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GENERATION IV-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

    Generation IV reactor

    Generation_IV_reactor

  • Generation II reactor
  • Design classification for nuclear reactors

    A generation II reactor is a design classification for a nuclear reactor, and refers to the class of commercial reactors built until the end of the 1990s

    Generation II reactor

    Generation II reactor

    Generation_II_reactor

  • Generation III reactor
  • Class of nuclear reactors with improved safety over its predecessors

    Generation III reactors, or Gen III reactors, are a class of nuclear reactors designed to succeed Generation II reactors, incorporating evolutionary improvements

    Generation III reactor

    Generation III reactor

    Generation_III_reactor

  • Molten-salt reactor
  • Type of nuclear reactor cooled by molten material

    power plant using a thorium fuel cycle in a breeder reactor. Increased research into Generation IV reactor designs renewed interest in the 21st century with

    Molten-salt reactor

    Molten-salt reactor

    Molten-salt_reactor

  • Nuclear reactor
  • Device for controlled nuclear reactions

    from the reactor pressure vessel to the turbine. Supercritical water reactor (SCWR) SCWRs are a Generation IV reactor concept where the reactor is operated

    Nuclear reactor

    Nuclear reactor

    Nuclear_reactor

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

    The lead-cooled reactor design has been proposed as a generation IV reactor. Plans for future implementation of this type of reactor include modular arrangements

    Lead-cooled fast reactor

    Lead-cooled fast reactor

    Lead-cooled_fast_reactor

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

    reactors of the Generation IV International Forum. The Dual Fluid Reactor is classified by its developers as the first Generation V nuclear reactor,

    Dual fluid reactor

    Dual_fluid_reactor

  • Supercritical water 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

    Supercritical water reactor

    Supercritical_water_reactor

  • Fourth generation
  • Topics referred to by the same term

    Fourth generation warfare, conflict characterized by a blurring of the lines between war and politics, soldier and civilian Generation IV reactor, a set

    Fourth generation

    Fourth_generation

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

    development of the HTGR is the Generation IV very-high-temperature reactor (VHTR). The use of a high-temperature, gas-cooled reactor for power production was

    High-temperature gas-cooled reactor

    High-temperature gas-cooled reactor

    High-temperature_gas-cooled_reactor

  • Gas-cooled fast reactor
  • 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

    Gas-cooled fast reactor

    Gas-cooled_fast_reactor

  • Integral fast reactor
  • Nuclear reactor design

    IFR was a sodium-cooled fast reactor (SFR) is its closest surviving fast breeder reactor, a type of Generation IV reactor. The U.S. Department of Energy

    Integral fast reactor

    Integral fast reactor

    Integral_fast_reactor

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

    Teplonositelem, 'Naturally Safe Lead-Cooled Fast Reactor') is a generation IV lead-cooled fast nuclear reactor. BREST-300 model is under construction since

    BREST (reactor)

    BREST_(reactor)

  • Nuclear power in China
  • China is developing several generation IV reactor designs. In December 2023, China’s HTR-PM, a high-temperature gas-cooled reactor at Shidao Bay, entered commercial

    Nuclear power in China

    Nuclear power in China

    Nuclear_power_in_China

  • HTR-PM
  • Chinese small modular nuclear reactor

    a Chinese small modular nuclear reactor. It is a high-temperature gas-cooled (HTGR) pebble-bed generation IV reactor evolved from the HTR-10 prototype

    HTR-PM

    HTR-PM

  • BN-800 reactor
  • Russian fast breeder nuclear reactor, operating since 2016

    portal Russia portal Generation IV reactor BN-Reactor BN-350 reactor – Deactivated fast breeder reactor in Aktau, Kazakhstan BN-600 reactor – Russian sodium-cooled

    BN-800 reactor

    BN-800 reactor

    BN-800_reactor

  • Aurora nuclear reactor
  • 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

    Aurora_nuclear_reactor

  • ALFRED (nuclear reactor)
  • Planned lead-cooled reactor demonstrator

    Fuel: MOX or Uranium (20%) Fast breeder reactor Fast neutron reactor Generation IV reactor "Generation IV & SMR". ansaldoenergia.com. "Nuclearelectrica

    ALFRED (nuclear reactor)

    ALFRED (nuclear reactor)

    ALFRED_(nuclear_reactor)

