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NUCLEAR REACTOR-COOLANT

  • Nuclear reactor coolant
  • Coolant in a nuclear reactor

    A nuclear reactor coolant is a coolant in a nuclear reactor used to remove heat from the nuclear reactor core and transfer it to electrical generators

    Nuclear reactor coolant

    Nuclear_reactor_coolant

  • Heavy-water reactor
  • Type of nuclear reactor

    reactor (HWR) is a type of nuclear reactor which uses heavy water (D2O, deuterium oxide) as a neutron moderator. It may also use this as the coolant,

    Heavy-water reactor

    Heavy-water reactor

    Heavy-water_reactor

  • Nuclear reactor
  • Device for controlled nuclear reactions

    from nuclear fission is passed to a working fluid coolant. In commercial reactors, this drives turbines and electrical generator shafts. Some reactors are

    Nuclear reactor

    Nuclear reactor

    Nuclear_reactor

  • Pressurized water 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

    Pressurized water reactor

    Pressurized_water_reactor

  • Liquid metal cooled reactor
  • 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

    Liquid_metal_cooled_reactor

  • Molten-salt 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

    Molten-salt reactor

    Molten-salt_reactor

  • Thermal-neutron reactor
  • Nuclear reactor that uses moderated neutrons

    nuclear reactor coolant. Nuclear fuel, which is a fissile material, usually uranium. Reactor vessel that is a pressure vessel containing the coolant and

    Thermal-neutron reactor

    Thermal-neutron_reactor

  • BN-600 reactor
  • Russian sodium-cooled fast breeder reactor

    BN-350 reactor. In 2014, its larger sister reactor, the BN-800 reactor, began operation. The plant is a pool type LMFBR, where the reactor, coolant pumps

    BN-600 reactor

    BN-600 reactor

    BN-600_reactor

  • Integral fast 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

    Integral fast reactor

    Integral_fast_reactor

  • Gas-cooled reactor
  • Type of nuclear reactor, CO2 or He cooled

    gas-cooled reactor (GCR) is a nuclear reactor that uses graphite as a neutron moderator and a gas (carbon dioxide or helium in extant designs) as coolant. Although

    Gas-cooled reactor

    Gas-cooled_reactor

  • BREST (reactor)
  • Lead-cooled reactor family designed in Russia

    chosen as a coolant for being high-boiling, radiation-resistant, low-activated and at atmospheric pressure. In a traditional nuclear reactor design, the

    BREST (reactor)

    BREST_(reactor)

  • Light-water reactor
  • 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

    Light-water reactor

    Light-water_reactor

  • Fast-neutron 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

    Fast-neutron reactor

    Fast-neutron_reactor

  • Organic nuclear 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

    Organic nuclear reactor

    Organic_nuclear_reactor

  • Sodium-cooled fast reactor
  • Type of nuclear reactor cooled by molten sodium

    fast reactor cooled by liquid sodium-potassium alloy, and demonstrated the concept of nuclear breeding. It also established sodium as the coolant of choice

    Sodium-cooled fast reactor

    Sodium-cooled fast reactor

    Sodium-cooled_fast_reactor

  • Lead-cooled fast reactor
  • Fast-neutron nuclear reactor cooled by molten lead

    reactor is a nuclear reactor design that uses molten lead or lead-bismuth eutectic as its coolant. These materials can be used as the primary coolant

    Lead-cooled fast reactor

    Lead-cooled fast reactor

    Lead-cooled_fast_reactor

  • Nuclear microreactor
  • Very small nuclear reactor of 1-20 MW capacity

    A nuclear microreactor is a type of nuclear reactor which can be easily assembled and transported by road, rail or air. Microreactors are 100 to 1,000

    Nuclear microreactor

    Nuclear microreactor

    Nuclear_microreactor

  • Boiling water reactor
  • Nuclear reactor where water boils in core

    electricity-generating nuclear reactor after the pressurized water reactor (PWR). BWRs are thermal neutron reactors, where water is thus used both as a coolant and as

