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"fast-breeder reactor" Definitions
  1. a breeder reactor in which there is no moderator and fission is caused by high-energy neutrons.
"fast-breeder reactor" Synonyms
nuclear reactor reactor atomic furnace atomic pile atomic power plant atomic reactor breeder reactor chain reactor core reactor neutron factory nuclear furnace nuclear power plant pile plutonium reactor reactor pile thermonuclear reactor uranium reactor

93 Sentences With "fast breeder reactor"

How to use fast breeder reactor in a sentence? Find typical usage patterns (collocations)/phrases/context for "fast breeder reactor" and check conjugation/comparative form for "fast breeder reactor". Mastering all the usages of "fast breeder reactor" from sentence examples published by news publications.

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The fast breeder reactor is not going to be commercially viable.
The experimental fast-breeder reactor, once dubbed the "dream reactor," was designed to produce more plutonium than it consumes, thus minimizing the amount of nuclear waste.
Now, Russia's BN-85033 fast reactor has entered commercial operation; India is expected to commission a commercial fast breeder reactor by the end of 2017; and China is making significant advances in both molten salt and fast reactor technologies.
The move to shut the Monju prototype fast breeder reactor in Fukui prefecture west of Tokyo adds to a list of failed attempts around the world to make the technology commercially viable and potentially cut stockpiles of dangerous nuclear waste.
The decision would have no impact on Japan's nuclear recycling policy as Tokyo would continue to co-develop a fast-breeder demonstration reactor that has been proposed in France, while research will continue at another experimental fast-breeder reactor, Joyo, which was a predecessor of Monju.
And then there is the question of what to do with Monju, a fast-breeder reactor (one that generates more fuel than it consumes) which cost $10 billion to build but has generated power for only one hour since its inauguration in 1995 owing to a series of accidents.
The Fast Breeder Reactor-600 (FBR-600) or Commercial Fast Breeder Reactor (CFBR) is a 600 MWe fast breeder nuclear reactor presently being constructed. The Indira Gandhi Centre for Atomic Research (IGCAR) is responsible for the design of this reactor as a successor for Prototype Fast Breeder Reactor (PFBR). The 1st twin unit would come up at Kalpakkam, close to the PFBR site itself. Designed to "burn" a mixture of Uranium Oxide and Plutonium Oxide to generate 600 MWe of power each, current plans involve building 6 Units, co- locating 2 at any given place.
In 1976, he participated in the demonstrations against the building of the fast breeder reactor Superphénix at Creys-Malville, Isère (France).
JAEA has another head base in Tsuruga, Fukui Prefecture. It is a fast breeder reactor center and a Research and Development (R&D;) center.
In France, CEA and EDF had started to build Phénix in 1968, which was powered up in December 1973. It was a pool-type liquid-metal fast breeder reactor cooled with liquid sodium and a small-scale (gross 264/net 233 MWe) prototype fast breeder reactor, located at the Marcoule nuclear site, near Orange, France. Phénix had to be stopped for refueling every two months. Between 1990 and 1996, it was run sporadically.
Schematic diagram showing the difference between the Loop and Pool designs of a liquid metal fast breeder reactor There have been two main design approaches to sodium-cooled reactors. In the pool type, the primary coolant is entirely contained in the main reactor vessel, which therefore includes not only the reactor core but also a heat exchanger. The US EBR-2, French Phénix and others used this approach, and it is used by India's Prototype Fast Breeder Reactor and China's CFR-600. In the loop type, the heat exchangers are external to the reactor tank.
The BN-800 reactor The BN-reactor is a type of sodium-cooled fast breeder reactor built in Russia from the company OKBM Afrikantov. Two BN-reactors are to date (2015) the only commercial fast breeder reactors in operation worldwide.
This percentage is expected to double every 10 years for several decades out. Plans are for 200 GW installed by 2030 which will include a large shift to Fast Breeder reactor and 1500 GW by the end of this century.
This is considered an important milestone in Indian breeder reactor technology. Using the experience gained from the operation of the FBTR, the Prototype Fast Breeder Reactor, a 500 MWe Sodium cooled fast reactor is being built at a cost of INR 5,677 crores (~US$900 million) and is expected to be critical by 2020. The PFBR will be followed by six more Commercial Fast Breeder Reactors (CFBRs) of 600 MWe each. The Gen IV SFR is a project that builds on two existing projects for sodium cooled FBRs, the oxide fueled fast breeder reactor and the metal fueled integral fast reactor.
However, in 2014 Japan agreed to cooperate in developing the emergency reactor cooling system, and in a few other areas, with the French ASTRID demonstration sodium- cooled fast breeder reactor. As of 2016, France was seeking the full involvement of Japan in the ASTRID development.
Phénix (French for phoenix) was a small-scale (gross 264/net 233 MWe) prototype fast breeder reactor, located at the Marcoule nuclear site, near Orange, France. It was a pool-type liquid-metal fast breeder reactor cooled with liquid sodium. It generated 590 MW of thermal power, and had a breeding ratio of 1.16 (16% more plutonium produced than consumed), but normally had to be stopped for refueling operations every two months. Phénix continued operating after the closure of the subsequent full-scale prototype Superphénix in 1997. After 2004, its main use was investigation of transmutation of nuclear waste while also generating some electricity.
Monju enters extended testing. Aug 31, 2007. A restart date of February 2009 was again delayed due to the discovery of holes in the reactor's auxiliary building; in August 2009 it was announced that restart might be in February 2010.Reuters. Japan fast-breeder reactor may restart in Feb.
