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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
Laboratory in Idaho Falls, Idaho, United States
Materials Test Area tested materials' exposure to reactor conditions. The Materials Test Area is part of the Advanced Test Reactor Complex. The Information
Idaho_National_Laboratory
Nuclear power system
Generating Station in Quebec, the Fugen Advanced Test Reactor in Japan, and the never-commissioned CIRENE reactor in Italy. These designs differ with the
Steam-Generating Heavy Water Reactor
Steam-Generating_Heavy_Water_Reactor
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
Project by the U.S. Department of Energy
The Versatile Test Reactor (VTR) was a project by the U.S. Department of Energy to build a fast-neutron test reactor by 2026. Funding for the project was
Versatile_Test_Reactor
Early nuclear reactor that provided essential research for future reactors
Materials Testing Reactor (MTR) was an early nuclear reactor specifically designed to facilitate the conception and the design of future reactors. It produced
Materials_Testing_Reactor
Breeder reactor in Tamil Nadu, India
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, India
Fast_Breeder_Test_Reactor
Nuclear reactor design
S-PRISM represents GVH's Generation IV reactor solution to closing the nuclear fuel cycle and is also part of its Advanced Recycling Center (ARC) proposition
PRISM_(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
Canadian third generation nuclear reactor design
The Advanced CANDU reactor (ACR), or ACR-1000, was a proposed Generation III+ nuclear reactor design, developed by Atomic Energy of Canada Limited (AECL)
Advanced_CANDU_reactor
reactor grade being defined as containing 19% or more Pu-240, coincides with the 1977 release of information about a 1962 "reactor grade nuclear test"
Reactor-grade_plutonium
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
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
Type of nuclear reactor cooled by molten salt
A molten-salt reactor (MSR) is a class of nuclear fission reactor in which the primary nuclear reactor coolant and/or the fuel is a mixture of molten salt
Molten-salt_reactor
Electromagnetic radiation from a charged particle in a medium
Cherenkov radiation is the characteristic blue glow of an underwater nuclear reactor. Its cause is similar to the cause of a sonic boom, the sharp sound heard
Cherenkov_radiation
Device for controlled nuclear reactions
A nuclear reactor is a device used to sustain a controlled fission nuclear chain reaction. They are used for commercial electricity, marine propulsion
Nuclear_reactor
Topics referred to by the same term
Advanced Test Reactor, nuclear research reactor at the Idaho National Laboratory, US Attenuated total reflectance in infrared spectroscopy Advanced tongue
ATR
Type of British nuclear reactor
The 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
Advanced_gas-cooled_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
engineering test reactor (HTTR) Ōarai JMTR (Japan Materials Testing Reactor) Naka JT-60 fusion reactor Nuclear Safety Research Reactor Fugen (ATR (Advanced Thermal
List of nuclear research reactors
List_of_nuclear_research_reactors
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
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
Laboratory's Advanced Test Reactor". U.S. Department of Energy. March 12, 2018. Retrieved November 28, 2020. "Advanced Test Reactor". Idaho National Laboratory
List of power stations in Idaho
List_of_power_stations_in_Idaho
Type of nuclear reactor that uses normal water
The light-water reactor (LWR) is a type of thermal-neutron reactor that uses normal water, as opposed to heavy water, as both its coolant and neutron moderator;
Light-water_reactor
South Korean advanced pressurized water nuclear reactor
The APR-1400 (for Advanced Power Reactor 1400 MW electricity) is an advanced pressurized water nuclear reactor designed by the Korea Electric Power Corporation
APR-1400
UK experimental HTR, operated from 1965 to 1976
The Windscale Advanced Gas Cooled Reactor (WAGR) was a nuclear power plant constructed on the Sellafield nuclear site in Cumbria, England. Commissioned
Windscale Advanced Gas Cooled Reactor
Windscale_Advanced_Gas_Cooled_Reactor
Type of nuclear reactor, CO2 or He cooled
engineering test reactor (since 1999) Gas Turbine Modular Helium Reactor (General Atomics design) Steam Cycle High-Temperature Gas-Cooled Reactor (Areva SMR
Gas-cooled_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
Nuclear reactor generating more fissile material than it consumes
A breeder reactor is a nuclear reactor that generates more fissile material than it consumes. These reactors can be fueled with more-commonly available
Breeder_reactor
Type of nuclear reactor
graphite-moderated nuclear reactors have been used in commercial electricity generation: Gas-cooled reactors Magnox UNGG reactor Advanced gas-cooled reactor (AGR) Water-cooled
Graphite-moderated_reactor
Indian fast breeder nuclear reactor design
gained from operating the lower power Kalpakkam Mini reactor (KAMINI) and Fast Breeder Test Reactor (FBTR). The PFBR is designed to generate electricity
Prototype Fast Breeder Reactor
Prototype_Fast_Breeder_Reactor
American nuclear technology company
Energy's Reactor Pilot Program. As part of the program, Oklo is constructing a pool-type isotope production reactor, the Groves Isotope Test Reactor, near
Oklo_Inc.
