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Generation IV reactor

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749: 558: 942: 302: 3821: 3811: 3791: 388: 1482: 3801: 1496: 890: 874: 681: 870:. The SFR fuel is contained in steel cladding. Liquid sodium fills the space between the clad elements that make up the fuel assembly. One of the design challenges is the risks of handling sodium, which reacts explosively if it comes into contact with water. The use of liquid metal instead of water as coolant allows the system to work at atmospheric pressure, reducing the risk of leakage. 824:, a 500 MWe Sodium cooled fast reactor is being built at a cost of INR 5,677 crores (~US$ 900 million). After numerous delays, the government reported in March 2020 that the reactor might be operational in December 2021. The PFBR was to be followed by six more Commercial Fast Breeder Reactors (CFBRs) of 600 MW 2604:"The aim of Generation IV systems is to maintain the high level of safety achieved by today's reactors, while shifting from the current principle of "mastering accidents" (i.e. accepting that accidents can occur, but taking care that the population is not affected) to the principle of "excluding accidents"." 126:"the development of concepts for one or more Generation IV systems that can be licensed, constructed, and operated in a manner that will provide a competitively priced and reliable supply of energy ... while satisfactorily addressing nuclear safety, waste, proliferation and public perception concerns." 1162:
cautions, "the problem with new reactors and accidents is twofold: scenarios arise that are impossible to plan for in simulations; and humans make mistakes". As one director of a U.S. research laboratory put it, "fabrication, construction, operation, and maintenance of new reactors will face a steep
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No precise definition of a Generation IV reactor exists. The term refers to nuclear reactor technologies under development as of approximately 2000, and whose designs were intended to represent 'the future shape of nuclear energy', at least at that time. The six designs selected were: the gas-cooled
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at Tsuruga, Japan. Using lead or molten salt coolants mitigates this problem as they are less reactive and have a high freezing temperature and ambient pressure. Lead has much higher viscosity, much higher density, lower heat capacity, and more radioactive neutron activation products than sodium.
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In 2000, GIF stated, "After the performance phase is complete for each system, at least six years and several US$ billion will be required for detailed design and construction of a demonstration system." In the Roadmap update of 2013, the performance and demonstration phases were considerably
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SCWRs share the steam explosion and radioactive steam release hazards of BWRs and LWRs as well as the need for extremely expensive heavy duty pressure vessels, pipes, valves, and pumps. These shared problems are inherently more severe for SCWRs due to their higher temperatures.
116:. It was connected to the grid in December 2023, making it the world's first Gen IV reactor to enter commercial operation. In 2024, it was reported that China would also build the world’s first thorium molten salt nuclear power station, scheduled to be operational by 2029. 46:) – an international organization that coordinates the development of generation IV reactors – specifically selected six reactor technologies as candidates for generation IV reactors. The designs target improved safety, sustainability, efficiency, and cost. The 317:
The very-high-temperature reactor (VHTR) uses a graphite-moderated core with a once-through uranium fuel cycle, using helium or molten salt. This reactor design envisions an outlet temperature of 1,000°C. The reactor core can be either a prismatic-block or a
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At the Forum's October 2021 meeting, the Forum members agreed to create a task force on non-electric applications of nuclear heat, including district and industrial heat applications, desalination and large-scale hydrogen production.
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In November 2013, a brief overview of the reactor designs and activities by each forum member was made available. An update of the technology roadmap which details R&D objectives for the next decade was published in January 2014.
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efficiency in the FBTR for the first time reached the 100,000 megawatt-days per metric ton uranium (MWd/MTU) mark. This is considered an important milestone in Indian breeder reactor technology. Using that experience, the
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fast reactor (GFR), the lead-cooled fast reactor (LFR), the molten salt reactor (MSR), the sodium-cooled fast reactor (SFR), the supercritical-water-cooled reactor (SCWR) and the very high-temperature reactor (VHTR).
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shifted to later dates, while no targets for the commercialisation phases are set. According to the GIF in 2013, "It will take at least two or three decades before the deployment of commercial Gen IV systems."
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It coordinates the development of GEN IV technologies. It has been instrumental in coordinating research into the six types of Generation IV reactors, and in defining the scope and meaning of the term itself.
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MCSFR does away with the graphite moderator. They achieve criticality using a sufficient volume of salt and fissile material. They can consume much more of the fuel and leave only short-lived waste.
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from other reactors, rather than breeding new fuel. The design reduces the half lives of the fissionable elements present in spent nuclear fuel while generating electricity largely as a byproduct.