The JAEA began preparatory engineering work on May 24, 2011 to set up equipment to be used to retrieve the IVTM that fell inside the vessel. The fallen device was successfully retrieved from the reactor vessel on June 23, 2011.Fallen device retrieved from Japan fast-breeder reactor June 23, 2011.
The 69 MWe prototype fast breeder reactor Fermi 1 unit was under construction and development at the site from 1956 to 1963. Initial criticality was achieved on August 23, 1963. On October 5, 1966 Fermi 1 suffered a partial fuel meltdown. Two of the 92 fuel assemblies were partially damaged.
In general terms, the hybrid is similar in concept to the fast breeder reactor, which uses a compact high-energy fission core in place of the hybrid's fusion core. Another similar concept is the accelerator-driven subcritical reactor, which uses a particle accelerator to provide the neutrons instead of nuclear reactions.
These test assemblies, also referred to as test vehicles or test loops, can simulate the conditions of a light water reactor, heavy water reactor, liquid metal fast breeder reactor, or a gas cooled reactor. In some experiments, provisions were made to make high speed film recordings of the experiment, such as these videos.
AR 265 begins near Strickler at AR 170 near SEFOR, a deactivated experimental fast breeder reactor. The route continues north as a winding, two-lane highway into Greenland until its junction with I-49 and US 71 in south Fayetteville. The roadway continues north after these intersections (as Arkansas Highway 112) into Fayetteville.
All operating plants today are PWRs. The sodium-cooled fast breeder reactor technology development reactors, Phénix and Superphénix, have been shut down. Work on a more advanced design in the form of the ASTRID reactor was finally abandoned in September 2019. The PWR plants were all developed by Framatome (now Areva) from the initial Westinghouse design.
A cutaway model of the 2nd most powerful presently operating fast breeder reactor in the world. The (BN-600), at 600 MW of nameplate capacity is equivalent in power output to a natural gas CCGT. It dispatches 560 MW to the Middle Urals power grid. Construction of a second breeder reactor, the BN-800 reactor was completed in 2014.
The reactor on the left, the vent stack on the right fast breeder reactor SNR-300, now an amusement park. The SNR-300 was a fast breeder sodium cooled nuclear reactor built near the town of Kalkar, North Rhine-Westphalia, Germany. The reactor was completed but never taken online. SNR-300 was to output 327 megawatts.
However, it is possible to build a fast reactor that breeds fuel by producing more than it consumes. After the initial fuel charge such a reactor can be refueled by reprocessing. Fission products can be replaced by adding natural or even depleted uranium without further enrichment. This is the concept of the fast breeder reactor or FBR.
On May 22, 1986, a nuclear fuel reprocessing plant at La Hague in Normandy, sustained a mechanical malfunction. Five workers were exposed to unsafe levels of radiation and hospitalized. On April 12, 1987, the Tricastin Nuclear Power Plant fast breeder reactor coolant leaked contaminating seven workers. In July 2008, approximately 100 workers were exposed to a radiation leak.
In September 2002, fuel burn- up 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 breeder reactor technology. Using the experience gained from the operation of the FBTR, a 500 MWe Prototype Fast Breeder Reactor (PFBR) is in advanced stage of construction at Kalpakkam.
The third and final UKAEA-operated reactor to be built on the Dounreay site was the Prototype Fast Reactor (PFR). In 1966 it was announced that the PFR would be built at Dounreay. PFR was a pool-type fast breeder reactor, cooled by 1,500 tonnes of liquid sodium and fuelled with MOX. The design output of PFR was 250 MWe (electrical).
On 21 October 2011 the Japanese government appointed a commission to study ways to cut wasteful expenditures, one possibility being decommissioning the Monju prototype fast breeder reactor. The Government Revitalization Unit took up this issue, because the calls to abolish this reactor were growing after the nuclear accident at Fukushima. As the accident at the Fukushima Daiichi power plant made it difficult, if not impossible, to build new nuclear power plants, the government panel would also review subsidies for localities with atomic power plants as well as functions of related entities such as the Japan Atomic Energy Agency.Mainichi Japan (22 October 2011) Gov't cost-cutting unit to study Monju reactor's abolition On 27 November, after a visit to the plant, nuclear disaster minister Goshi Hosono said that scrapping the Monju-fast- breeder reactor was an option that would be given serious thought.
Even with its normal shutdown devices disabled, the reactor shut itself down safely without overheating anywhere in the system. The IFR project was canceled by the US Congress in 1994, three years before completion.The IFR at Argonne National Laboratory The proposed Generation IV Sodium-Cooled Fast Reactor is its closest surviving fast breeder reactor design. Other countries have also designed and operated fast reactors.
This heat is transferred from the reactor core via three independent circulation loops. Each comprises a primary sodium pump, two intermediate heat exchangers, a secondary sodium pump with an expansion tank located upstream, and an emergency pressure discharge tank. These feed a steam generator, which in turn supplies a condensing turbine that turns the generator. There is much international interest in the fast-breeder reactor at Beloyarsk.
The Clinch River Breeder Reactor was initially conceived as a major step toward developing liquid-metal fast breeder reactor technology as a commercially viable electric power generation system in the United States. In 1971 U.S. President Richard Nixon established this technology as the nation’s highest priority research and development effort. However, the Clinch River project was controversial from the start, and economic and political considerations eventually led to its demise.
RAF Dounreay was built for RAF Coastal Command in 1944, but not used by them. It was transferred to the Royal Navy as HMS Tern II, but not commissioned and on care and maintenance until 1954. In 1955 the airfield was taken over by the United Kingdom Atomic Energy Authority (UKAEA) for developing a fast breeder reactor. One runway was kept operational until the 1990s for transport to/from the site.