    Boiling water reactor

    Boiling water reactor

    Boiling_water_reactor

  • Heat pipe-cooled reactor
  • Type of nuclear reactor cooled by heat pipes

    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 the

    Heat pipe-cooled reactor

    Heat_pipe-cooled_reactor

  • Nuclear meltdown
  • Reactor accident due to core overheating

    A nuclear meltdown (core meltdown, core melt accident, meltdown or partial core melt) is a severe nuclear reactor accident that results in core damage

    Nuclear meltdown

    Nuclear meltdown

    Nuclear_meltdown

  • Economic Simplified Boiling Water Reactor
  • Nuclear reactor design

    levels inside the reactor, keeping the nuclear fuel submerged in water and adequately cooled. In events where the reactor coolant pressure boundary remains

    Economic Simplified Boiling Water Reactor

    Economic Simplified Boiling Water Reactor

    Economic_Simplified_Boiling_Water_Reactor

  • Integral Molten Salt Reactor
  • Nuclear power plant design

    (the reactor and primary coolant is operated near normal atmospheric pressure), the inability to lose primary coolant (the fuel is the coolant), the

    Integral Molten Salt Reactor

    Integral Molten Salt Reactor

    Integral_Molten_Salt_Reactor

  • High-temperature gas-cooled reactor
  • Type of nuclear reactor that operates at high temperatures as part of normal operation

    All existing HTGR reactors use helium coolant. The reactor core can be either a "prismatic block" (reminiscent of a conventional reactor core) or a "pebble-bed"

    High-temperature gas-cooled reactor

    High-temperature gas-cooled reactor

    High-temperature_gas-cooled_reactor

  • BN-800 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

    BN-800 reactor

    BN-800_reactor

  • Steam-Generating Heavy Water Reactor
  • Nuclear power system

    moderator and normal "light" water as the coolant. The coolant boils in the reactor, like a boiling water reactor, and drives the power-extraction steam

    Steam-Generating Heavy Water Reactor

    Steam-Generating_Heavy_Water_Reactor

  • Prototype Fast Breeder Reactor
  • Indian fast breeder nuclear reactor design

    India. The indigenously developed reactor achieves a crucial second stage outlined in India's three stage nuclear power program building on the decades

    Prototype Fast Breeder Reactor

    Prototype_Fast_Breeder_Reactor

  • Nuclear reactor core
  • Part of a reactor containing the fuel

    A nuclear reactor core is the portion of a nuclear reactor containing the nuclear fuel components where the nuclear reactions take place and the heat

    Nuclear reactor core

    Nuclear reactor core

    Nuclear_reactor_core

  • RBMK
  • 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

    RBMK

    RBMK

  • Dual fluid reactor
  • German nuclear reactor design proposal with liquid metal cooling loops

    separation of liquid metallic fuel and coolant and by the provision for continuous fuel processing beyond Generation IV reactor concepts. The fuel can be a molten

    Dual fluid reactor

    Dual_fluid_reactor

  • UNGG reactor
  • Type of nuclear reactor

    The UNGG (Uranium Naturel Graphite Gaz) is an obsolete nuclear power reactor design developed in France. It was graphite moderated, cooled by carbon dioxide

    UNGG reactor

    UNGG reactor

    UNGG_reactor

  • Supercritical water reactor
  • Concept nuclear reactor whose water operates at supercritical pressure

    with a BWR, the turbine and reactor pressure vessel are in the same coolant loop, in contrast to a pressurized water reactor (PWR). Most SCWR plants are

    Supercritical water reactor

    Supercritical water reactor

    Supercritical_water_reactor

  • Reactor pressure vessel
  • Nuclear power plant component

    A reactor pressure vessel (RPV) in a nuclear power plant is the pressure vessel containing the nuclear reactor coolant, core shroud, and the reactor core