Nuclear facility in Idaho, United States
Transient Reactor Test Facility (TREAT) is an air-cooled, graphite moderated, thermal spectrum test nuclear reactor designed to test reactor fuels and
Transient Reactor Test Facility
Transient_Reactor_Test_Facility
Indian nuclear reactor design
The Advanced Heavy-Water Reactor (AHWR) or AHWR-300 is an Indian Generation III+ reactor design developed by the Bhabha Atomic Research Centre and intended
Advanced_heavy-water_reactor
US nuclear ramjet project, 1957–1964
kilometers (8 sq mi) at NTS Site 401, also known as Jackass Flats. The test reactors were moved about on a railroad car that could be controlled remotely
Project_Pluto
Nuclear research facility in Mumbai, India
the theoretical design of reactors to, computer modeling and simulation, risk analysis, development and testing of new reactor fuel, materials, etc. It
Bhabha_Atomic_Research_Centre
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
Material fuelling nuclear reactors
It is currently used in the Advanced Test Reactor (ATR) at Idaho National Laboratory, and the nuclear research reactor at the University of Massachusetts
Nuclear_fuel
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 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
U.S. project to build a nuclear thermal rocket
Nuclear reactors for Project Rover were built at LASL Technical Area 18 (TA-18), also known as the Pajarito Canyon Site. They were tested there at very
Project_Rover
U.S. government research and development program
Laboratories (SNL) Advanced Test Reactor (ATR) National Scientific User Facility Center for Advanced Energy Studies (CAES) Consortium for Advanced Simulation
Light Water Reactor Sustainability Program
Light_Water_Reactor_Sustainability_Program
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 1957
Organic Moderated Reactor Experiment
Organic_Moderated_Reactor_Experiment
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
American nuclear power plant
AP1000 (Advanced Passive 1000) is a nuclear power plant designed and sold by Westinghouse Electric Company. The plant is a pressurized water reactor with
AP1000
Nuclear energy extracted from thorium isotopes
thorium. The AEC began an advanced converters program, which identified the heavy-water reactor, high-temperature gas-cooled reactor (HTGR), thorium seed-blanket
Thorium-based_nuclear_power
Nuclear reactor, Oak Ridge 1965–1969
section data. It was a test reactor simulating the neutronic "kernel" of a type of inherently safer epithermal thorium breeder reactor called the liquid fluoride
Molten-Salt Reactor Experiment
Molten-Salt_Reactor_Experiment
Topics referred to by the same term
Inclusive Design Research Centre Advanced Technology Research Council Advanced Test Reactor Critical, a part of a nuclear reactor United States Alien Terrorist
ATRC
US Nuclear thermal rocket engine project (1956–1973)
rocket. Reactors were tested at very low power before being shipped to Jackass Flats in the Nevada Test Site. While LASL concentrated on reactor development
NERVA
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
Soviet physicist (1904–1990)
Cherenkov radiation is named for his discovery of the phenomenon; pictured here glowing is the core of the Advanced Test Reactor.
Pavel_Cherenkov
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
Experimental tokamak
Test Reactor (CFETR) HL-2M List of fusion experiments ASDEX Upgrade ITER Joint European Torus JT-60 KSTAR "China's New Thermonuclear Fusion Reactor Test
Experimental Advanced Superconducting Tokamak
Experimental_Advanced_Superconducting_Tokamak
Nuclear power station located near Kemmerer, WY
Washington-based reactor developer, received funding in 2020 to construct a Natrium reactor as part of the Department of Energy's Advanced Reactor Demonstration
Kemmerer_Power_Station
Nuclear reactor design company
cost-share funding through the Advanced Reactor Demonstration Program (ARDP) to test, license and build an advanced reactor within seven years. Company objectives
TerraPower
U.S. project 1946–1961
operational nuclear reactor on board. The NTA flew a total of 47 times testing the reactor over West Texas and Southern New Mexico. The reactor, named the Aircraft
Aircraft_Nuclear_Propulsion
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
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
Person who controls a nuclear reactor
A reactor operator (or nuclear reactor operator) is an individual at a nuclear power plant or other nuclear reactor who is responsible for directly controlling
Reactor_operator
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
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
Type of nuclear reactor
A pressurized water reactor (PWR) is a type of light-water nuclear reactor. PWRs are the most common type of nuclear power reactor, representing almost
Pressurized_water_reactor
NASA project aimed at producing a nuclear reactor for space
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
Kilopower
City in Idaho, United States
Among other projects, INL operates and manages the world-famous Advanced Test Reactor (ATR). According to the United States Census Bureau, the city has
Idaho_Falls,_Idaho
Soviet nuclear thermal rocket engine
NERVA (the U.S. nuclear thermal rocket engine project). The design of the reactor core included thermal insulation between uranium carbide/tungsten carbide
RD-0410
India's premier nuclear research centre
Breeder Test Reactor (FBTR) is IGCAR's flagship facility and a cornerstone of India's fast reactor programme. It is a sodium-cooled fast breeder reactor, maintained
Indira Gandhi Centre for Atomic Research
Indira_Gandhi_Centre_for_Atomic_Research
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