Recycled thorium that is recovered from the reactor is then sent back, and plutonium is stored to be later used for a fast breeder reactor. The fuel for AHWR would be manufactured by ADVANCED FUEL FABRICATION FACILITY, which is under the direction of BARC Tarapur. AFFF is currently working on PFBR fuel rod production. AFFF has been associated with fuel rod fabrication for other research purposes in the past.
He entered the University of Wisconsin–Madison in 1967 and received his PhD degree in nuclear engineering two years later. In 1969, he joined Argonne National Laboratory as a researcher, working in the area of energy and environmental systems, including Liquid Metal Fast Breeder Reactor safety research, and electric hybrid vehicle development. More than one hundred technical reports and articles had been published before his early retirement in 1996.
Spent fuel is processed at facilities in Trombay near Mumbai, at Tarapur on the west coast north of Mumbai, and at Kalpakkam on the southeast coast of India. Plutonium will be used in a fast breeder reactor (under construction) to produce more fuel, and other waste vitrified at Tarapur and Trombay. Interim storage for 30 years is expected, with eventual disposal in a deep geological repository in crystalline rock near Kalpakkam.
Decisions about the 2012 budget would be taken after the discussions in a panel of cabinet members about the nuclear policy of Japan, including the fast breeder reactor project, would be complete.NHK-world (20 November 2011) Govt panel seeks to revise nuclear projects Reports in 2012 indicated that plans to generate electricity at Monju would be abandoned, and the plant repurposed into a research centre for handling spent nuclear fuel. On 29 May 2013, the NRA announced that JAEA was prohibited from restarting the fast breeder reactor, describing the safety culture at the plant as "deteriorated", because the problems at the plant were not addressed, and the staff were aware of the delayed inspections. The NRA said that before it could plan a restart of the reactor, JAEA must allocate appropriate funds and human resources to rebuild a maintenance and management system to prevent the recurrence of coolant leakages and other problems.
Rather, an excess of fuel is inserted with reactivity control mechanisms, such that the reactivity control is inserted fully at the beginning of life to bring the reactor from supercritical to critical; as the fuel is depleted, the reactivity control is withdrawn to support continuing fission. In a fast breeder reactor, the above applies, though the reactivity from fuel depletion is also compensated by breeding either or and from thorium-232 or , respectively.
Robert Hurst, (3 January 1915 – 16 May 1996) was a New Zealand-born scientist. He was the first director of the experimental fast-breeder reactor complex at Dounreay, and later the director of the British Ship Research Association. During World War II he worked in bomb disposal and mine detection, and was awarded the George Medal for his work as part of the team that defused the first V-1 flying bomb found intact in Britain.
A cutaway model of the reactor. The core, that is the nuclear fuel at the heart of the reactor has dimensions of 2 meters in height by 0.75 meters in diameter, similar to the BN-800 reactor. Main building of Beloyarsk Nuclear Power Station as seen from the Beloyarskoye Reservoir near Zarechny, Sverdlovsk Oblast, Russia. Beloyarsk has the largest fast breeder reactor, the (BN-600), at 600 MW it is the most powerful breeder in the world.
In Koriyama, Fukushima, 16,000 people called for the end of nuclear power. In Shizuoka Prefecture, 1,100 people appealed for the scrapping of the Hamaoka Nuclear Power Plant. In Tsuruga, Fukui, 1,200 people marched in the streets of the city of Tsuruga, the home of the Monju fast-breeder reactor prototype and other nuclear reactors. In Nagasaki and Hiroshima, anti-nuclear protesters and atomic-bomb survivors marched together and demanded that Japan should end its nuclear dependency.
He removed the initial problems and raised the reactor power in steps, after commissioning of all the systems. The reactor was connected to the grid and electricity was generated in July 1997 at 10 MW power. In September 2002 the indigenously designed and fabricated fuel reached a burn up of 100,000 MWd/t without any failure. In 1985, he was designated as the Head of Nuclear Systems Division and was responsible for the preliminary design of 500 MWe Prototype Fast Breeder Reactor (PFBR).
When the project for the subsequent full-scale power-plant prototype Superphénix was started in 1986, it was generally felt that no more experimental FBT prototypes were needed. Superphénix demonstrated very poor reliability and had a historical capacity factor less than 7%. Many of these problems were solved over time, and by 1996 the prototype was reaching its design operational goals. The Russian BN-600 reactor is a similar sodium- cooled fast breeder reactor, built at the Beloyarsk Nuclear Power Station, in Russia.
It was renamed as Indira Gandhi Centre for Atomic Research (IGCAR) by the then Prime Minister of India, Rajiv Gandhi in December 1985. The centre is engaged in broad-based multidisciplinary programme of scientific research and advanced engineering directed towards the development of Fast Breeder Reactor technology, in India. The present Director of IGCAR is A. K. Bhaduri. He has taken over as Director with effect from 1 July 2016, following the superannuation of Dr. S. A. V. Satya Murty.
The BN-800 is an updated version of the BN-600, and started operation in 2014. The Phénix breeder reactor in France was powered down in 2009 after 36 years of operation. Both China and India are building breeder reactors. The Indian 500 MWe Prototype Fast Breeder Reactor is in the commissioning phase, with plans to build more. Another alternative to fast breeders are thermal breeder reactors that use uranium-233 bred from thorium as fission fuel in the thorium fuel cycle.
Cook mainly dealt with the development of new reactors. A number of types were developed, including the Advanced Gas-Cooled Reactor (AGR) at Windscale, considered a natural successor to the Magnox reactors; the Fast Breeder Reactor (FBR) at Dounreay; the high-temperature Dragon reactor at Winfrith. In addition, under the 1958 US–UK Mutual Defence Agreement, the Royal Navy received access to Pressurized Water Reactor (PWR) technology used in US nuclear submarines. He was elected a fellow of the Royal Society in 1962.