    Reactor pressure vessel

    Reactor pressure vessel

    Reactor_pressure_vessel

  • Experimental Breeder Reactor I
  • Breeder reactor in Idaho, US

    world's first breeder reactor. At 1:50 p.m. on December 20, 1951, it became one of the world's first electricity-generating nuclear power plants when it

    Experimental Breeder Reactor I

    Experimental Breeder Reactor I

    Experimental_Breeder_Reactor_I

  • Light water graphite reactor
  • graphite reactor (LWGR) is a design of nuclear reactor that uses purified graphite as a neutron moderator and light water (H2O) as a liquid coolant. Due to

    Light water graphite reactor

    Light_water_graphite_reactor

  • Bharat Small Modular Reactor
  • Indian nuclear reactor design

    The Bharat Small Modular Reactor, abbreviated as BSMR, is a small modular reactor design being developed in India by the Nuclear Power Corporation of India

    Bharat Small Modular Reactor

    Bharat Small Modular Reactor

    Bharat_Small_Modular_Reactor

  • Small modular reactor
  • Type of nuclear fission reactor

    A small modular reactor (SMR) is an emergent class of nuclear fission reactors with a rated electrical power of less than 300 megawatts (MWe), which use

    Small modular reactor

    Small modular reactor

    Small_modular_reactor

  • Nuclear power plant
  • Thermal power station where the heat source is a nuclear reactor

    a nuclear reactor heats the reactor coolant. The coolant may be water or gas, or even liquid metal, depending on the type of reactor. The reactor coolant

    Nuclear power plant

    Nuclear power plant

    Nuclear_power_plant

  • Aircraft Nuclear Propulsion
  • U.S. project 1946–1961

    section is instead directed into the nuclear reactor core. The air is heated further, thereby cooling the reactor. The air is then expanded through a turbine

    Aircraft Nuclear Propulsion

    Aircraft Nuclear Propulsion

    Aircraft_Nuclear_Propulsion

  • Leningrad Nuclear Power Plant
  • Nuclear power plant in Sosnovy Bor, Leningrad Oblast, Russia

    RBMK type of reactor. Despite its age, in 2012 and 2013 the Leningrad NPP took the third place in the annual contest for the Best Nuclear Power Plants

    Leningrad Nuclear Power Plant

    Leningrad Nuclear Power Plant

    Leningrad_Nuclear_Power_Plant

  • Advanced gas-cooled reactor
  • Type of British nuclear reactor

    gas-cooled reactors, using graphite as the neutron moderator and carbon dioxide as coolant. They have been the backbone of the UK's nuclear power generation

    Advanced gas-cooled reactor

    Advanced gas-cooled reactor

    Advanced_gas-cooled_reactor

  • Loss-of-coolant accident
  • Form of nuclear reactor failure

    loss-of-coolant accident (LOCA) is a mode of failure for a nuclear reactor in which the coolant inventory or coolant flow that removes heat from the reactor core

    Loss-of-coolant accident

    Loss-of-coolant_accident

  • X-10 Graphite Reactor
  • Decommissioned nuclear reactor in Tennessee, US

    The X-10 Graphite Reactor is a decommissioned nuclear reactor at Oak Ridge National Laboratory in Oak Ridge, Tennessee. Formerly known as the Clinton

    X-10 Graphite Reactor

    X-10 Graphite Reactor

    X-10_Graphite_Reactor

  • Pressurized heavy-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 frequently

    Pressurized heavy-water reactor

    Pressurized heavy-water reactor

    Pressurized_heavy-water_reactor

  • Nuclear power in Canada
  • Nuclear power in Canada is provided by 17 commercial reactors with a net capacity of 12.7 gigawatt (GW), producing a total of 84.6 terawatt-hours (TWh)

    Nuclear power in Canada

    Nuclear power in Canada

    Nuclear_power_in_Canada

  • List of small modular reactor designs
  • 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

  • Organic Moderated Reactor Experiment
  • Decommissioned nuclear reactor experiment in Idaho

    to 1963 to explore the use of hydrocarbons as coolant, moderator, and reflector materials in power reactor conditions. Such organic fluids are non-corrosive