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The GEN IV Forum reframes the reactor safety paradigm, from accepting that nuclear accidents can occur and should be mastered, to eliminating the physical possibility of an accident. Active and
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H. Boussier, S. Delpech, V. Ghetta et Al. : The Molten Salt Reactor (MSR) in Generation IV: Overview and Perspectives, GIF SYMPOSIUM PROCEEDINGS/2012 ANNUAL REPORT, NEA No. 7141, pp95
494:'s Molten Chloride Fast Reactor. This concept mixes the liquid natural uranium and molten chloride coolant in the reactor core, reaching very high temperatures at atmospheric pressure. 1967: 2147: 3314: 2885: 591:(LWR) operating at higher pressure and temperatures with a direct, once-through heat exchange cycle. As commonly envisioned, it would operate on a direct cycle, much like a 2542: 2389: 1865: 3508: 2425: 2407: 265:
than they consume. These systems offer significant advances in sustainability, safety and reliability, economics, proliferation resistance, and physical protection.
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In 2013 German, British, and French institutes finished a 3-year collaboration study on the follow-on industrial scale design. They were funded by the EU's 7th FWP
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The European Sustainable Nuclear Industrial Initiative funded three Generation IV reactor systems. Advanced Sodium Technical Reactor for Industrial Demonstration (
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fuel, advanced fuel particles, or ceramic-clad actinide compounds. Core configurations involve pin- or plate-based fuel assemblies or prismatic blocks.
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Many reactor types were considered initially; the list was then refined to focus on the most promising technologies. Three systems are nominally
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learning curve: advanced technologies will have a heightened risk of accidents and mistakes. The technology may be proven, but people are not".
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Locatelli, Giorgio; Mancini, Mauro; Todeschini, Nicola (2013-10-01). "Generation IV nuclear reactors: Current status and future prospects".
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of conventional reactors. This latter design was found to be the most competitive by consultancy firm Energy Process Development in 2015.
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A specific risk of the SFR is related to using metallic sodium as a coolant. In case of a breach, sodium explosively reacts with water.
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systems would be at least as effective as those of Generation III systems and render the most severe accidents physically impossible.
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Demonstration: complete and license the detailed design and carry out construction and operation of prototype or demonstration systems.
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The GIF Forum has introduced development timelines for each of the six systems. Research and development is divided into three phases:
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Performance: verify and optimise "engineering-scale processes, phenomena and materials capabilities" under prototypical conditions;
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Molten salt can be used for thermal, epithermal and fast reactors. Since 2005 the focus has been on fast spectrum MSRs (MSFR).
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Improved safety via features such as ambient pressure operation, automatic passive reactor shutdown, and alternate coolants.
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with a reactor outlet coolant temperature of 550-800 Â°C. The higher temperature enables the production of hydrogen by
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are being used to provide operating experience and technological solutions that will be applied to the construction of the
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Viability: test basic concepts under relevant conditions; identify and resolve all "potential technical show-stoppers";
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design, to purportedly give enhanced proliferation resistance. Preparatory construction work commenced in May 2020.
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The European Sustainable Nuclear Industrial Initiative provided funding for three Generation IV reactor systems:
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Other designs include integral molten salt reactors (e.g. IMSR) and molten chloride salt fast reactors (MCSFR).
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has received the greatest share of funding that supports demonstration facilities. Moir and Teller consider the
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directly uses fission neutrons without moderation. Fast reactors can be configured to "burn", or fission, all
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The gas-cooled fast reactor (GFR) features a fast-neutron spectrum and closed fuel cycle. The reactor is
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The Generation IV International Forum (GIF) is an international organization with its stated goal being
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reactor is a modernized and commercial implementation of the Integral Fast Reactor (IFR), developed by
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supported by central and eastern Europe; and a lead-cooled fast reactor, LFR, technology pilot called
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than a thermal reactor due to the higher average speed of the neutrons that cause the fission events.
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Article from Idaho National Laboratory detailing some current efforts at developing Gen. IV reactors.
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concept. Because the average speed of the fission-causing neutrons within the fuel is faster than
3759: 3734: 3348: 3125: 2913:"In the wake of a severe plant accident, advanced reactor designs are getting renewed attention." 2510: 1787:"Dual criticality for Chinese demonstration HTR-PM  : New Nuclear - World Nuclear News" 1465: 1347: 1110: 908: 689: 600: 498: 476: 274: 214:, the Canadian developer of a molten salt reactor, became the first private company to join GIF. 74: 35: 3717: 2276: 3624: 2202: 1540: 1275: 1067: 89: 1936:"Generation IV International Forum Updates Technology Roadmap and Builds Future Collaboration" 780:
Sodium-cooled fast reactors (SCFRs) have been operated in multiple countries since the 1980s.
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with construction expected by 2036. A reduced-power model called Guinevere was started up at
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What is the risk of a severe accident resembling Chernobyl or Fukushima in a Gen IV design?