Chen studied nuclear engineering at National Tsing Hua University and completed a doctorate in the subject at Iowa State University in 1983. His dissertation was titled Simulation of plenum thermo-hydraulics in a liquid metal fast breeder reactor under a buoyancy-affected condition. Chen worked for Argonne National Laboratory and General Electric before serving as president and chief executive officer of Macromicro Technology. He served on the Legislative Yuan in Taiwan between 2005 and 2008, as a representative of overseas Chinese affiliated with the Democratic Progressive Party.
Construction of a second breeder reactor, the BN-800 reactor, is completed. The BN-600 reactor is a sodium-cooled fast breeder reactor, built at the Beloyarsk Nuclear Power Station, in Zarechny, Sverdlovsk Oblast, Russia. Designed to generate electrical power of 600 MW in total, the plant dispatches 560 MW to the Middle Urals power grid. It has been in operation since 1980 and represents an evolution on the preceding BN-350 reactor. In 2014, its larger sister reactor, the BN-800 reactor began operation.
In 1966, ETEC began as the Liquid Metals Engineering Center (LMEC). The LMEC was created by the U.S. Atomic Energy Commission to provide development and non-nuclear testing of liquid metal reactor components. The Liquid Metals Information Center (LMIC) was established at the same time by the AEC. The LMIC served as a technical information library relating to liquid metals and liquid metal components for the United States government. Both the LMEC and LMIC supported the United States Government’s Liquid Metal Fast Breeder Reactor program.
The BN-1200 reactor is a sodium-cooled fast breeder reactor project, under development by OKBM Afrikantov in Zarechny, Russia. The BN-1200 is based on the earlier BN-600 and especially BN-800, with which it shares a number of features. The reactor's name comes from its electrical output, nominally 1220 MWe. Originally part of an aggressive expansion plan including as many as eight BN-Reactors starting construction in 2012, plans for the BN-1200 were repeatedly scaled back until only two were ordered.
Unit 1 of the Higashidori plant is now scheduled to begin operating in December 2015, while unit 2 will start up in 2018 at the earliest. As of September 2008, Japanese ministries and agencies were seeking an increase in the 2009 budget by 6%. The total requested comes to 491.4 billion Japanese yen (US$4.6 billion), and the focuses of research are development of the fast breeder reactor cycle, next- generation light water reactors, the Iter project, and seismic safety.NucNet. Japan Budget Proposals Seek Increase In Nuclear Spending .
ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) was a proposal for a 600 MW sodium-cooled fast breeder reactor (Generation IV), proposed by the Commissariat à l'énergie atomique (CEA). It was to be built on the Marcoule Nuclear Site in France. It was the successor of the three French fast reactors Rapsodie, Phénix and Superphénix. The main goals of ASTRID were the multi-recycling of plutonium, aiming at preserving natural uranium resources, minor actinide transmutation, aiming at reducing nuclear waste, and an enhanced safety comparable to Generation III reactors, such as the EPR.
Superphénix () or SPX was a nuclear power station prototype on the Rhône river at Creys-Malville in France, close to the border with Switzerland. Superphénix was a 1,242 MWe fast breeder reactor with the twin goals of reprocessing nuclear fuel from France's line of conventional nuclear reactors, while also being an economical generator of power on its own. Construction began in 1974 but suffered from a series of cost overruns, delays and enormous public protests. Construction was complete in 1981, but the plant was not connected to the grid until December 1986.
In June 1997, one of the first actions of Lionel Jospin on becoming Prime Minister was to announce the closure of the plant "because of its excessive costs". As Jospin's government included Green ministers, pro-nuclear critics argued that Jospin's decision was motivated by political motives. Superphénix was the last fast breeder reactor operating in Europe for electricity production. According to a 1996 report by the French Accounting Office (Cour des Comptes), the total expenditure on the reactor to date was estimated at 60 billion francs (9.1 billion euro).
Aerial shot ~1979. PFR in centreground, DFR 'sphere' top right Dounreay Nuclear Power Development Establishment was formed in 1955 primarily to pursue the UK Government policy of developing civil fast breeder reactor (FBR) technology. The site was operated by the United Kingdom Atomic Energy Authority (UKAEA). Three nuclear reactors were built there by the UKAEA, two of them FBRs plus a thermal research reactor used to test construction materials subject to high radiation levels for the programme, and also fabrication and reprocessing facilities for the materials test rigs and for fuel for the FBRs.
Despite its intention to close the Monju facility, the Cabinet appeared to reaffirm its commitment to a fast breeder program of some kind, essential if Japan's stockpile of some 50 tonnes of plutonium is to be disposed of. Jōyō is a test fast breeder reactor located in Ōarai, Ibaraki. The reactor was built in the 1970s for the purpose of experimental tests and the development of FBR technologies. The successor to Monju was expected to be a larger demonstration plant to be completed around 2025, built by the newly formed Mitsubishi FBR Systems company.
Diversification of the site was started in the 1970s with the creation of the Phénix prototype fast breeder reactor, which was operational until 2009, and is nowadays an important site for decommissioning nuclear facilities activities. the Phénix reactor was planned to be succeeded by the sodium-cooled fast reactor ASTRID (Advanced Sodium Technical Reactor for Industrial Demonstration), foreseen to become operational in the 2030s. However in 2019 the ASTRID project was closed. Since 1995, the MELOX factory has been producing MOX from a mix of uranium and plutonium oxides.
