyànduī), or CFETR, is a proposed tokamak fusion reactor, which uses
China Fusion Engineering Test Reactor
China_Fusion_Engineering_Test_Reactor
Experimental nuclear-powered US Air Force satellite
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
SNAP-10A
Nuclear facility in Idaho, United States
structural materials. Constructed in 1958, and operated from 1959 until 1994, TREAT was built to conduct transient reactor tests where the test material is subjected
Transient Reactor Test Facility
Transient_Reactor_Test_Facility
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
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
Research reactor in Ōarai, Ibaraki, Japan
The high-temperature engineering test reactor (HTTR) is a graphite-moderated gas-cooled research reactor in Ōarai, Ibaraki, Japan operated by the Japan
High-temperature engineering test reactor
High-temperature_engineering_test_reactor
American nuclear physicist (1915–2006)
1961. Weinberg had the Materials Testing Reactor converted into a mock-up of a real reactor called the Low Intensity Test Reactor (LITR) or "Poor Man's
Alvin_M._Weinberg
Proposed fuel-recycling commercial reactor
Powerhouse is a small modular reactor design developed by Oklo Inc. It is a 75 MW pool-type sodium-cooled fast reactor. Its first commercial unit is under
Aurora_nuclear_reactor
Material fuelling nuclear reactors
fertile materials, such as 238U or thorium, which can be converted into fissile material when it absorbs a neutron. A breeder reactor is a reactor that uses
Nuclear_fuel
Nuclear reactor where the coolant is liquid metal
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 adapted
Liquid_metal_cooled_reactor
Concept nuclear reactor whose water operates at supercritical pressure
The supercritical water reactor (SCWR) is a concept Generation IV reactor, designed as a light water reactor (LWR) that operates at supercritical pressure
Supercritical_water_reactor
North Korean nuclear site
nuclear reactors. It is located in Nyongbyon County in North Pyongan Province, about 100 km north of Pyongyang. The center produced the fissile material for
Nyongbyon Nuclear Scientific Research Center
Nyongbyon_Nuclear_Scientific_Research_Center
Severe events involving radioactive materials
release to the environment, or a reactor core melt. The prime example of a "major nuclear accident" is one in which a reactor core is damaged and significant
Nuclear and radiation accidents and incidents
Nuclear_and_radiation_accidents_and_incidents
Electricity generation by nuclear fusion
Structural material stability is a critical issue. Materials that can survive the high temperatures and neutron bombardment experienced in a fusion reactor are
Fusion_power
Molten salt reactor program
to design, test, and build nuclear reactors that incorporate molten salt as a fuel-carrier and/or coolant, and thorium as a fertile material. The TMSR
TMSR (Chinese reactor project)
TMSR_(Chinese_reactor_project)
Belgian Nuclear Research Centre
industry. Commissioned in 1962, The Belgian Reactor 2 (BR2) is a materials testing reactor. It is a high-flux reactor (~ 1015 neutron・cm-2・s-1) in which neutrons
SCK_CEN
Chemical reactor materials selection is an important aspect in the design of a chemical reactor. There are four main groups of chemical reactors - CSTR
Chemical reactor materials selection
Chemical_reactor_materials_selection
Reactor-grade plutonium (RGPu) is the isotopic grade of plutonium that is found in spent nuclear fuel after the uranium-235 primary fuel that a nuclear
Reactor-grade_plutonium
U.S. Department of Energy reservation in South Carolina
1950s to produce materials used in the fabrication of nuclear weapons, primarily tritium and plutonium-239, by irradiating target materials with neutrons
Savannah_River_Plant
Pressurised water reactor series
first PWR2 reactor was completed in 1985 with testing beginning in August 1987 at the Vulcan Naval Reactor Test Establishment. The reactor fuel is highly
Rolls-Royce_PWR
International nuclear fusion research and engineering megaproject
the heavy-water CANDU fission reactors) is just 20 kilograms per year, insufficient for power plants. ITER will be testing tritium breeding blanket technology
ITER
Chemical element with atomic number 98 (Cf)
produced by the irradiation of plutonium targets at Materials Testing Reactor at National Reactor Testing Station, eastern Idaho; these findings were reported
Californium
Nuclear reactor design company
developing multiple designs of fast-neutron reactors, including a sodium-cooled fast reactor (SFR) and a molten-salt reactor. As of 2026, the company is constructing
TerraPower
Nuclear power plant in Eurajoki, Finland
work, excessively hot water flowed to the reactor water clean-up system filters. The hot water dissolved materials from the filters. When the clean-up system
Olkiluoto_Nuclear_Power_Plant
Type of very-high-temperature reactor
A pebble-bed reactor (PBR) is a type of nuclear reactor where the nuclear fuel is contained within a bed of pyrolytic graphite spheres (pebbles), with
Pebble-bed_reactor
First industrial-scale nuclear reactor
The B Reactor at the Hanford Site, near Richland, Washington, was the first large-scale nuclear reactor ever built, at 250 MW. It achieved criticality
B_Reactor
Space exploration using nuclear energy
Kilopower reactor. Aside from nuclear electric propulsion, more powerful nuclear space propulsion systems have been developed and undergone ground testing. Nuclear
Nuclear_power_in_space
Structure surrounding a nuclear reactor to prevent radioactive releases
attempts to stabilize the reactors. Containment systems for nuclear power reactors are distinguished by size, shape, materials used, and suppression systems
Containment_building
Type of nuclear fuel