    Organic Moderated Reactor Experiment

    Organic Moderated Reactor Experiment

    Organic_Moderated_Reactor_Experiment

  • Nuclear submarine
  • Submarine powered by a nuclear reactor

    A nuclear submarine is a submarine powered by a nuclear reactor, but not necessarily nuclear-armed. Nuclear submarines have considerable performance advantages

    Nuclear submarine

    Nuclear submarine

    Nuclear_submarine

  • Molten-Salt Reactor Experiment
  • Nuclear reactor, Oak Ridge 1965–1969

    nuclear cross section data. It was a test reactor simulating the neutronic "kernel" of a type of inherently safer epithermal thorium breeder reactor called

    Molten-Salt Reactor Experiment

    Molten-Salt Reactor Experiment

    Molten-Salt_Reactor_Experiment

  • BWRX-300
  • Small modular nuclear reactor design

    Boiling water reactors are nuclear technology that use ordinary light water as a nuclear reactor coolant. Like most boiling water reactors, the BWRX-300

    BWRX-300

    BWRX-300

  • Pebble-bed 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

    Pebble-bed reactor

    Pebble-bed_reactor

  • CANDU reactor
  • Canadian heavy water nuclear reactor design

    generated in the fuel of all nuclear fission reactors. In CANDU reactors, additional tritium is generated in the heavy water coolant and moderator due to neutron

    CANDU reactor

    CANDU reactor

    CANDU_reactor

  • Kori Nuclear Power Plant
  • Nuclear power plant in South Korea

    second-largest fully operational nuclear generating station by total reactor count and the number of currently operational reactors since 2016, after it exceeded

    Kori Nuclear Power Plant

    Kori Nuclear Power Plant

    Kori_Nuclear_Power_Plant

  • Olkiluoto Nuclear Power Plant
  • Nuclear power plant in Eurajoki, Finland

    cubic metres of radioactive coolant water leaked from the reactor into containment space rooms because a hatch in the reactor refueling pool had not been

    Olkiluoto Nuclear Power Plant

    Olkiluoto Nuclear Power Plant

    Olkiluoto_Nuclear_Power_Plant

  • Davis–Besse Nuclear Power Station
  • Nuclear power plant in Ottawa County, Ohio, United States

    reactor coolant to be reclaimed and reinjected into the reactor; the high pressure injection pumps that would reinject such reclaimed reactor coolant;

    Davis–Besse Nuclear Power Station

    Davis–Besse Nuclear Power Station

    Davis–Besse_Nuclear_Power_Station

  • Passive nuclear safety
  • Nuclear power safety method that does not require electrical power nor intervention

    Passive nuclear safety is a design approach for safety features, implemented in a nuclear reactor, that does not require any active intervention on the

    Passive nuclear safety

    Passive_nuclear_safety

  • Sodium–potassium alloy
  • Chemical compound

    reactor was destroyed in 2012. The United States' experimental SNAP-10A satellite, which was the first nuclear reactor in space, used NaK as coolant.

    Sodium–potassium alloy

    Sodium–potassium alloy

    Sodium–potassium_alloy

  • Sanmen Nuclear Power Station
  • Nuclear plant in Zhejiang, China

    to 2017. In January 2017 China National Nuclear Corporation (CNNC) announced that the final reactor coolant pump had been installed with start of operations

    Sanmen Nuclear Power Station

    Sanmen Nuclear Power Station

    Sanmen_Nuclear_Power_Station

  • Chernobyl Nuclear Power Plant
  • Decommissioned nuclear power plant in Ukraine

    reactor designs, such as the VVER pressurized water reactor. Originally named the Chernobyl Nuclear Power Plant of V. I. Lenin after the founding leader

    Chernobyl Nuclear Power Plant

    Chernobyl Nuclear Power Plant

    Chernobyl_Nuclear_Power_Plant

  • Sodium Reactor Experiment
  • Nuclear power plant in California, US

    California. The reactor operated from 1957 to 1964. On July 12, 1957 the Sodium Reactor Experiment became the first nuclear reactor in California to