The LMEC and the LMIC were established within a western portion of Santa Susana Field Laboratory called Area IV. In 1978, the LMEC charter was expanded to include general energy-related technology and the center was renamed the Energy Technology Engineering Center. Research and development at ETEC primarily involved metallic sodium because the proposed Fast Breeder Reactor required liquid sodium to operate. Sodium was chosen because it has desirable heat transfer properties, a low operating pressure when compared to water, and sodium has a relatively low melting point.
Plutonium is fissionable with both fast and thermal neutrons, which make it ideal for either nuclear reactors or nuclear bombs. Most reactor designs in existence are thermal reactors and typically use water as a neutron moderator (moderator means that it slows down the neutron to a thermal speed) and as a coolant. But in a fast breeder reactor, some other kind of coolant is used which will not moderate or slow the neutrons down much. This enables fast neutrons to dominate, which can effectively be used to constantly replenish the fuel supply.
Intermediate-energy neutrons have poorer fission/capture ratios than either fast or thermal neutrons for most fuels. An exception is the uranium-233 of the thorium cycle, which has a good fission/capture ratio at all neutron energies. Fast-neutron reactors use unmoderated fast neutrons to sustain the reaction and require the fuel to contain a higher concentration of fissile material relative to fertile material U-238. However, fast neutrons have a better fission/capture ratio for many nuclides, and each fast fission releases a larger number of neutrons, so a fast breeder reactor can potentially "breed" more fissile fuel than it consumes.
Pressurized Heavy Water Reactor (PHWR) construction in Kakrapur, Gujarat, during Basu's term as the secretary at the DEA. As the secretary of the Department of Atomic Energy (DAE) between 2015 and 2018, Basu supported initiatives to accelerate the pace of nuclear power deployment in India. In May 2017, the Government of India gave its approval to DAE's plan for construction of 10 pressurized heavy-water reactors (PHWRs) and two pressurized water reactors (PWRs). In this period, the DAE took pm simultaneous construction of 21 reactors, with the Prototype Fast Breeder Reactor (PFBR) at Kalpakkam being in advanced stages of commissioning.
Hurst returned to Cambridge after the war to complete his PhD in physical chemistry. In 1948 he joined the Atomic Energy Research Establishment at Harwell, working first on the chemistry of plutonium, before heading a team that investigated the potential of different types of nuclear reactors. In 1957, he was appointed chief chemist at the Atomic Energy Authority Industrial Research and Development branch at Risley, Cheshire, and in 1958 he was named as the first director of the Dounreay experimental fast- breeder reactor complex. In 1963, Hurst left Dounreay to take up the directorship of the British Ship Research Association.
Another issue was the high cost of building and operating breeder reactors to produce electricity. In 1981, it was estimated that construction costs for a fast breeder reactor would be twice the cost of building a conventional light-water nuclear reactor of similar capacity. That same year it was estimated that the market price of mined, processed uranium, then $25 per pound, would have to increase to nearly $165 per pound in 1981 dollars before the breeder would become financially competitive with the conventional light-water nuclear reactor. United States electric utility companies were reluctant to invest in such an expensive technology.
The dual fluid reactor (DFR) is a reactor concept of a private German research institute, the Institute for Solid-State Nuclear Physics. Combining the advantages of the molten salt reactor with those of the liquid metal cooled reactor, it is supposed to reach the criteria for reactors of the Generation IV International Forum. The fuel is a molten solution of actinide chloride salts, while the cooling is provided by molten lead in a separate loop. As a fast breeder reactor, the DFR can use both natural uranium and thorium to breed fissile material, as well as recycle High-level waste and plutonium.
Reprocessing Development Laboratory was designed in early seventies and the commissioning of inactive facilities was carried out in 1976. The plutonium handling facilities were cleared for operation in 1980. The reprocessing of irradiated thorium rods which was carried out during the period 1989 to 1992 in the concrete shielded cells, was the first major radioactive operation. The U-233 recovered during the operation was used in fabricating the fuel for the KAlpakkam MINI reactor (KAMINI). U-233 was also useful for the fuel development programme for carrying out the Prototype Fast Breeder Reactor test fuel irradiation experiments in Fast Breeder Test Reactor.
Currently, the Board consists of a full-time Chairman, an ex officio Member, three part-time Members and a Secretary. AERB is supported by the Safety Review Committee for Operating Plants (SARCOP), Safety Review Committee for Applications of Radiation (SARCAR) and Advisory Committees for Project Safety Review (ACPSRs) (e.g. Pressurized heavy-water reactor, light water reactor, Prototype Fast Breeder Reactor and waste management projects). ACPSRs recommend to AERB issuance of authorisations at different stages of a plant of the Department of Atomic Energy (DAE), after reviewing the submissions made by the plant authorities based on the recommendations of the associated Design Safety Committees.
Dr. Clifford Dalton (1916-1961) was a New Zealand nuclear scientist and inventor of the fast breeder reactor. During the Second World War in 1942 he married scientist and author Catherine Graves (daughter of the writer Robert Graves) at Aldershot Register Office in Manor Park. Peter J. Conradi, A Very English Hero: The Making of Frank Thompson, Bloomsbury Publishing Plc, London (2012) - Google Books pg 145 In 1947, he joined the Atomic Energy Research Establishment at Harwell in England. They subsequently emigrated to Australia, where he worked as Engineer-In-Chief of the Australian Atomic Energy Commission. Family.
The Nuclear Power Corporation of India Limited commented in its annual report for 2011 that its biggest challenge is to address public and policymaker perceptions about the safety of nuclear power, particularly after the Fukushima Daiichi nuclear disaster in Japan. In 2011, India had 18 pressurized heavy water reactors in operation, with another four projects launched totalling 2.8 GW capacity. India is in the process of launching its first prototype fast breeder reactor using plutonium-based fuel obtained by reprocessing the spent fuel of first-stage reactors. The prototype reactor is located in Tamil Nadu and has a capacity of 500MW.