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that uses lead as a cooling medium with molten salt fuel, commonly a metal chloride, e.g.
8: 3739: 3524: 3118: 2986: 2965: 2252:"Idaho National Laboratory detailing some current efforts at developing Gen. IV reactors" 1550: 1437: 1409: 1228: 1084: 867: 792: 736: 665: 596: 588: 584: 522: 480: 479:, to aid in greater closed-fuel cycle capabilities. Other notable approaches include the 396: 327: 323: 78: 62: 58: 2334: 2240: 1706: 1629: 1038:
Two other lead-cooled fast reactors under development are the SVBR-100, a modular 100 MW
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operated for over thirty years at Idaho National Laboratory, but was shut down in 1994.
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proposed by France, but subsequently cancelled; a gas-cooled fast reactor, GFR, called
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Multiple proof of concept Gen IV designs have been built. For example, the reactors at
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is used to prevent sodium oxidation. Argon can displace oxygen in the air and can pose
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It was established in 2001, aiming at availability for industrial deployment by 2030.
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that features a long refueling interval, a modular system rated at 300 to 400 MW
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gas-cooled fast reactor, planned for central or eastern Europe. The central European
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designs operate at much higher temperatures than prior generations. This allows for
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for high thermal efficiency. Several fuel forms are under consideration: composite
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Nuclear waste that remains radioactive for a few centuries instead of millennia
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The two largest experimental sodium cooled fast reactors are in Russia, the
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was the first country to operate a demonstration generation-IV reactor, the
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Potential to burn existing nuclear waste and produce electricity: a closed
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U.S. Department of Energy Office of Nuclear Energy, Science and Technology
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The European Sustainable Nuclear Industrial Initiative is funding a 100 MW
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design. The high temperatures enable applications such as process heat or
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in 2015 suggested that some might enter commercial operation before 2030.
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GEN IV International Forum. Published 1 October 2013. Accessed Nov. 2021)
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emitted by fission to make them more likely to be captured by the fuel.
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Broader range of fuels, including unencapsulated raw fuels (non-pebble
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The majority of reactors in operation around the world are considered
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The lead-cooled fast reactor (LFR) features a fast-neutron-spectrum
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A molten salt reactor (MSR) is a type of reactor where the primary
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Technology Roadmap Update for Generation IV Nuclear Energy Systems
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reactor are similar to the proposed pool type Gen IV SFR designs.
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between 1984 and 1994. The primary purpose of PRISM is burning up
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lead-bismuth cooled fast neutron reactor concept designed by OKB
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isotopes. The reactor design uses an unmoderated core running on
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was provided a five-year grant of up to $ 40 million by the
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first Gen IV reactor). The largest ever operated was the French
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Since 2021, the Chinese government is operating a demonstration
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Preparatory construction for Brest-300 reactor begins in Russia
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Relative to Gen II-III, advantages of Gen IV reactors include:
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Early thermal spectrum concepts and many current ones rely on
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for the efficient production of hydrogen and the synthesis of
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A Technology Roadmap for Generation IV Nuclear Energy Systems
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mixture. It operates at high temperature and low pressure.
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The Gen IV SFR is a project that builds on the oxide fueled
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Another notable feature of the MSR is the possibility of a
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US DOE Nuclear Energy Research Advisory Committee (2002).
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100–300x energy yield from the same amount of nuclear fuel
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International Thorium Energy Organisation - www.IThEO.org
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design technologies that are envisioned as successors of
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Numerous progenitors of the Gen IV SFR exist. The 400 MW
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produced by the present world fleet of thermal neutron
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Supercritical water-cooled reactors (SCWRs) offer high
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to advance their reactor development. The Xe-100 is a
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Science or Fiction - Is there a Future for Nuclear?