  • Fast-neutron reactor
  • Nuclear reactor where fast neutrons maintain a fission chain reaction

    reactor Gas-cooled fast reactor Generation IV reactor Lead-cooled fast reactor Nuclear fuel cycle Sodium-cooled fast reactor Thermal-neutron reactor With

    Fast-neutron reactor

    Fast-neutron reactor

    Fast-neutron_reactor

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

    since 2016 BREST-300 - generation IV lead-cooled fast reactor, in construction since 2020 Generation IV reactor "Fast Neutron Reactors". world-nuclear.org

    BN-1200 reactor

    BN-1200 reactor

    BN-1200_reactor

  • Pebble-bed reactor
  • Type of very-high-temperature reactor

    considered a type of very-high-temperature reactor (VHTR), one of the six classes of nuclear reactors in the Generation IV initiative. The basic design features

    Pebble-bed reactor

    Pebble-bed reactor

    Pebble-bed_reactor

  • Thorium-based nuclear power
  • Nuclear energy extracted from thorium isotopes

    (ADS) – Type of nuclear reactor designPages displaying short descriptions of redirect targets Generation IV reactor – New nuclear reactor technologies under

    Thorium-based nuclear power

    Thorium-based nuclear power

    Thorium-based_nuclear_power

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

    "Chapter 5: Sodium-cooled Fast Reactors (SFRs)". In Pioro, Igor L. (ed.). Handbook of Generation IV Nuclear Reactors (2nd ed.). Woodhead Publishing.

    Sodium-cooled fast reactor

    Sodium-cooled fast reactor

    Sodium-cooled_fast_reactor

  • TMSR-LF1
  • Molten salt reactor prototype

    detected, indicating successful nuclear breeding. The TMSR-LF1 is a Generation IV reactor constructed with the following specifications: Thermal power: 2

    TMSR-LF1

    TMSR-LF1

    TMSR-LF1

  • Gen4 Energy
  • US company, 2012 to 2018

    conventional Generation IV reactor design: a uranium nitride fueled, lead-bismuth cooled reactor. They believed that using a liquid-metal-cooled fast reactor would

    Gen4 Energy

    Gen4 Energy

    Gen4_Energy

  • Liquid metal cooled reactor
  • Nuclear reactor where the coolant is liquid metal

    metal. Liquid metal cooled reactors were first adapted for breeder reactor power generation. They have also been used to power nuclear submarines. Due to their

    Liquid metal cooled reactor

    Liquid_metal_cooled_reactor

  • International Reactor Innovative and Secure
  • International Reactor Innovative and Secure (IRIS) is a Generation IV reactor design made by an international team of companies, laboratories, and universities

    International Reactor Innovative and Secure

    International_Reactor_Innovative_and_Secure

  • List of small modular reactor designs
  • pebble-bed generation IV reactor partly based on the earlier HTR-10 prototype reactor. The reactor unit has a thermal capacity of 250 MW, and two reactors are

    List of small modular reactor designs

    List_of_small_modular_reactor_designs

  • Breeder reactor
  • Nuclear reactor generating more fissile material than it consumes

    and BM-40A reactors as well as the SVBR-100 reactor. Three of the proposed generation IV reactor types are FBRs: Gas-cooled fast reactor cooled by helium

    Breeder reactor

    Breeder reactor

    Breeder_reactor

  • Subcritical reactor
  • Device that achieves nuclear fission without triggering a chain reaction

    part of a light water reactor design, other proposals have been made that incorporate an ADS into other generation IV reactor concepts.[citation needed]

    Subcritical reactor

    Subcritical_reactor

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

    The Prototype Fast Breeder Reactor (PFBR) is a 500 MWe pool type sodium-cooled, fast breeder reactor commissioned at the same site as the Madras Atomic

    Prototype Fast Breeder Reactor

    Prototype_Fast_Breeder_Reactor

  • OK-650 reactor
  • Nuclear fission reactor

    detection of leaks, were included, along with newer-generation emergency cooling systems for the main reactor core. It was developed by OKBM Afrikantov. "AKULA

    OK-650 reactor

    OK-650_reactor

  • Lead-bismuth eutectic
  • Alloy of lead and bismuth used as a coolant in nuclear reactors

    coolant in some nuclear reactors, and is a proposed coolant for the lead-cooled fast reactor, part of the Generation IV reactor initiative. It has a melting