His initiatives in these areas are driven by a vision of achieving energy independence through the deployment of advanced nuclear energy systems that may be located close to population centres in our densely populated country. Dr. Sinha has overseen the launch of various important projects of the Department of Atomic Energy including the Kudankulam Nuclear Power Plant. The Prototype Fast Breeder Reactor (PFBR) is under advanced stages of construction in Kalpakkam, India. The foundation stone of the 2800 Megawatt Gorakhpur Nuclear Power Plant or the Gorakhpur Haryana Anu Vidyut Pariyojana (GHAVP) was laid in January 2014.
The Atomic Energy Commission (AEC) replaced the Manhattan Project on January 1, 1947, and on January 1, 1948 it announced that the Argonne National Laboratory would be "focused chiefly on problems of reactor development." Zinn did not seek the additional responsibility, which he realised would divert the Laboratory away from research, and divert him from other responsibilities, such as designing a fast breeder reactor. He even obtained a written assurance from Carroll L. Wilson, the AEC's general manager, that it would not. He was therefore willing to collaborate with Alvin Weinberg to allow the Oak Ridge National Laboratory to remain involved in reactor design.
Zirconium crystal bar and cube During his early years at the DAE, Sundaram was in charge of the production of zirconium, beryllium, titanium, tantalum and other refractory metals and he contributed to the establishment of a production facility at Nuclear Fuel Complex which produced zirconium sponge, niobium and tantalum metal products. He oversaw the project from research to production, including the setting up of a pilot plant. Later, when he moved to IGCAR, he took over the Fast Breeder Test Reactor (FBTR) project and it was during his tenancy as the director, the reactor reached criticality, in 1985. Subsequently, he guided the Prototype Fast Breeder Reactor project until his retirement.
The power plant was located in Aktau (formerly known as Shevchenko in 1964–1992), Kazakhstan, on the shore of the Caspian Sea. Construction of the BN-350 fast breeder reactor began in 1964, and the plant first produced electricity in 1973. In addition to providing power for the city (135 MWe), BN-350 was also used for producing plutonium and for desalination to supply fresh water (120,000 m³ fresh water/day) to the city. The project lifetime of the reactor officially finished in 1993, and in June 1994, the reactor was forced to shut down because of a lack of funds to buy fuel.
Suzuki (born 1942) was an authority on the nuclear fuel cycle, and became President of the JAEA in August 2010. Before this he was a professor at the University of Tokyo and the chairman of the former Nuclear Safety Commission. Yonezo Tsujikura, vice president of the JAEA, served as acting president until a successor was chosen.The Mainichi Shimbun (17 May 2013) Head of operator of trouble-plagued fast-breeder reactor resigns At the end of the fiscal year 2011, a budget of was requested to continue the Monju project. This money would cover the costs of maintenance and the costs of the test run, planned in the summer of 2012.
Certain fast breeder reactor designs may be more susceptible to meltdown than other reactor types, due to their larger quantity of fissile material and the higher neutron flux inside the reactor core. Other reactor designs, such as Integral Fast Reactor model EBR II,Integral fast reactor had been explicitly engineered to be meltdown-immune. It was tested in April 1986, just before the Chernobyl failure, to simulate loss of coolant pumping power, by switching off the power to the primary pumps. As designed, it shut itself down, in about 300 seconds, as soon as the temperature rose to a point designed as higher than proper operation would require.
During its construction, a total of 3.8 lakh (380,000) railway sleeper (logs) were brought from all over India to lift the 180 ton critical equipment in the first unit, due to lack of proper infrastructure and handling equipment. the Prototype Fast Breeder Reactor (PFBR) was in its final construction stage, and was expected to reach criticality in March 2017 with 500 MW of electricity production. The following month the loading of the 1750 ton liquid sodium coolant were expected to happen in four to five months, with sources in the Department of Atomic Energy reporting that criticality would likely be reached only around May 2017.
The nuclear fission properties of berkelium are different from those of the neighboring actinides curium and californium, and they suggest berkelium to perform poorly as a fuel in a nuclear reactor. Specifically, berkelium-249 has a moderately large neutron capture cross section of 710 barns for thermal neutrons, 1200 barns resonance integral, but very low fission cross section for thermal neutrons. In a thermal reactor, much of it will therefore be converted to berkelium-250 which quickly decays to californium-250.G. Pfennig, H. Klewe-Nebenius, W. Seelmann Eggebert (Eds.): Karlsruhe nuclide, 7 Edition, 2006 In principle, berkelium-249 can sustain a nuclear chain reaction in a fast breeder reactor.
Georges Vendryes (1920 – 16 September 2014) was a French physicist who played a significant role in the French nuclear industry and is considered the "father" of fast breeder reactor technology, for which he received the Enrico Fermi Prize and Japan Prize. Vendryes studied at the École Polytechnique and the École des Ponts et Chaussées and received his doctorate in nuclear physics at the Sorbonne. From 1948 he was employed by the French nuclear research authority CEA, where he made his first experiments under Frédéric Joliot- Curie. At the CEA he worked on neutron transport experiments and research and development of different type of reactors including controlled thermonuclear fusion.
For ten years, Nissim, believing that fast breeder reactor "can explode with their fast neutrons","les surgénérateurs comme Creys-Malville, qui, avec leurs neutrons rapides, peuvent faire explosion" did everything he could to stop the construction of the Superphénix nuclear plant, including training himself for underground guerilla, notably sabotaging electricity pylons with explosives. On 18 January 1982, Nissim fired five rockets on the Superphénix nuclear plant, then under construction. Five rocket-propelled grenades were launched at the incomplete containment building – two hit and caused damage, missing the reactor's empty core. The weapon, a RPG-7, was obtained from the Red Army Faction through Carlos the Jackal and the Belgian Cellules Communistes Combattantes.