2758:"Key components of second HTR-PM reactor connected" 743: 533:) is below the consumption rate, thus reducing the 2354: 2352: 2320: 2053: 617:The mission of the SCWR is generation of low-cost 16:New nuclear reactor technologies under development 2310:"Molten salt and traveling wave nuclear reactors" 1649: 1647: 936: 877:The sustainable fuel-cycle proposed in the 1990s 3837: 2602:GEN IV International Forum (accessed Nov. 2021). 2591: 2588:, Nuclear Engineering International. 22 May 2020 2509:. Nuclear Engineering at Argonne. 3 March 2014. 996:. The fuel is metal or nitride-based containing 675: 2632:"4th Generation Nuclear Power — OSS Foundation" 2469: 2349: 1995: 1993: 1991: 1113:concerns for workers. This was a factor at the 992:, and a large monolithic plant at 1,200 MW 893:IFR concept (Black and White with clearer text) 191:The Forum was initiated in January 2000 by the 2929:International Thorium Energy Committee - iThEC 2891: 2884:(Nov. 2007) - A publication from the Austrian 1666: 1664: 1644: 1302:), China National Nuclear Corporation (CNNC) ( 1035:in March 2009 and became operational in 2012. 858:and fueled by a metallic alloy of uranium and 3620:Small sealed transportable autonomous (SSTAR) 2949: 2777: 2775: 1596:Welcome to Generation IV International forum. 1590: 1588: 1586: 984:. Proposals include a small 50 to 150 MW 739:, with the goal of making a sustainable VHTR. 2475: 2120: 1988: 1658:. World Nuclear Association, update Dec 2020 911:operated for ten years at Hanford; the 20 MW 854:One SFR reactor concept is cooled by liquid 752:Pool design Sodium-Cooled Fast Reactor (SFR) 571:The supercritical water reactor (SCWR) is a 465:Most MSR designs are derived from the 1960s 382: 1914: 1877: 1875: 1661: 1611: 1609: 1607: 1605: 3800: 2956: 2942: 2888:about 'Generation IV' and Fusion reactors. 2810:"China begins building pilot fast reactor" 2772: 2307: 2189: 2187: 2185: 2183: 2181: 1883:FAQ 2: When will Gen IV reactors be built? 1797: 1781: 1779: 1760: 1758: 1688: 1583: 587:as the working fluid. SCWRs are basically 2559: 2308:Tennenbaum, Jonathan (February 4, 2020). 1742: 636:One SCWR design under development is the 561:Supercritical-Water-Cooled Reactor (SCWR) 553:Supercritical-water-cooled reactor (SCWR) 3532: 2898:Mechanical Engineering (the magazine of 2684: 2560:Hellemans, Alexander (12 January 2012). 2490: 2087: 1872: 1602: 1308:Indira Gandhi Centre for Atomic Research 940: 888: 872: 747: 679: 556: 469:(MSRE). Variants include the conceptual 386: 300: 2867:Generation IV International Forum (GIF) 2680: 2678: 2659: 2178: 1776: 1755: 1172:Summary of designs for Gen IV reactors 1021:accelerator-driven sub-critical reactor 3838: 3547:Liquid-fluoride thorium reactor (LFTR) 2615:"Strategies to Address Global Warming" 2408:"the European Gas cooled Fast Reactor" 1736: 672:more actinide fuel than they consume. 3552:Molten-Salt Reactor Experiment (MSRE) 2937: 2685:Sovacool, Benjamin K. (August 2010). 2277:"Europe: Moltex' Stable Salt Reactor" 2145: 1889: 1743:De Clercq, Geert (October 13, 2014). 1511:List of small modular reactor designs 881:concept (color), an animation of the 2675: 2476:Ramachandran, R. (August 20, 2020). 1925:GEN IV International Forum Nov 2021) 1803: 1689:Moir, Ralph; Teller, Edward (2005). 1118:Prototype Fast Breeder Reactor Monju 490:Another design under development is 364:, or 320 MWe in a 'four-pack'. 297:Very-high-temperature reactor (VHTR) 132:As of 2021, active members include: 3557:Integral Molten Salt Reactor (IMSR) 1132:are similar to the proposed Gen IV 1004:. The reactor is cooled by natural 313:High-temperature gas-cooled reactor 268: 114:high-temperature gas-cooled reactor 13: 3366: 2121:Fehrenbacher, Katie (2016-02-16). 