|
BN-800
The BN-800 reactor (Russian: реактор БН–800) is a sodium-cooled fast breeder reactor, built at the Beloyarsk Nuclear Power Station, in Zarechny, Sverdlovsk Oblast, Russia. The reactor is designed to generate 880 MW of electrical power. The plant was considered part of the weapons-grade Plutonium Management and Disposition Agreement signed between the United States and Russia, with the reactor being part of the final step for a plutonium-burner core (a core designed to burn and, in the process, destroy, and recover energy from, plutonium) The plant reached its full power production in August 2016. According to Russian business journal ''Kommersant'', the BN-800 project cost 140.6 billion rubles (roughly 2.17 billion dollars). Design The plant is a pool-type LMFBR, in which the reactor, coolant pumps, intermediate heat exchangers and associated piping are all located in a common liquid sodium pool. This is essentially the same general design as EBR-II, which entered ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Beloyarsk Nuclear Power Station
The Beloyarsk Nuclear Power Station (NPS; russian: Белоярская атомная электростанция им. И. В. Курчатова []) was the third of the Soviet Union, Soviet Union's nuclear plants. It is situated by Zarechny, Sverdlovsk Oblast, Zarechny in Sverdlovsk Oblast, Russia. Zarechny township was created to service the station, which is named after the Beloyarsky District, Sverdlovsk Oblast, Beloyarsky District. The closest city is Yekaterinburg. Early reactors Two earlier reactors were constructed at Beloyarsk: an AMB-100 reactor (operational 1964–1983) and an AMB-200 reactor (operational 1967–1989). Both were supercritical water reactors; the first unit used 67 tons of uranium enriched to 1.8%, while the second unit used 50 tons of uranium enriched to 3.0%. The first unit had an indirect steam cycle, while the second had a direct one. Although they were comparable in power to the Shippingport Atomic Power Station, the Soviet planners regarde ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Breeder Reactor
A breeder reactor is a nuclear reactor that generates more fissile material than it consumes. Breeder reactors achieve this because their neutron economy is high enough to create more fissile fuel than they use, by irradiation of a fertile material, such as uranium-238 or thorium-232, that is loaded into the reactor along with fissile fuel. Breeders were at first found attractive because they made more complete use of uranium fuel than light water reactors, but interest declined after the 1960s as more uranium reserves were found,Helmreich, J.E. ''Gathering Rare Ores: The Diplomacy of Uranium Acquisition, 1943–1954'', Princeton UP, 1986: ch. 10 and new methods of uranium enrichment reduced fuel costs. Fuel efficiency and types of nuclear waste Breeder reactors could, in principle, extract almost all of the energy contained in uranium or thorium, decreasing fuel requirements by a factor of 100 compared to widely used once-through light water reactors, which extract less tha ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Fast Breeder Reactor
A breeder reactor is a nuclear reactor that generates more fissile material than it consumes. Breeder reactors achieve this because their neutron economy is high enough to create more fissile fuel than they use, by irradiation of a fertile material, such as uranium-238 or thorium-232, that is loaded into the reactor along with fissile fuel. Breeders were at first found attractive because they made more complete use of uranium fuel than light water reactors, but interest declined after the 1960s as more uranium reserves were found,Helmreich, J.E. ''Gathering Rare Ores: The Diplomacy of Uranium Acquisition, 1943–1954'', Princeton UP, 1986: ch. 10 and new methods of uranium enrichment reduced fuel costs. Fuel efficiency and types of nuclear waste Breeder reactors could, in principle, extract almost all of the energy contained in uranium or thorium, decreasing fuel requirements by a factor of 100 compared to widely used once-through light water reactors, which extract less tha ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
BN-1200 Reactor
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. The first was to begin construction at the Beloyarsk nuclear power plant in 2015, with initial commissioning in 2017, followed by a second unit at the same location. A possible new station known as South Ural would host another two BN-1200s at some future point. In 2015, after several minor delays, problems at the recently completed BN-800 indicated a redesign of the fuel was needed. Construction of the BN-1200 was put on "indefinite hold", and Rosenergoatom stated that no dec ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Generation III+ Reactor
Generation III reactors, or Gen III reactors, are a class of nuclear reactors designed to succeed Generation II reactors, incorporating evolutionary improvements in design. These include improved fuel technology, higher thermal efficiency, significantly enhanced safety systems (including passive nuclear safety), and standardized designs intended to reduce maintenance and capital costs. They are promoted by the Generation IV International Forum (GIF). The first Generation III reactors to begin operation were Kashiwazaki 6 and 7 advanced boiling water reactors (ABWRs) in 1996 and 1997. Since 2012, both have been shut down due to security concerns. Due to the prolonged period of stagnation in the construction of new reactors and the continued (albeit declining) popularity of Generation II/II+ designs in new construction, relatively few third generation reactors have been built. Overview The older Gen II reactors comprise the vast majority of current nuclear reactors. Gen III rea ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Generation III Reactor
Generation III reactors, or Gen III reactors, are a class of nuclear reactors designed to succeed Generation II reactors, incorporating evolutionary improvements in design. These include improved fuel technology, higher thermal efficiency, significantly enhanced safety systems (including passive nuclear safety), and standardized designs intended to reduce maintenance and capital costs. They are promoted by the Generation IV International Forum (GIF). The first Generation III reactors to begin operation were Kashiwazaki 6 and 7 advanced boiling water reactors (ABWRs) in 1996 and 1997. Since 2012, both have been shut down due to security concerns. Due to the prolonged period of stagnation in the construction of new reactors and the continued (albeit declining) popularity of Generation II/II+ designs in new construction, relatively few third generation reactors have been built. Overview The older Gen II reactors comprise the vast majority of current nuclear reactors. Gen III re ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