India published about twice the number of papers on thorium as its nearest competitors, during each of the years from 2002 to 2006. The Indian nuclear establishment estimates that the country could produce 500 GWe for at least four centuries using just the country's economically extractable thorium reserves. , India's first Prototype Fast Breeder Reactor had been delayed – with first criticality expected in 2015 – and India continued to import thousands of tonnes of uranium from Russia, Kazakhstan, France, and Uzbekistan. The 2005 Indo–US Nuclear Deal and the NSG waiver, which ended more than three decades of international isolation of the Indian civil nuclear programme, have created many hitherto unexplored alternatives for the success of the three-stage nuclear power programme.
In a thermal neutron spectrum, the concentrations of several heavy actinides (curium-242 and plutonium-240) can become quite high, creating fuel that is substantially different from the usual uranium or mixed uranium-plutonium oxides (MOX) that most current reactors were designed to use. Another pyrochemical process, the PYRO-B process, has been developed for the processing and recycling of fuel from a transmuter reactor ( a fast breeder reactor designed to convert transuranic nuclear waste into fission products ). A typical transmuter fuel is free from uranium and contains recovered transuranics in an inert matrix such as metallic zirconium. In the PYRO-B processing of such fuel, an electrorefining step is used to separate the residual transuranic elements from the fission products and recycle the transuranics to the reactor for fissioning.
His work for the Department of Atomic Energy (DAE) was mainly concerned with the physical and mechanical metallurgy aspects (deformation, fracture, stress corrosion cracking and low cycle fatigue) of AISI 304, 304 LN, 316 and 316 LN austenitic stainless steels and an improved grade D9, all construction materials for the Fast Breeder Reactor program. He was a consultant to the R & D Centre for Iron and Steel, Steel Authority of India Limited (SAIL), when they produced for the first time in the country both Extra Deep Drawing (EDD) and Liquid Petroleum Gas (LPG) grades of steel. He was a consultant to Tata Engineering and Locomotive Company (now known as Tata Motors) when they introduced the micro-alloyed ferrite - pearlite steel (first generation), 49MnVS3, for the first time in India for the forging of crankshafts.
Nonetheless, reactor research accounted for almost half the laboratory's budget in 1949, and 84 percent of its research was classified. Zinn did not get along well with Captain Hyman G. Rickover, the US Navy's Director of Naval Reactors, but nonetheless Argonne assisted in the development of nuclear marine propulsion, eventually producing two reactors, a land-based prototype Mark I and a propulsion reactor, the Mark II. The STR (Submarine Thermal Reactor) pressurized water reactor designed at Argonne powered the first nuclear- powered submarine, , and became the basis of nearly all the reactors installed in warships. The other branch of reactor development at the Argonne National Laboratory, and the one closer to Zinn's heart, was the fast breeder reactor. At the time it was believed that uranium was a scarce resource, so it would be wise to make the best use of it.
In 1965 he was appointed vice president of Union Carbide's Nuclear Division. In a 1971 paper, Weinberg first used the term "Faustian bargain" to describe nuclear energy: Weinberg was fired by the Nixon administration from ORNL in 1973 after 18 years as the laboratory's director, because he continued to advocate increased nuclear safety and molten salt reactors (MSRs), instead of the Administration's chosen Liquid Metal Fast Breeder Reactor (LMFBR) that the AEC's Director of Reactor Division, Milton Shaw, was appointed to develop. Weinberg's firing effectively halted development of the MSR, as it was virtually unknown by other nuclear laboratories and specialists. There was a brief revival of MSR research at ORNL as part of the Carter administration's nonproliferation interests, culminating in ORNL-TM-7207, "Conceptual Design Characteristics of a Denatured Molten-Salt Reactor with Once-Through Fueling", by Engel, et al.
June 18, 2009 S-PRISM is a commercial implementation of the Integral Fast Reactor developed by Argonne National Laboratory between 1984 and 1994. It is a sodium-cooled fast breeder reactor, based on the Experimental Breeder Reactor II (EBR-II) design, scaled up by a factor of ten. The design utilizes reactor modules, each having a power output of 311 MWe, to enable factory fabrication at low cost. In an identical fashion to the EBR-II that it is based on, the reactor would transition to a much lower power level whenever temperatures rise significantly, moreover the reactor vessel modules are pool type, as opposed to loop type, with the pool conferring substantial thermal inertia and the final key safety feature includes a "RVACS", which is a passive reactor vessel air cooling system to remove decay heat.
In September 2011 the ministry of education, science and technology asked for the fiscal year of 2012 only 20 to 30 percent of the budget to maintain and manage the Monju reactor for the year 2011. The uncertainty about Japan's future energy policy caused the ministry to conclude that the project could not proceed.JAIF (26 September 2011) Earth-quake-report 217: Japan to freeze fast-breeder reactor project The test run of the reactor, in which the reactor's output would be raised to 40 percent of its capacity by the end of March 2012, was postponed on September 29, 2011, by the Japanese Government because the uncertainty over the future of nuclear energy. After the disaster in Fukushima, the Atomic Energy Commission of Japan made a start with a review of Japan's long term energy policy.