    Lead-bismuth eutectic

    Lead-bismuth_eutectic

  • Advanced heavy-water reactor
  • 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

    Advanced_heavy-water_reactor

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

    reactor is expected to operate up until 2040. Energy portal Nuclear technology portal Russia portal Generation IV reactor BN-Reactor BN-350 reactor –

    BN-600 reactor

    BN-600 reactor

    BN-600_reactor

  • BN-Reactor
  • Nuclear technology portal Russia portal Generation IV reactor BN-350 reactor BN-600 reactor BN-800 reactor BN-1200 reactor Klepikov, A Kh, Tazhibayeva, I L,

    BN-Reactor

    BN-Reactor

  • Newcleo
  • Nuclear energy company

    cooperate on advanced reactors". World Nuclear News. Baldoni, Mattia (10 April 2024). "CEA and newcleo to Partner On Generation IV Reactors". "newcleo, Fincantieri

    Newcleo

    Newcleo

    Newcleo

  • Nuclear power
  • Power generated from nuclear reactions

    already retired. Research into advanced generation IV reactor types was officially started by the Generation IV International Forum (GIF) based on eight

    Nuclear power

    Nuclear power

    Nuclear_power

  • Southern Company Services
  • develop Generation IV reactor designs. One of two beneficiaries, Southern Company Services will use the funding to develop a Molten Chloride Fast Reactor, a

    Southern Company Services

    Southern_Company_Services

  • CFR-600
  • Nuclear reactor in Fujian province, China

    is a generation IV demonstration project by the China National Nuclear Corporation (CNNC). Construction started in late 2017. These first reactor started

    CFR-600

    CFR-600

  • VM reactor
  • Russian nuclear pressurized water reactors

    (Echo), and Project 627 Кит (November) first-generation submarines. It was a pressurized water reactor (PWR), using 21% enriched uranium-235 fuel to

    VM reactor

    VM_reactor

  • PRISM (reactor)
  • Nuclear reactor design

    Vernova Hitachi Nuclear Energy (GVH). The S-PRISM represents GVH's Generation IV reactor solution to closing the nuclear fuel cycle and is also part of its

    PRISM (reactor)

    PRISM (reactor)

    PRISM_(reactor)

  • Reactor protection system
  • Nuclear safety and security components in a nuclear power plant

    reactor (evolutionary improvements of existing designs 1996–present) Generation IV reactor (technologies still under development unknown start date, possibly

    Reactor protection system

    Reactor_protection_system

  • Light-water reactor
  • Type of nuclear reactor that uses normal water

    SCWR remains hypothetical as of 2009; it is a Generation IV design that is still a light-water reactor, but it is only partially moderated by light water

    Light-water reactor

    Light-water reactor

    Light-water_reactor

  • Reactor-grade plutonium
  • plutonium as time goes on. Generation II thermal-neutron reactors (today's most numerous nuclear power stations) can reuse reactor-grade plutonium only to

    Reactor-grade plutonium

    Reactor-grade_plutonium

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

    inside the Petten high-flux reactor was underway. Generation IV reactor Thorium-based nuclear power List of small nuclear reactor designs Passive nuclear

    Liquid fluoride thorium reactor

    Liquid fluoride thorium reactor

    Liquid_fluoride_thorium_reactor

  • Kemmerer Power Station
  • Nuclear power station located near Kemmerer, WY

    will construct the rotatable plug assembly. Generation IV reactor Nuclear power in the United States Pequeño IV, Antonio (2024-03-19). "TerraPower: What

    Kemmerer Power Station

    Kemmerer Power Station

    Kemmerer_Power_Station

  • Small modular 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

    Small modular reactor

    Small_modular_reactor

  • RBMK
  • Type of Soviet nuclear power reactor

    an early Generation II reactor and the oldest commercial reactor design still in wide operation. Certain aspects of the original RBMK reactor design had

    RBMK

    RBMK

    RBMK

  • Boiling water 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

    Boiling water reactor

    Boiling_water_reactor

  • Polonium-210
  • Isotope of polonium

    reactors cooled with lead-bismuth eutectic rather than pure lead. However, given the eutectic properties of this alloy, some proposed Generation IV reactor