    Sodium Reactor Experiment

    Sodium Reactor Experiment

    Sodium_Reactor_Experiment

  • Three Mile Island accident
  • 1979 nuclear accident in Pennsylvania

    Mile Island accident was a partial nuclear meltdown of the Unit 2 reactor (TMI-2) of the Three Mile Island Nuclear Generating Station, located on the

    Three Mile Island accident

    Three Mile Island accident

    Three_Mile_Island_accident

  • United States naval reactors
  • Classes of nuclear reactors used by the United States Navy

    119.519361°W / 46.565222; -119.519361 United States naval reactors are nuclear reactors used by the United States Navy aboard certain ships to generate

    United States naval reactors

    United States naval reactors

    United_States_naval_reactors

  • Greifswald Nuclear Power Plant
  • Decommissioned nuclear power plant located in Lubmin, Germany

    largest nuclear power station in East Germany before it was shut down shortly after the German reunification.[citation needed] The plant's reactors were

    Greifswald Nuclear Power Plant

    Greifswald Nuclear Power Plant

    Greifswald_Nuclear_Power_Plant

  • Soviet submarine K-19
  • Ballistic missile submarine

    to avoid a nuclear meltdown. Sacrificing their own lives, the engineering crew jury-rigged a secondary coolant system and kept the reactor from a meltdown

    Soviet submarine K-19

    Soviet submarine K-19

    Soviet_submarine_K-19

  • TOPAZ nuclear reactor
  • Soviet nuclear reactor for use in space

    The TOPAZ nuclear reactor is a lightweight nuclear reactor developed for long term space use by the Soviet Union. Cooled by liquid metal, it uses a high-temperature

    TOPAZ nuclear reactor

    TOPAZ_nuclear_reactor

  • Beloyarsk Nuclear Power Station
  • Nuclear power station in Russia

    typical enrichment in other Russian reactors is in the range of 3–4% 235U. BN-600 reactors use liquid sodium as a coolant. The station lacks a containment

    Beloyarsk Nuclear Power Station

    Beloyarsk Nuclear Power Station

    Beloyarsk_Nuclear_Power_Station

  • Nuclear and radiation accidents and incidents
  • Severe events involving radioactive materials

    causes harm. In a large nuclear reactor, a loss of coolant accident can damage the core: for example, at Three Mile Island Nuclear Generating Station a recent

    Nuclear and radiation accidents and incidents

    Nuclear and radiation accidents and incidents

    Nuclear_and_radiation_accidents_and_incidents

  • Nuclear power in the United States
  • United States, nuclear power is provided by 96 commercial reactors with a net capacity of 98 gigawatts (GW), with 65 pressurized water reactors and 31 boiling

    Nuclear power in the United States

    Nuclear power in the United States

    Nuclear_power_in_the_United_States

  • Liquid fluoride thorium reactor
  • Type of nuclear reactor that uses molten material as fuel

    steam turbine or closed-cycle gas turbine. Molten-salt-fueled reactors (MSRs) supply the nuclear fuel mixed into a molten salt. They should not be confused

    Liquid fluoride thorium reactor

    Liquid fluoride thorium reactor

    Liquid_fluoride_thorium_reactor

  • Generation IV 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

    Generation_IV_reactor

  • Heavy water
  • Form of water

    hydrogen isotope. Heavy water contains deuterium atoms and is used in nuclear reactors. Semiheavy water (HDO) is more common than pure heavy water, while

    Heavy water

    Heavy water

    Heavy_water

  • Vulcan Naval Reactor Test Establishment
  • UK Ministry of Defence in Scotland

    prototype nuclear reactors, trialling five different types of submarine reactor core. The site is located adjacent to the Dounreay civil nuclear site. When

    Vulcan Naval Reactor Test Establishment

    Vulcan Naval Reactor Test Establishment

    Vulcan_Naval_Reactor_Test_Establishment

  • Rolls-Royce PWR
  • Pressurised water reactor series

    The Rolls-Royce Pressurised Water Reactor (PWR) series has powered the Royal Navy's nuclear submarines since the Valiant class, commissioned in 1966.