1804:Howe, Colleen (December 6, 2023). 1342:-1700/393 (VVER-SCWR or VVER-SKD) 1166: 579:, it is more accurately termed an 354:United States Department of Energy 14: 3862: 2848: 2451:"Advanced Nuclear Power Reactors" 2295:analysis.nuclearenergyinsider.com 1126:Fort St. Vrain Generating Station 1050:(Lead-cooled fast reactor) 300 MW 120:Generation IV International Forum 40:Generation IV International Forum 3820: 3819: 3810: 3809: 3799: 3790: 3789: 3640:Fast Breeder Test Reactor (FBTR) 2892:Gail H. Marcus (December 2011). 2513:from the original on 2021-12-21. 2333:. March 24, 2010. Archived from 1970:Genesis of Generation IV Concept 1745:"Can Sodium Save Nuclear Power?" 1494: 1480: 1436:, Elysium Industries, Thorizon, 744:Sodium-cooled fast reactor (SFR) 647: 583:than a thermal reactor. It uses 573:reduced moderation water reactor 261:to further reduce waste and can 244: 146:European Atomic Energy Community 92:systems, as the majority of the 2894:"Nuclear Power After Fukushima" 2824: 2802: 2750: 2725: 2653: 2624: 2607: 2579: 2553: 2535: 2517: 2499: 2484: 2443: 2418: 2400: 2382: 2301: 2283: 2269: 2244: 2233: 2164: 2139: 2114: 2081: 2021: 1960: 1946: 1928: 1858: 1834: 1816: 1556:Liquid fluoride thorium reactor 764:Experimental Breeder Reactor II 517:in the spent nuclear fuel with 403:Liquid fluoride thorium reactor 3630:Energy Multiplier Module (EM2) 2426:"The GOFASTR research program" 2088:Fountain, Henry (2016-01-19). 2010:. January 2014. Archived from 1977:. January 2014. Archived from 1682: 1655:Generation IV Nuclear Reactors 1312:Prototype Fast Breeder Reactor 937:Lead-cooled fast reactor (LFR) 822:Prototype Fast Breeder Reactor 467:Molten-Salt Reactor Experiment 448:by flowing into a core with a 1: 1577: 1061: 885:technology is also available. 700:very-high-temperature reactor 684:Gas-Cooled Fast Reactor (GFR) 676:Gas-cooled fast reactor (GFR) 521:. The net production rate of 341:approved a design similar to 335:next generation nuclear plant 306:Very-high-temperature reactor 180:. Non-active members include 71:high temperature electrolysis 67:very-high-temperature reactor 3430:Uranium Naturel Graphite Gaz 2691:Journal of Contemporary Asia 2372:that is proposed by Belgium" 2201:. GIF-002-00. Archived from 2175:X Energy (accessed Feb 2023) 1264:30–150, 300–1500, 1000–2000 728:are pursuing the technology. 221: 7: 3846:Nuclear power reactor types 3777:Aircraft Reactor Experiment 2457:. World Nuclear Association 2146:Conca, James (2017-03-27). 2033:Nuclear Energy Agency (NEA) 1638:10.1016/j.enpol.2013.06.101 1473: 1417:Fluoride or chloride salts 1391:20–180, 300–1200, 600–1000 927:Argonne National Laboratory 567:Supercritical water reactor 96:systems have been retired. 10: 3867: 3615:Liquid-metal-cooled (LMFR) 1791:www.world-nuclear-news.org 1770:www.world-nuclear-news.org 954: 948: 843:plutonium and eliminating 761: 758:Sodium-cooled fast reactor 755: 687: 564: 400: 394: 310: 3851:Idaho National Laboratory 3785: 3752: 3740:Stable Salt Reactor (SSR) 3653: 3635:Reduced-moderation (RMWR) 3600: 3583: 3523: 3450: 3442:Advanced gas-cooled (AGR) 3416: 3407: 3359: 3339: 3292: 3274: 3230: 3135: 3117: 2985: 2972: 2703:10.1080/00472331003798350 1502:Nuclear technology portal 1448:, Thorium Tech Solution ( 1288:GE Hitachi Nuclear Energy 866:, the "nuclear waste" of 813:Fast Breeder Test Reactor 599:(not to be confused with 391:Molten Salt Reactor (MSR) 383:Molten-salt reactor (MSR) 339:Idaho National Laboratory 197:U.S. Department of Energy 48:World Nuclear Association 3805:List of nuclear reactors 3645:Dual fluid reactor (DFR) 3261:Steam-generating (SGHWR) 