    Polonium-210

    Polonium-210

    Polonium-210

  • OK-550 reactor
  • Nuclear fission reactor

    Лира (Lira or Alfa in NATO designation) fourth generation submarines. It is a liquid metal cooled reactor (LMR), using highly enriched uranium-235 fuel

    OK-550 reactor

    OK-550 reactor

    OK-550_reactor

  • Nuclear fusion–fission hybrid
  • Proposed uses of generating power from nuclear fission and fusion

    Generation IV reactor, next generation fission reactor designs claiming much higher safety, and greatly increased fuel use efficiency. Integral Fast Reactor, a

    Nuclear fusion–fission hybrid

    Nuclear_fusion–fission_hybrid

  • GE Vernova Hitachi Nuclear Energy
  • American nuclear technology company

    boiling water reactor (BWR). The research into the project continued for the next 50 years resulting in the production of 6 different generations of BWRs.

    GE Vernova Hitachi Nuclear Energy

    GE_Vernova_Hitachi_Nuclear_Energy

  • CANDU reactor
  • 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

    CANDU reactor

    CANDU_reactor

  • MBIR
  • Fast neutron research reactor

    portal Generation IV reactor BN-800 reactorgeneration IV sodium-cooled fast breeder reactor, operational since 2016 BREST-300 – generation IV lead-cooled

    MBIR

    MBIR

  • Economic Simplified Boiling Water Reactor
  • Nuclear reactor design

    Boiling Water Reactor (ESBWR) is a passively safe generation III+ reactor design derived from its predecessor, the Simplified Boiling Water Reactor (SBWR) and

    Economic Simplified Boiling Water Reactor

    Economic Simplified Boiling Water Reactor

    Economic_Simplified_Boiling_Water_Reactor

  • General Atomics
  • American defense and energy company

    GA-ASI. General Atomics is also developing a Generation IV reactor design, the Gas Turbine Modular Helium Reactor (GT-MHR). In 2010, General Atomics presented

    General Atomics

    General_Atomics

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

    an improved Generation II gas cooled reactor. In France, the UNGG was replaced by the pressurized water reactor (PWR). Gas-cooled reactor types include:

    Gas-cooled reactor

    Gas-cooled_reactor

  • Advanced boiling water 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

    Advanced_boiling_water_reactor

  • The Alvin Weinberg Foundation
  • 2000 until 2005, was its last Director. Generation IV reactor Liquid fluoride thorium reactor Molten salt reactor Thorium-based nuclear power Ruz, Camila

    The Alvin Weinberg Foundation

    The Alvin Weinberg Foundation

    The_Alvin_Weinberg_Foundation

  • Next Generation Nuclear Plant
  • Cancelled American reactor project

    A Next Generation Nuclear Plant (NGNP) is a specific proposed generation IV very-high-temperature reactor (VHTR) that could be coupled to a neighboring

    Next Generation Nuclear Plant

    Next Generation Nuclear Plant

    Next_Generation_Nuclear_Plant

  • Mitsubishi Heavy Industries
  • Japanese multinational corporation

    likely to be the most aggressive corporate venture into FBR and Generation IV reactor technology. In 2011, Mitsubishi launched the Type-J gas turbines

    Mitsubishi Heavy Industries

    Mitsubishi Heavy Industries

    Mitsubishi_Heavy_Industries

  • Urenco Group
  • European nuclear fuel company

    which some Generation IV reactors need for fuel. In 2025 Urenco signed the first commercial contract to supply HALEU to Generation IV reactors. Urenco plans

    Urenco Group

    Urenco_Group

  • Closed-cycle gas turbine
  • Gas turbine using a working fluid in a closed loop

    modular reactor was intended to be coupled with a helium CCGT. Future nuclear (Generation IV reactors) may employ CCGT for power generation, e.g. Flibe

    Closed-cycle gas turbine

    Closed-cycle gas turbine

    Closed-cycle_gas_turbine

  • CATHARE (software)
  • CATHARE code thermal-hydraulics simulation software

    in most reactor design projects in the French nuclear sector, whether for Generation III power reactors (EPR, NUWARD), Generation IV reactors (sodium-cooled

    CATHARE (software)

    CATHARE_(software)

  • List of commercial nuclear reactors
  • ASEA-ATOM Gen IV, BWR-3000, BWR 75. The full reactor model name is ASEA-ATOM Gen I. The full reactor model name is ASEA-ATOM Gen II. The full reactor model name