    Rolls-Royce PWR

    Rolls-Royce_PWR

  • Temelín Nuclear Power Station
  • Power plant in the Czech Republic

    Coolant outlet temperature: approx. 320 °C (608F) Coolant flow through reactor: 23.5 m3/s Number per reactor unit: 4 Steam delivered per one generator: 1,470

    Temelín Nuclear Power Station

    Temelín Nuclear Power Station

    Temelín_Nuclear_Power_Station

  • RELAP5-3D
  • Simulates a nuclear reactor's coolant system and core

    a nuclear reactor's coolant system and the reactor core for various operational transients and postulated accidents that might occur in a nuclear reactor

    RELAP5-3D

    RELAP5-3D

    RELAP5-3D

  • Piqua Nuclear Power Facility
  • Nuclear reactor in Ohio, United States

    The Piqua Nuclear Power Facility was an organic-cooled and moderated nuclear reactor which operated just outside the southern city limits of Piqua, Ohio

    Piqua Nuclear Power Facility

    Piqua Nuclear Power Facility

    Piqua_Nuclear_Power_Facility

  • Corium (nuclear reactor)
  • Material in core during nuclear meltdown

    created in a nuclear reactor core during a nuclear meltdown accident. Resembling lava in consistency, it consists of a mixture of nuclear fuel, fission

    Corium (nuclear reactor)

    Corium (nuclear reactor)

    Corium_(nuclear_reactor)

  • Graphite-moderated reactor
  • Type of nuclear reactor

    is a nuclear reactor that uses carbon as a neutron moderator, which allows natural uranium to be used as nuclear fuel. The first artificial nuclear reactor

    Graphite-moderated reactor

    Graphite-moderated reactor

    Graphite-moderated_reactor

  • Nikolai Vladimirovich Zateyev
  • Soviet submarine commander

    submarine K-19 in July 1961 during the Hotel class submarine's nuclear-reactor coolant leak. Zateyev and the actions of his crew managed to avert disaster

    Nikolai Vladimirovich Zateyev

    Nikolai_Vladimirovich_Zateyev

  • A2W reactor
  • Naval nuclear reactor

    The A2W reactor is a naval nuclear reactor used by the United States Navy to provide electricity generation and propulsion on warships. The A2W designation

    A2W reactor

    A2W_reactor

  • Dragon reactor
  • UK experimental HTR, operated from 1965 to 1976

    construction and operation of experimental and research nuclear reactors. Dragon used helium gas as the coolant and graphite as the neutron moderator. Fuel was

    Dragon reactor

    Dragon reactor

    Dragon_reactor

  • Nuclear power in the United Kingdom
  • domestically developed Magnox and their successor AGR reactors with graphite moderator and CO2 coolant but the last of those are nearing the end of their

    Nuclear power in the United Kingdom

    Nuclear_power_in_the_United_Kingdom

  • Fukushima nuclear accident
  • 2011 nuclear accident in Japan

    the heat exchanger by the reactor pressure, and the condensed coolant would be fed back into the vessel by gravity. Each reactor was initially designed to

    Fukushima nuclear accident

    Fukushima nuclear accident

    Fukushima_nuclear_accident

  • Natural nuclear fission 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

  • Residual heat removal system
  • Safety system in nuclear reactors

    heat Nuclear reactor coolant Light-water reactor Auxiliary feedwater Nuclear reactor safety system Boiling water reactor safety systems Reactor Concepts

    Residual heat removal system

    Residual_heat_removal_system

  • Breeder 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

    Breeder reactor

    Breeder_reactor

  • Gas-cooled fast reactor
  • Type of nuclear reactor cooled by a gas

    which allows for better coolant circulation than traditional fuel assemblies. The reactors are intended for use in nuclear power plants to produce electricity