high-temperature gas-cooled reactors (HTGRs), both prismatic-block and pebble-bed. The first reactor to use TRISO was the Dragon reactor, while the first commercial
TRISO_fuel
Substance that slows down particles with no electric charge
moderator (roughly 75% of the world's reactors). Solid graphite (20% of reactors) and heavy water (5% of reactors) are the main alternatives. Beryllium
Neutron_moderator
U.S. project 1946–1961
Aircraft Shield Test Reactor (ASTR), was operational but did not power the aircraft; the primary purpose of the flight program was testing the effectiveness
Aircraft_Nuclear_Propulsion
Nuclear reactor design
A pressurized heavy-water reactor (PHWR) is a nuclear reactor that uses heavy water (deuterium oxide D2O) as its coolant and neutron moderator. PHWRs
Pressurized heavy-water reactor
Pressurized_heavy-water_reactor
Feasibility experiment for aircraft nuclear propulsion
The Aircraft Reactor Experiment (ARE) was an experimental nuclear reactor designed to test the feasibility of fluid-fuel, high-temperature, high-power-density
Aircraft_Reactor_Experiment
Field of physics dealing with nuclear reactors
reactor for the production of energy. Most nuclear reactors use a chain reaction to induce a controlled rate of nuclear fission in fissile material,
Nuclear_reactor_physics
Substance that can absorb large quantities of neutrons in a reactor core
effect. However, neutron-absorbing materials, also called poisons, are intentionally inserted into some types of reactors in order to lower the high reactivity
Neutron_poison
Australia's first nuclear reactor
purpose was nuclear materials testing, using its high neutron flux to give materials intended for use in nuclear power reactors their entire expected
High_Flux_Australian_Reactor
American nuclear technology company
modular nuclear reactor, the Aurora Powerhouse, and intends to sell both electricity and radioisotopes produced by their Aurora reactors. The company's
Oklo_Inc.
German nuclear reactor test facility
captured and the materials used were flown out to the United States. Today, the Atomic Cellar Museum is located at the former site of the reactor. The main objective
Haigerloch_atomic_pile
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 research reactor in Washington State University
operating power of 100 kW. It was initially a General Electric Materials Test Reactor with plate-type fuel bundles, but was upgraded in 1967 to a 1MW
Washington State University Reactor
Washington_State_University_Reactor
U.S. project to build a nuclear thermal rocket
Testing of fuel elements and other materials science was done by the LASL N Division at TA-46 using various ovens and later a custom test reactor, the
Project_Rover
Class of nuclear reactor used for education and research
TRIGA is a swimming pool reactor that can be installed without a containment building, and is designed for research and testing use by scientific institutions
TRIGA
Type of Soviet nuclear power reactor
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
RBMK
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
Research nuclear reactor in Australia
have been known simply as the Lucas Heights reactor. The main reactor uses are: Irradiation of target materials to produce radioisotopes for medical and
Open-pool Australian lightwater reactor
Open-pool_Australian_lightwater_reactor
Type of nuclear reactor that operates at high temperatures as part of normal operation
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 output
High-temperature gas-cooled reactor
High-temperature_gas-cooled_reactor
French mathematician (1928–2023)
course qhe RD taught at CEA/Saclay/ INSTN. 1957. The Pegasus fuel material test reactor, in collaboration with Pierre Arditti and R. Raievski, CEA Cadarache
Robert_Dautray
Series of boiling water nuclear reactor safety experiments
boiling water nuclear reactors conducted by Argonne National Laboratory in the 1950s and 1960s at the National Reactor Testing Station in eastern Idaho
BORAX_experiments
Experimental molten-salt reactor under construction
The Molten Chloride Reactor Experiment (MCRE) is an experimental molten-salt reactor under construction at Idaho National Laboratory (INL). It is planned
Molten Chloride Reactor Experiment
Molten_Chloride_Reactor_Experiment
Chinese small modular nuclear reactor
HTR-PM". Nuclear Engineering International. 26 March 2020. "Cold testing of HTR-PM reactors completed : New Nuclear – World Nuclear News". www.world-nuclear-news
HTR-PM
Federal research center in Tennessee, US
the Spallation Neutron Source, the High Flux Isotope Reactor, and the Center for Nanophase Materials Sciences. Oak Ridge National Laboratory is managed
Oak_Ridge_National_Laboratory
Nuclear reactor in China
fast-reactor design, construction, and operational experience, and will be a key facility for testing and researching components and materials to be
China Experimental Fast Reactor
China_Experimental_Fast_Reactor
Retired research and test reactor
TR-2 nuclear reactor, also known as the Westinghouse Test Reactor or Westinghouse Testing Reactor (WTR) was a small research and test reactor designed and
Westinghouse_TR-2
Lead-cooled reactor family designed in Russia
other materials in the blanket, which can be used to convert nuclear waste materials into less dangerous forms. The idea of using fast neutron reactors as
BREST_(reactor)
Nuclear research facility in Mumbai, India
theoretical design of reactors to, computer modeling and simulation, risk analysis, development and testing of new reactor fuel, materials, etc. It also researches
Bhabha_Atomic_Research_Centre
American nuclear energy company
TX-1 facility. The company also began irradiation testing of TRISO-X fuel in the Advanced Test Reactor at Idaho National Laboratory in November 2025, and
X-energy
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