American nuclear energy company
fluoride salt-cooled high-temperature reactors (FHRs), a type of molten-salt reactor, in a small modular reactor (SMR) form factor. Kairos Power was founded
Kairos_Power
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
Space exploration using nuclear energy
United States tested the first and its only space reactor aboard SNAP-10A for 43 days in 1965. The Soviet Union's US-A program tested the BES-5 and TOPAZ-I
Nuclear_power_in_space
American nuclear technology company
up sites for advanced reactor roll-out". Reuters. Retrieved August 23, 2026. Launch Pad will provide authorization to build, fuel, and test Radiant's first
Radiant_Nuclear
German nuclear reactor test facility
setting up the largest German reactor test to date in the still-intact Dahlem institute bunker when the Red Army advanced to within 80 km of Berlin. As
Haigerloch_atomic_pile
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
Nuclear reactor design
the Advanced Boiling Water Reactor (ABWR). All are designs by GE Vernova Hitachi Nuclear Energy (GVH), and are based on previous Boiling Water Reactor designs
Economic Simplified Boiling Water Reactor
Economic_Simplified_Boiling_Water_Reactor
Type of nuclear fuel
Due to a lack of irradiation data, UCO kernels were tested for NGNP during the US Advanced Gas Reactor Fuel Development and Qualification (AGR) Program beginning
TRISO_fuel
Nuclear reactor in Sweden
principle with a condensation pool, used by nearly all BWR-reactors in the world, was tested. In a reactor with this design steam from postulated pipe breaks
R4_nuclear_reactor
Nuclear reactor design
The advanced boiling water reactor (ABWR) is a Generation III boiling water reactor. The ABWR is currently offered by GE Vernova Hitachi Nuclear Energy
Advanced boiling water reactor
Advanced_boiling_water_reactor
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
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
Class of Indian nuclear-powered ballistic missile submarines
enabled the production version of the reactor for Arihant. The reactor subsystems were tested at the Machinery Test Center in Visakhapatnam. Facilities
Arihant-class_submarine
US Defense Department project of building a deployable nuclear power reactor
Pele transportable nuclear reactor, and test it for up to three years; if test performance warrants it, this type of reactor will generate a nominal 2
Project_Pele
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)
Type of nuclear power reactor
of fast neutron reactors. The RMWR concept builds upon the Advanced Boiling Water Reactor and is under active development in theoretical studies, particularly
Reduced moderation water reactor
Reduced_moderation_water_reactor
Russian fast neutron research reactor
The BOR-60 is an operational Russian research sodium-cooled fast reactor designed to test nuclear fuels, structural materials and coolants, as well as scientific
BOR-60
Nuclear spacecraft propulsion technology
Shuttle development. Although more than ten reactors of varying power output have been built and tested, as of 2025[update], no nuclear thermal rocket
Nuclear_thermal_rocket
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
Nuclear fission reactor family
The KLT-40 family are nuclear fission reactors originating from OK-150 and OK-900 ship reactors. KLT-40 were developed to power the Taymyr-class icebreakers
KLT-40_reactor
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
Research reactor in Daejeon, South Korea
The High-Flux Advanced Neutron Application Reactor (HANARO; Korean: 하나로) is a 30 MW multi-purpose research reactor located at Daejeon, Republic of Korea
High-Flux Advanced Neutron Application Reactor
High-Flux_Advanced_Neutron_Application_Reactor
Very small nuclear reactor of 1-20 MW capacity
reactors (LWRs), high-temperature gas reactors (HTGRs), and advanced reactor designs, such as liquid metal fast reactors (FRs), molten salt reactors (MSRs)
Nuclear_microreactor
U.S. Department of Energy reservation in South Carolina
Laboratory leveraging both the High Flux Isotope Reactor at Oak Ridge and the Advanced Test Reactor at Idaho National Laboratory. The U.S. Transplutonium
Savannah_River_Plant
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
Nuclear power plant design
reactor (DMSR), a reactor design from Oak Ridge National Laboratory. In addition, it incorporates some elements found in the small modular advanced high
Integral_Molten_Salt_Reactor
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
American nuclear-energy company
Energy (DOE) selected Deep Fission for its Reactor Pilot Program, a pathway for testing advanced reactors outside the national laboratories. It is a development-stage
Deep_Fission,_Inc.
North Korean nuclear site
North Korea's six nuclear weapon tests from 2006 to 2017, and since 2009 is developing indigenous light water reactor nuclear power station technology
Nyongbyon Nuclear Scientific Research Center
Nyongbyon_Nuclear_Scientific_Research_Center
CANFLEX is an advanced fuel bundle designed for CANDU design nuclear reactors. Its name is derived from its function: CANDU FLEXible fueling. It was developed
CANFLEX
US nuclear technology company
projects such as coal gasification and gradually ceased designing and testing nuclear reactors. Atomics International was eventually merged with another division
Atomics_International
Prototype pebble bed reactor, China
portal Nuclear technology portal Pebble bed modular reactor High-temperature engineering test reactor HTR-10, Tsinghua University, 2010, archived from the
HTR-10
South Korean nuclear reactor
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
OPR-1000
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