    Gas-cooled fast reactor

    Gas-cooled fast reactor

    Gas-cooled_fast_reactor

  • VM reactor
  • Russian nuclear pressurized water reactors

    The VM reactor (Russian: реактор ВМ) is type of various series of nuclear pressurized water reactors (PWR). They were used singly or in pairs to power

    VM reactor

    VM_reactor

  • Dhruva reactor
  • Radioisotope production reactor

    The Dhruva reactor is India's largest nuclear research reactor. It was the first nuclear reactor in Asia proper. Located in the Mumbai suburb of Trombay

    Dhruva reactor

    Dhruva_reactor

  • BN-1200 reactor
  • Fast breeder nuclear reactor under development in Russia

    The BN-1200 reactor is a sodium-cooled fast breeder reactor project, under development by OKBM Afrikantov at Beloyarsk Nuclear Power Station in Zarechny

    BN-1200 reactor

    BN-1200 reactor

    BN-1200_reactor

  • FLiBe
  • Chemical compound

    It is both a nuclear reactor coolant and solvent for fertile or fissile material. It served both purposes in the Molten-Salt Reactor Experiment (MSRE)

    FLiBe

    FLiBe

    FLiBe

  • Advanced Test Reactor
  • Idaho National Laboratory research neutron source

    environment while accelerating the nuclear conditions. The ATR is a pressurized light water reactor (LWR), using water as both coolant and moderator. The core is

    Advanced Test Reactor

    Advanced Test Reactor

    Advanced_Test_Reactor

  • Cernavodă Nuclear Power Plant
  • Nuclear power plant in Romania

    reactor technology from AECL, using heavy water produced at Drobeta-Turnu Severin as its neutron moderator and as its coolant agent. By using nuclear

    Cernavodă Nuclear Power Plant

    Cernavodă Nuclear Power Plant

    Cernavodă_Nuclear_Power_Plant

  • Gas core reactor rocket
  • Rocket-propelled by exhausted coolant of a gas-cooled nuclear reactor

    reactor rockets are a conceptual type of rocket that is propelled by the exhausted coolant of a gaseous fission reactor. The nuclear fission reactor core

    Gas core reactor rocket

    Gas_core_reactor_rocket

  • Advanced heavy-water reactor
  • Indian nuclear reactor design

    PHWRs the tubes are vertical rather than horizontal. The reactor core contains 452 coolant channels, of which 424 contain a fuel cluster. Each cluster

    Advanced heavy-water reactor

    Advanced_heavy-water_reactor

  • List of commercial nuclear reactors
  • 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

  • FLiNaK
  • FLiNaK also could see potential use as a coolant in the very high temperature reactor, a type of nuclear reactor. FLiNaK salt was researched heavily during

    FLiNaK

    FLiNaK

    FLiNaK

  • Nuclear navy
  • Navy with ships powered by nuclear energy

    unrelated to their reactor plants and still lie on the Atlantic sea floor. [citation needed] K-8 (1960; November-class submarine; loss of coolant) K-19 (1961;

    Nuclear navy

    Nuclear_navy

  • Cooling system
  • Topics referred to by the same term

    internal combustion engine cooling Cooling systems for nuclear powerplants, using nuclear reactor coolant Cooling systems for computer equipment, see computer

    Cooling system

    Cooling_system

  • Scram
  • 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

    Scram

    Scram

  • SLOWPOKE reactor
  • Family of nuclear research reactors

    Kritical Experiment) is a family of low-energy, tank-in-pool type nuclear research reactors designed by Atomic Energy of Canada Limited (AECL) beginning in

    SLOWPOKE reactor

    SLOWPOKE reactor

    SLOWPOKE_reactor

Searches for online references containing NUCLEAR REACTOR-COOLANT

NUCLEAR REACTOR-COOLANT

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NUCLEAR REACTOR-COOLANT

  • Hector
  • Boy/Male

    Spanish American Shakespearean Greek Latin

    Hector

    Tenacious.