    List of commercial nuclear reactors

    List_of_commercial_nuclear_reactors

  • 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

  • Shidao Bay Nuclear Power Plant
  • Nuclear plant in Shandong, China

    criticality of a generation IV commercial nuclear power plant, in September 2021. Reactor two achieved first criticality in November 2021. Reactor one was connected

    Shidao Bay Nuclear Power Plant

    Shidao_Bay_Nuclear_Power_Plant

  • EPR (nuclear reactor)
  • Third-generation pressurised water nuclear reactor design

    The EPR is a Generation III+ pressurised water reactor design. It has been designed and developed mainly by Framatome (part of Areva between 2001 and

    EPR (nuclear reactor)

    EPR (nuclear reactor)

    EPR_(nuclear_reactor)

  • BM-40A reactor
  • Russian nuclear fission reactor for use in submarines

    Лира (Lira or Alfa in NATO designation) fourth generation submarines. It is a liquid metal cooled reactor (LMR), using highly enriched uranium-235 fuel

    BM-40A reactor

    BM-40A reactor

    BM-40A_reactor

  • Jōyō (nuclear reactor)
  • Test sodium-cooled fast reactor in Ōarai, Ibaraki, Japan

    techniques in the experimental fast reactor Joyo. / In-pile testing and instrumentation for development of generation-IV fuels and materials. Proceedings

    Jōyō (nuclear reactor)

    Jōyō (nuclear reactor)

    Jōyō_(nuclear_reactor)

  • ASTRID (reactor)
  • Cancelled fast breeder reactor in France

    Sodium Technological Reactor for Industrial Demonstration) was a proposal for a 600 MW sodium-cooled fast breeder reactor (Generation IV), proposed by the

    ASTRID (reactor)

    ASTRID (reactor)

    ASTRID_(reactor)

  • Leslie Dewan
  • American nuclear engineer

    Transatomic Power was founded to design and develop a molten salt reactor (Generation IV reactor) to generate clean and low-cost nuclear power. In December 2012

    Leslie Dewan

    Leslie Dewan

    Leslie_Dewan

  • MYRRHA
  • Design project of a nuclear reactor coupled to a proton accelerator

    neutron reactor Gas-cooled fast reactor Generation IV reactor Integral Fast Reactor Sodium-cooled fast reactor Mueller, Alex C. (2013). "Transmutation

    MYRRHA

    MYRRHA

    MYRRHA

  • VVER
  • Soviet / Russian nuclear reactor type

    nuclear coolant and the neutron moderator, in a reactor intended for energy generation. The idea of such a reactor was proposed[when?] at the Kurchatov Institute

    VVER

    VVER

    VVER

  • Online refuelling
  • number of planned reactor designs which include provision for online refuelling, including pebble-bed and molten salt Generation IV reactors. "Nuclear power

    Online refuelling

    Online refuelling

    Online_refuelling

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

    100 reactors began operations, 107 were retired. An international coalition is advancing research and development on six Generation IV nuclear reactor technologies

    Nuclear power plant

    Nuclear power plant

    Nuclear_power_plant

  • Zhaoyuan Nuclear Power Plant
  • Nuclear plant in Shandong, China

    portal Nuclear power in China List of commercial nuclear reactors § China Generation IV reactor "Zhaoyuan nuclear power plant". Global Energy Monitor. 25

    Zhaoyuan Nuclear Power Plant

    Zhaoyuan_Nuclear_Power_Plant

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

    advanced gas-cooled reactor (AGR) is a type of nuclear reactor designed and operated by the United Kingdom. These are the second generation of British gas-cooled

    Advanced gas-cooled reactor

    Advanced gas-cooled reactor

    Advanced_gas-cooled_reactor

  • Sulfur–iodine cycle
  • Thermochemical process used to produce hydrogen

    Test Reactor, a reactor which reached first criticality in 1998, JAEA have the aspiration of using further nuclear very high-temperature generation IV reactors

    Sulfur–iodine cycle

    Sulfur–iodine cycle

    Sulfur–iodine_cycle

  • TEM (nuclear propulsion)
  • Nuclear propulsion project

    exploration. The first reactor tests are scheduled for the early 2020s; as of May 2020, the first orbital flight test of the reactor is planned for no earlier

    TEM (nuclear propulsion)

    TEM (nuclear propulsion)

    TEM_(nuclear_propulsion)