Because the Mihama Nuclear Power Plant and the Monju fast breeder reactor could also be affected by a possible earthquake caused by the Urazoko fault.The Mainichi Shimbun (7 March 2012) Quake severity estimate for Tsuruga nuclear plant to be reassessed On 17 July 2013 a commission of five experts led by NRA commissioner Kunihiko Shimazaki started the investigations on the geological activity of 8 zones of crushed rock under the reactor. Whether these old faults could move in conjunction with the active fault situated half a kilometer from the reactor site, and would constitute a hazard for the reactor safety. One of the experts, Chiba University professor Takahiro Miyauchi,The Mainichi Shimbun (19 July 2013) Govt's nuclear fuel cycle policy teeters on edge as onsite Monju inspection completed did not take part in the two-day survey, but would visit the site afterwards.
Retrieved 10 December 2011. As an alternative to electrowinning, the wanted metal can be isolated by using a molten alloy of an electropositive metal and a less reactive metal.Ionic Liquids/Molten Salts and Lanthanides/Actinides Reference List. Merck.de. Retrieved 10 December 2011. Since the majority of the long term radioactivity, and volume, of spent fuel comes from actinides, removing the actinides produces waste that is more compact, and not nearly as dangerous over the long term. The radioactivity of this waste will then drop to the level of various naturally occurring minerals and ores within a few hundred, rather than thousands of, years. The mixed actinides produced by pyrometallic processing can be used again as nuclear fuel, as they are virtually all either fissile, or fertile, though many of these materials would require a fast breeder reactor in order to be burned efficiently.
During the time that AESD was active, the Large site also housed the Westinghouse Fusion Power Systems Department (FPSD), which had a role in development and startup of the Tokamak Reactor at the Princeton Plasma Physics Laboratory (PPPL) in 1982. Along with the Advanced Coal Conversion Department (ACCD) and Advanced Reactors Division (ARD), AESD and FPSD constituted the Company's Advanced Power Systems Business Unit (APSBU), which was based at the Company's Waltz Mill Site in Madison, Pennsylvania, along I-70 a few miles west of the New Stanton interchange of the Pennsylvania Turnpike (I-76). ACCD operated a coal gasification process demonstration unit (PDU), which was funded by DoE in the early 1970s, and conducted related research projects. ARD had the development contract for the planned Liquid Metal Fast Breeder Reactor (LMFBR) project at Clinch River, Tennessee, near the Oak Ridge National Laboratory.
The surplus plutonium bred in each fast reactor can be used to set up more such reactors, and might thus grow the Indian civil nuclear power capacity till the point where the third stage reactors using thorium as fuel can be brought online, which is forecasted as being possible once 50 GW of nuclear power capacity has been achieved. The uranium in the first stage PHWRs that yield 29 EJ of energy in the once- through fuel cycle, can be made to yield between 65 and 128 times more energy through multiple cycles in fast breeder reactors. The design of the country's first fast breeder, called Prototype Fast Breeder Reactor (PFBR), was done by Indira Gandhi Centre for Atomic Research (IGCAR). Bharatiya Nabhikiya Vidyut Nigam Ltd (Bhavini), a public sector company under the Department of Atomic Energy (DAE), has been given the responsibility to build the fast breeder reactors in India.
Heysham nuclear power stations Britain's fleet of operational reactors consists of 14 advanced gas-cooled reactors at six discrete sites and one PWR unit at Sizewell B. The total installed nuclear capacity in the United Kingdom is about 9 GW. In addition, the UK experimented with Fast Breeder reactor technologies at Dounreay in Scotland; however the last fast breeder (with 250MWe of capacity) was shut down in 1994. Even with changes to the planning system to speed nuclear power plant applications, there are doubts over whether the necessary timescale could be met to increase nuclear power output, and over the financial viability of nuclear power with present oil and gas prices. With no nuclear plants having been constructed since Sizewell B in 1995, there are also likely to be capacity issues within the native nuclear industry. The existing privatised nuclear supplier, British Energy, had been in financial trouble in 2004.
According to the United States Nuclear Regulatory Commission, there was no abnormal radioactivity released into the environment.NRC "Fermi, Unit 1", NRC Website, 3 February 2011, accessed 17 March 2011. Fermi 1 was a liquid metal (sodium) cooled fast breeder reactor design. It was capable of producing 200 megawatts thermal (MWt) power or 69 MW electrical power with 26% enriched metallic uranium fuel. The enriched uranium section of the reactor (core) was a 30 inch in diameter cylinder by 30 inches high and contained 92 fuel assemblies. The core was surrounded by 548 additional assemblies containing depleted uranium. These assemblies were about 2.5 inches square by about 8 feet tall. Only the core section contained the enriched uranium while depleted uranium was placed above and below within the assemblies. The core also contained 2 control rods and 8 safety rods. The plant was designed for 430 MWt and 125 MWe using a newer uranium oxide fuel, but the plant was closed before the fuel was ever ordered.
Calder Hall power station was first connected to the national power grid on 27 August 1956 Nuclear capacity (red) as a proportion of total generating capacity, 1955–2016 The United Kingdom Atomic Energy Authority (UKAEA) was established in 1954 as a statutory corporation to oversee and pioneer the development of nuclear energy within the United Kingdom. The first station to be connected to the grid, on 27 August 1956, was Calder Hall, although the production of weapons-grade plutonium was the main reason behind this power station. Calder Hall was the world's first nuclear power station to deliver electricity in commercial quantities (although the 5 MW "semi-experimental" reactor at Obninsk in the Soviet Union was connected to the public supply in 1954). In February 1966 it was announced that the first prototype fast breeder reactor in the United Kingdom would be constructed in Dounreay, Scotland, at a cost of £30 million. British Nuclear Fuels Limited (BNFL) was established in February 1971 from the demerger of the production division of the UK Atomic Energy Authority (UKAEA). In 1984 BNFL became a public limited company, British Nuclear Fuels plc, wholly owned by the UK government.

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