    Hector

  • Moujid
  • Boy/Male

    Indian

    Moujid

    Creator

    Moujid

  • Ector
  • Boy/Male

    Arthurian Legend

    Ector

    Father of Arthur.

    Ector

  • Clear
  • Surname or Lastname

    English

    Clear

    English : probably a habitational name from clere, a component of several place names in north Hampshire (Highclere, Burghclere, Kingsclere). This is of uncertain origin, probably from a Celtic stream name meaning ‘bright’ (cognate with Latin clarus ‘clear’, ‘bright’).English and Irish : variant of Clare.Translation of German Klar 1.

    Clear

  • Duclea
  • Girl/Female

    Latin

    Duclea

    Sweet.

    Duclea

  • Sanjaan | سنجان
  • Boy/Male

    Muslim

    Sanjaan | سنجان

    Creator

    Sanjaan | سنجان

  • Rachita
  • Girl/Female

    Assamese, Gujarati, Hindu, Indian, Kannada, Malayalam, Marathi, Rajasthani, Sanskrit, Sindhi, Tamil, Telugu

    Rachita

    Creator

    Rachita

  • HECTOR
  • Male

    Arthurian

    HECTOR

    , sir Hector de Maris; (defender).

    HECTOR

  • ECTOR
  • Male

    Arthurian

    ECTOR

    , defender.

    ECTOR

  • Sanjan | ஸஂஜந
  • Boy/Male

    Tamil

    Sanjan | ஸஂஜந

    Creator

    Sanjan | ஸஂஜந

  • Actor
  • Boy/Male

    Latin

    Actor

    Son of Azeus.

    Actor

  • Hector
  • Boy/Male

    American, Australian, British, Chinese, Christian, Danish, Dutch, English, French, German, Greek, Italian, Latin, Portuguese, Shakespearean, Spanish

    Hector

    Steadfast; Anchor; Holds Fast; Star; Coined from Esther Vanhomrigh; Tenacious; Defend; Hold Fast; Coined from Esther Vanho

    Hector

  • Rachiyata
  • Girl/Female

    Hindu

    Rachiyata

    Creator

    Rachiyata

  • Rachiyata | ரசியதா
  • Girl/Female

    Tamil

    Rachiyata | ரசியதா

    Creator

    Rachiyata | ரசியதா

  • Hector
  • Boy/Male

    Christian & English(British/American/Australian)

    Hector

    Steadfast

    Hector

  • Moujid |
  • Boy/Male

    Muslim

    Moujid |

    Creator

    Moujid |

  • Rachika
  • Girl/Female

    Hindu, Indian, Malayalam, Marathi, Tamil

    Rachika

    Creator

    Rachika

  • Hector
  • Surname or Lastname

    Scottish

    Hector

    Scottish : Anglicized form of the Gaelic personal name Eachann (earlier Eachdonn, already confused with Norse Haakon), composed of the elements each ‘horse’ + donn ‘brown’.English : found in Yorkshire and Scotland, where it may derive directly from the medieval personal name. According to medieval legend, Britain derived its name from being founded by Brutus, a Trojan exile, and Hector was occasionally chosen as a personal name, as it was the name of the Trojan king’s eldest son. The classical Greek name, Hektōr, is probably an agent derivative of Greek ekhein ‘to hold back’, ‘hold in check’, hence ‘protector of the city’.German, French, and Dutch : from the personal name (see 2 above). In medieval Germany, this was a fairly popular personal name among the nobility, derived from classical literature. It is a comparatively rare surname in France.

    Hector

  • HECTOR
  • Male

    English

    HECTOR

     Anglicized form of Scottish Gaelic Eachann, HECTOR means "brown horse." Compare with another form of Hector.

    HECTOR

  • Vidhaath | விதாத
  • Boy/Male

    Tamil

    Vidhaath | விதாத

    Creator

    Vidhaath | விதாத

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