  • Pandora's Promise
  • 2013 American film

    nuclear reactors generation III reactor generation IV reactor integral fast reactor Experimental Breeder Reactor I Experimental Breeder Reactor II small

    Pandora's Promise

    Pandora's_Promise

  • Outline of nuclear technology
  • Overview of and topical guide to nuclear technology

    reactor Fast neutron reactor Gas-cooled fast reactor Generation IV reactor Integral Fast Reactor Lead-cooled fast reactor Liquid-metal-cooled reactor

    Outline of nuclear technology

    Outline_of_nuclear_technology

  • George Monbiot
  • English writer and political activist (born 1963)

    waste production; he contrasted this with two generation IV reactor concepts: "if integral fast reactors were deployed, the UK's stockpile of nuclear waste

    George Monbiot

    George Monbiot

    George_Monbiot

  • RITM-200
  • Nuclear reactor

    The RITM-200 is an integrated Generation III+ pressurized water reactor developed by OKBM Afrikantov and designed to produce 55 MWe. The design is an

    RITM-200

    RITM-200

  • OK-150 reactor
  • Soviet marine nuclear reactor

    The OK-150 reactor (1st generation) and its successor, the OK-900 reactor (2nd generation) are Soviet marine nuclear reactors used to power ships at sea

    OK-150 reactor

    OK-150_reactor

  • ClearPath Foundation
  • American environmental organization

    modular reactors and generation IV reactors. In February 2016, ClearPath's CEO Jay Faison proposed developing "super-competitive, next-generation" nuclear

    ClearPath Foundation

    ClearPath_Foundation

  • Inherent safety
  • Situation with a low worst-case danger level

    these are much more complex than the Dow F & E Index. Fail-safe Generation IV reactor Intrinsic safety Passive nuclear safety Prevention through design

    Inherent safety

    Inherent_safety

  • TRISO fuel
  • Type of nuclear fuel

    for use in the very-high-temperature reactor concept, one of the six classes of reactor designs in the Generation IV initiative that is attempting to reach

    TRISO fuel

    TRISO fuel

    TRISO_fuel

  • Economics of nuclear power
  • different electricity generation sources Generation IV reactor – New nuclear reactor technologies under development Light Water Reactor Sustainability Program –

    Economics of nuclear power

    Economics of nuclear power

    Economics_of_nuclear_power

  • Terrestrial Energy
  • Nuclear technology company developing the Integral Molten Salt Reactor

    technology company working on Generation IV nuclear technology. The company is developing an Integral Molten Salt Reactor (IMSR). By late 2017, it was

    Terrestrial Energy

    Terrestrial_Energy

  • Nuclear power in Belgium
  • contribute to Generation IV reactor research through the MYRRHA project. There are two commercial nuclear power plants operational with seven reactors: Doel Nuclear

    Nuclear power in Belgium

    Nuclear_power_in_Belgium

  • Graphite-moderated 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

    Graphite-moderated reactor

    Graphite-moderated_reactor

  • History of France's civil nuclear program
  • future solutions is concentrated on Generation IV reactors and nuclear fusion. Meanwhile, shutting down reactors presents new challenges. President Macron

    History of France's civil nuclear program

    History_of_France's_civil_nuclear_program

  • Infrastructure Investment and Jobs Act
  • Legislation of the 117th United States Congress

    lead. The largest single energy project to receive Act funds was a Generation IV reactor in Kemmerer, Wyoming by the nuclear fission startup TerraPower.

    Infrastructure Investment and Jobs Act

    Infrastructure Investment and Jobs Act

    Infrastructure_Investment_and_Jobs_Act

  • Shelley Moore Capito
  • American politician (born 1953)

    Advanced Nuclear for Clean Energy (ADVANCE) Act of 2023 in support of generation IV reactor technology and nuclear development in general. The ADVANCE Act was

    Shelley Moore Capito

    Shelley Moore Capito

    Shelley_Moore_Capito

  • 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

    Pressurized heavy-water reactor

    Pressurized heavy-water reactor

    Pressurized_heavy-water_reactor

  • Mark Lynas
  • British author and journalist (born 1973)

    featured in the 2013 pro-nuclear documentary film Pandora's Promise. Generation IV reactor research programs are developing the type of nuclear power described

    Mark Lynas

    Mark_Lynas

  • 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

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