1571:List of nuclear reactors 1368:Energy Multiplier Module 1010:thermochemical processes 951:Lead-cooled fast reactor 945:Lead-Cooled Fast Reactor 507:utilization or reduction 444:salt. The fluid reaches 411:or the fuel itself is a 371:200-MW high temperature 333:In 2012, as part of its 193:Office of Nuclear Energy 90:third generation reactor 3795:Nuclear fusion reactors 3760:Organic nuclear reactor 2966:nuclear fission reactor 2788:US Department of Energy 1599:GIF (accessed Feb 2023) 1027:. It is to be built in 909:Fast Flux Test Facility 807:reactor at over 1200 MW 791:(880 MWe gross). These 690:Gas-cooled fast reactor 535:nuclear storage problem 477:plutonium(III) chloride 440:), dissolved in molten 360:that would generate 80 326:via the thermochemical 36:generation III reactors 2221:Cite journal requires 1541:Generation III reactor 946: 894: 886: 753: 685: 562: 392: 375:as a successor to its 308: 1566:Small modular reactor 1546:Integral Fast Reactor 1536:Generation II reactor 1531:List of reactor types 944: 892: 879:Integral fast reactor 876: 837:integral fast reactor 835:and the metal fueled 751: 683: 595:(BWR). Since it uses 593:boiling water reactor 560: 539:nuclear proliferation 434:thorium tetrafluoride 426:uranium tetrafluoride 390: 304: 3625:Traveling-wave (TWR) 3109:Supercritical (SCWR) 2812:. World Nuclear News 2760:. World Nuclear News 2636:www.ossfoundation.us 2531:. February 22, 2012. 2394:www.alphagalileo.org 1772:. 13 September 2021. 1430:Seaborg Technologies 868:light water reactors 833:fast breeder reactor 666:light water reactors 589:light water reactors 523:transuranic elements 289:is used to slow the 79:carbon-neutral fuels 2995:Aqueous homogeneous 2877:Gen IV presentation 1922:Origins of the GIF. 1830:. December 6, 2023. 1749:Scientific American 1715:10.13182/NT05-A3655 1707:2005NucTe.151..334M 1630:2013EnPol..61.1503L 1551:Stable salt reactor 1336:300–700, 1000–1500 1229:Tsinghua University 1195:Example developers 1173: 737:framework programme 597:supercritical water 585:supercritical water 541:concerns and other 481:Stable Salt Reactor 397:Molten salt reactor 328:sulfur-iodine cycle 324:hydrogen production 75:sulfur–iodine cycle 63:molten-salt reactor 59:sodium fast reactor 3815:Nuclear technology 2922:2016-03-06 at the 2860:2014-11-09 at the 2838:2022-12-29 at the 2669:The New York Times 2094:The New York Times 2069:. 15 February 2012 2066:World Nuclear News 1828:World Nuclear News 1695:Nuclear Technology 1454:Terrestrial Energy 1446:Copenhagen Atomics 1171: 1046:in Russia and the 947: 931:spent nuclear fuel 895: 887: 864:spent nuclear fuel 754: 686: 662:spent nuclear fuel 612:thermal efficiency 581:epithermal reactor 563: 545:associated with a 511:spent nuclear fuel 472:Dual fluid reactor 457:epithermal reactor 393: 373:pebble bed reactor 320:pebble bed reactor 309: 281:that uses slow or 212:Terrestrial Energy 3833: 3832: 3825:Nuclear accidents 3748: 3747: 3579: 3578: 3575: 3574: 3519: 3518: 3403: 3402: 3335: 3334: 2886:Ecology Institute 2549:. 29 August 2019. 2455:world-nuclear.org 1676:world-nuclear.org 1471: 1470: 1186:Temperature (°C) 1180:Neutron spectrum 1158:Nuclear engineer 1136:designs, and the 982:closed fuel cycle 980:) coolant with a 720:Allegro: a 100 MW 348:In January 2016, 287:neutron moderator 86:second generation 3858: 3823: 3822: 3813: 3812: 3803: 3802: 3793: 3792: 3735:Helium gas (GFR) 3598: 3597: 3593: 3530: 3529: 3414: 3413: 3364: 3363: 3357: 3356: 3352: 3351: 3133: 3132: 3129: 3128: 2958: 2951: 2944: 2935: 2934: 2912: 2910: 2908: 2843: 2828: 2822: 2821: 2819: 2817: 2806: 2800: 2799: 2797: 2795: 2779: 2770: 2769: 2767: 2765: 2754: 2748: 2747: 2745: 2743: 2738:. 