BN-600 Reactor
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. The plant is a pool type LMFBR, where the reactor, coolant pumps, intermediate heat exchangers and associated piping are all located in a common liquid sodium pool. This is essentially the same general design as EBR-II, which went into service in 1963. The reactor system is housed in a concrete rectilinear building, and provided with filtration and gas containment features. In the first 15 years of operation, there have been 12 incidents involving sodium/water interactions from tube breaks in the steam generators, a sodium-air oxidation/"fire" ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
MOX Fuel
Mixed oxide fuel, commonly referred to as MOX fuel, is nuclear fuel that contains more than one oxide of fissile material, usually consisting of plutonium blended with natural uranium, reprocessed uranium, or depleted uranium. MOX fuel is an alternative to the low-enriched uranium (LEU) fuel used in the light-water reactors that predominate nuclear power generation. For example, a mixture of 7% plutonium and 93% natural uranium reacts similarly, although not identically, to LEU fuel (3 to 5% uranium-235). MOX usually consists of two phases, UO2 and PuO2, and/or a single phase solid solution (U,Pu)O2. The content of PuO2 may vary from 1.5 wt.% to 25–30 wt.% depending on the type of nuclear reactor. One attraction of MOX fuel is that it is a way of utilizing surplus weapons-grade nuclear material, weapons-grade plutonium, an alternative to storage of surplus plutonium, which would need to be secured against the risk of theft for use in nuclear weapons. On the other hand, some st ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Pool-type LMFBR
A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium. The initials SFR in particular refer to two Generation IV reactor proposals, one based on existing liquid metal cooled reactor (LMFR) technology using mixed oxide fuel (MOX), and one based on the metal-fueled integral fast reactor. Several sodium-cooled fast reactors have been built and some are in current operation, particularly in Russia. Others are in planning or under construction. For example in 2022, in the USA, TerraPower (using its Traveling Wave technology) is planning to build its own reactors along with molten salt energy storage in partnership with GEHitachi's PRISM integral fast reactor design, under the ''Natrium'' appellation in Kemmerer, Wyoming. Aside from the Russian experience, Japan, India, China, France and the USA are investing in the technology. Fuel cycle The nuclear fuel cycle employs a full actinide recycle with two major options: One is an intermediate-size (150–600 ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
OKBM Afrikantov
OKBM Afrikantov (full name: OAO I. I. Afrikantov OKB Mechanical Engineering, russian: Опытное конструкторское бюро машиностроения им. И. И. Африкантова) is a nuclear engineering company located in Nizhny Novgorod, Russia. It is a subsidiary of Rosatom. The company is named after Igor Afrikantov. The company is best known as the main designer for the Soviet Union's and Russia's flagship nuclear propulsion projects, including reactors for nuclear submarines, nuclear-powered icebreakers, and the floating nuclear power plant project. It also designs fast breeder reactors. History The company was founded in 1945. In 1998, it was named after its former chief designer and director I. I. Afrikantov. Products The company is a developer of the nuclear reactors. It has designed and assembled KLT-40S reactors for the first Russian floating nuclear power station ''Akademik Lomonosov''. It also developed the RITM-200 ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Plutonium Management And Disposition Agreement
The Plutonium Management and Disposition Agreement is an agreement between the United States and Russia signed in 2000, wherein both nations agreed to dispose of significant fractions of their "excess" (beyond what they need for their nuclear weapons) weapons-grade plutonium. An amended version was signed in April 2010 and went into effect in July 2011. The US has about 90 tons of weapons-capable plutonium, while Russia has 128 tons. The US declared 60 tons as excess, while Russia declared 50 tons excess. The two sides agreed that each would eliminate 34 tons. The agreement regulates the conversion of non-essential plutonium into mixed oxide (MOX) fuel used to produce electricity. Both sides were required to render 34 tons of weapons grade plutonium, into reactor grade plutonium alongside reaching the ''spent fuel standard'', that is mixed with the other more highly irradiating products within spent fuel. In 2007, the US began constructing the Mixed Oxide Fuel Fabrication Fa ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Waste Isolation Pilot Plant
The Waste Isolation Pilot Plant, or WIPP, is the world's third deep geological repository (after Germany's Repository for radioactive waste Morsleben and the Schacht Asse II salt mine) licensed to store transuranic radioactive waste for 10,000 years. The storage rooms at the WIPP are 2,150 feet (660 m) underground in a salt formation of the Delaware Basin. The waste is from the research and production of United States nuclear weapons only. The plant started operation in 1999, and the project is estimated to cost $19 billion in total. It is located approximately east of Carlsbad, New Mexico, in eastern Eddy County, in an area known as the southeastern New Mexico nuclear corridor, which also includes the National Enrichment Facility near Eunice, New Mexico, the Waste Control Specialists low-level waste disposal facility just over the state line near Andrews, Texas, and the International Isotopes, Inc. facility to be built near Eunice, New Mexico. Various mishaps at the plant i ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