21 August 2009 2737: 2729: 2723: 2722: 2682: 2673: 2672: 2663:(17 June 2011). 2657: 2651: 2650: 2648: 2647: 2638:. Archived from 2628: 2622: 2621: 2619: 2611: 2605: 2595: 2589: 2583: 2577: 2576: 2574: 2572: 2557: 2551: 2550: 2539: 2533: 2532: 2521: 2515: 2514: 2503: 2497: 2496: 2488: 2482: 2481: 2473: 2467: 2466: 2464: 2462: 2447: 2441: 2440: 2438: 2437: 2428:. Archived from 2422: 2416: 2415: 2410:. Archived from 2404: 2398: 2397: 2386: 2380: 2379: 2374:. Archived from 2356: 2347: 2346: 2344: 2342: 2327: 2318: 2317: 2305: 2299: 2298: 2287: 2281: 2280: 2279:. 20 April 2015. 2273: 2267: 2266: 2264: 2263: 2254:. Archived from 2248: 2242: 2237: 2231: 2230: 2224: 2219: 2217: 2209: 2207: 2200: 2191: 2176: 2172:Reactor: Xe-100. 2168: 2162: 2161: 2159: 2158: 2143: 2137: 2136: 2134: 2133: 2118: 2112: 2111: 2109: 2108: 2085: 2079: 2078: 2076: 2074: 2057: 2051: 2043: 2037: 2036: 2025: 2019: 2018: 2017:on 25 June 2014. 2016: 2009: 1997: 1986: 1985: 1983: 1976: 1964: 1958: 1957: 1950: 1944: 1943: 1932: 1926: 1918: 1912: 1911: 1909: 1907: 1897:"GIF Membership" 1893: 1887: 1879: 1870: 1869: 1862: 1856: 1855: 1853: 1852: 1838: 1832: 1831: 1820: 1814: 1813: 1801: 1795: 1794: 1783: 1774: 1773: 1762: 1753: 1752: 1740: 1734: 1733: 1731: 1729: 1686: 1680: 1679: 1668: 1659: 1651: 1642: 1641: 1613: 1600: 1592: 1521:Nuclear material 1504: 1499: 1498: 1497: 1490: 1485: 1484: 1462:Southern Company 1440:, Flibe Energy ( 1414:Fast or thermal 1327:Water or Sodium 1324:Thermal or fast 1174: 1170: 577:thermal neutrons 543:technical issues 499:thermal spectrum 283:thermal neutrons 269:Thermal reactors 251:thermal reactors 94:first generation 3866: 3865: 3861: 3860: 3859: 3857: 3856: 3855: 3836: 3835: 3834: 3829: 3781: 3744: 3649: 3594: 3587: 3586: 3571: 3515: 3446: 3421: 3399: 3371: 3353: 3346: 3345: 3344: 3331: 3297: 3288: 3270: 3235: 3226: 3140: 3123: 3122: 3121: 3113: 3027:Natural fission 2981: 2980: 2968: 2962: 2924:Wayback Machine 2906: 2904: 2862:Wayback Machine 2851: 2846: 2840:Wayback Machine 2829: 2825: 2815: 2813: 2808: 2807: 2803: 2793: 2791: 2781: 2780: 2773: 2763: 2761: 2756: 2755: 2751: 2741: 2739: 2735: 2731: 2730: 2726: 2683: 2676: 2661:Tabuchi, Hiroko 2658: 2654: 2645: 2643: 2630: 2629: 2625: 2617: 2613: 2612: 2608: 2603: 2596: 2592: 2584: 2580: 2570: 2568: 2566:Science Insider 2558: 2554: 2541: 2540: 2536: 2523: 2522: 2518: 2505: 2504: 2500: 2489: 2485: 2474: 2470: 2460: 2458: 2449: 2448: 2444: 2435: 2433: 2424: 2423: 2419: 2406: 2405: 2401: 2396:. 27 July 2023. 2388: 2387: 2383: 2358: 2357: 2350: 2340: 2338: 2329: 2328: 2321: 2306: 2302: 2289: 2288: 2284: 2275: 2274: 2270: 2261: 2259: 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279:nuclear reactor 275:thermal reactor 271: 263:breed more fuel 247: 224: 122: 32:nuclear reactor 17: 12: 11: 5: 3864: 3854: 3853: 3848: 3831: 3830: 3828: 3827: 3817: 3807: 3797: 3786: 3783: 3782: 3780: 3779: 3774: 3773: 3772: 3767: 3756: 3754: 3750: 3749: 3746: 3745: 3743: 3742: 3737: 3732: 3727: 3726: 3725: 3720: 3715: 3710: 3705: 3700: 3695: 3690: 3685: 3680: 3675: 3670: 3659: 3657: 3651: 3650: 3648: 3647: 3642: 3637: 3632: 3627: 3622: 3617: 3612: 3610:Integral (IFR) 3607: 3601: 3595: 3584: 3581: 3580: 3577: 3576: 3573: 3572: 3570: 3569: 3564: 3559: 3554: 3549: 3544: 3538: 3536: 3527: 3521: 3520: 3517: 3516: 3514: 3513: 3512: 3511: 3506: 3505: 3504: 3499: 3494: 3489: 3474: 3469: 3468: 3467: 3456: 3454: 3448: 3447: 3445: 3444: 3439: 3434: 3425: 3423: 3419: 3411: 3405: 3404: 3401: 3400: 3398: 3397: 3392: 3387: 3382: 3376: 3374: 3369: 3361: 3354: 3340: 3337: 3336: 3333: 3332: 3330: 3329: 3328: 3327: 3322: 3317: 3312: 3301: 3299: 3295: 3290: 3289: 3287: 3286: 3280: 3278: 3272: 3271: 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1846:en.cnnc.com.cn 1833: 1815: 1796: 1775: 1754: 1735: 1701:(3): 334–340. 1681: 1660: 1643: 1601: 1581: 1579: 1576: 1574: 1573: 1568: 1563: 1558: 1553: 1548: 1543: 1538: 1533: 1528: 1523: 1518: 1513: 1507: 1506: 1505: 1491: 1475: 1472: 1469: 1468: 1427: 1424: 1421: 1418: 1415: 1412: 1406: 1405: 1392: 1389: 1386: 1383: 1380: 1377: 1371: 1370: 1365: 1362: 1359: 1356: 1353: 1350: 1344: 1343: 1337: 1334: 1331: 1328: 1325: 1322: 1316: 1315: 1265: 1262: 1259: 1256: 1253: 1250: 1244: 1243: 1218: 1215: 1212: 1209: 1206: 1203: 1197: 1196: 1193: 1190: 1187: 1184: 1181: 1178: 1168: 1165: 1160:David Lochbaum 1103: 1102: 1099: 1092: 1081: 1078: 1068:passive safety 1063: 1060: 1056:BN-600 reactor 1051: 1039: 1016: 993: 989: 985: 949:Main article: 938: 935: 912: 905: 883:pyroprocessing 825: 808: 756:Main article: 745: 742: 741: 740: 729: 726:Visegrád Group 721: 688:Main article: 677: 674: 649: 646: 642:breeding ratio 565:Main article: 554: 551: 537:, without the 437: 429: 395:Main article: 384: 381: 311:Main article: 298: 295: 270: 267: 253:and three are 246: 243: 238: 237: 234: 231: 223: 220: 174:United Kingdom 121: 118: 104:in Shidaowan, 15: 9: 6: 4: 3: 2: 3863: 3852: 3849: 3847: 3844: 3843: 3841: 3826: 3818: 3816: 3808: 3806: 3798: 3796: 3788: 3787: 3784: 3778: 3775: 3771: 3768: 3766: 3763: 3762: 3761: 3758: 3757: 3755: 3751: 3741: 3738: 3736: 3733: 3731: 3728: 3724: 3721: 3719: 3716: 3714: 3711: 3709: 3706: 3704: 3701: 3699: 3696: 3694: 3691: 3689: 3686: 3684: 3681: 3679: 3676: 3674: 3671: 3669: 3666: 3665: 3664: 3661: 3660: 3658: 3656: 3655:Generation IV 3652: 3646: 3643: 3641: 3638: 3636: 3633: 3631: 3628: 3626: 3623: 3621: 3618: 3616: 3613: 3611: 3608: 3606: 3605:Breeder (FBR) 3603: 3602: 3599: 3596: 3591: 3582: 3568: 3565: 3563: 3560: 3558: 3555: 3553: 3550: 3548: 3545: 3543: 3540: 3539: 3537: 3535: 3531: 3528: 3526: 3522: 3510: 3507: 3503: 3500: 3498: 3495: 3493: 3490: 3488: 3485: 3484: 3483: 3480: 3479: 3478: 3475: 3473: 3470: 3466: 3463: 3462: 3461: 3458: 3457: 3455: 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reactors 645: 643: 639: 634: 630: 628: 624: 620: 615: 613: 608: 606: 602: 601:critical mass 598: 594: 590: 586: 582: 578: 574: 568: 559: 550: 548: 544: 540: 536: 532: 528: 524: 520: 516: 512: 508: 504: 500: 495: 493: 488: 486: 482: 478: 474: 473: 468: 463: 460: 458: 454: 451: 447: 443: 435: 427: 422: 419: 416: 414: 410: 404: 398: 389: 380: 378: 374: 370: 365: 363: 359: 355: 351: 346: 344: 340: 337:competition, 336: 331: 329: 325: 321: 314: 307: 303: 294: 292: 288: 284: 280: 276: 266: 264: 260: 256: 255:fast reactors 252: 245:Reactor types 242: 235: 232: 229: 228: 227: 219: 215: 213: 210:In May 2019, 208: 204: 202: 198: 194: 189: 187: 183: 179: 178:United States 175: 171: 167: 163: 159: 155: 151: 147: 143: 139: 135: 130: 127: 117: 115: 111: 108:, which is a 107: 103: 99: 95: 91: 87: 82: 80: 76: 72: 68: 64: 60: 55: 51: 49: 45: 41: 37: 33: 29: 25: 21: 20:Generation IV 3663:Sodium (SFR) 3654: 3590:fast-neutron 3429: 2975: 2905:. 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Index

nuclear reactor
generation III reactors
World Nuclear Association
sodium fast reactor
molten-salt reactor
very-high-temperature reactor
high temperature electrolysis
sulfur–iodine cycle
carbon-neutral fuels
second generation
third generation reactor
first generation
China
HTR-PM
Shandong
pebble-bed
high-temperature gas-cooled reactor
Australia
Canada
China
European Atomic Energy Community
France
Japan
Russia
South Africa
South Korea
Switzerland
United Kingdom
United States
Argentina

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