RITM-200
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RITM-200
The RITM-200 is an integrated generation 3+ pressurized water reactor developed by OKBM Afrikantov and designed to produce 55 MWe. The design is an improvement of KLT-40 reactor. It uses up to 20% enriched uranium-235 and can be refueled every 10 years for a 60 year planned lifespan in floating power plant installation. If installed in a stationary power plant the fuel cycle is 6 years. The RITM-200 has a compact integrated layout placing equipment within the steam generator casing, halving system weight compared to earlier designs and improving ability to operate in rolling and pitching seas. It powers the Project 22220 icebreakers, the first of which went critical in October 2019. In November 2020 Rosatom announced plans to place a land-based RITM-200N SMR in isolated Ust-Kuyga town in Yakutia. The reactor will replace current coal and oil based electricity and heat generation at half the price. Technical design for this type of RITM-200 core should be finished in 2022. Re ...
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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 ...
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Project 22220 Icebreaker
Project 22220, also known through the Russian type size series designation LK-60Ya,The type size series designation "LK-60Ya" (russian: ЛК-60Я) comes from the Russian language word for "icebreaker" (russian: text=ледокол, translit=ledokol), propulsion power (60 megawatts), and the first letter of the Russian word for "nuclear" (russian: text=ядерное, translit=yadernoye). is a series of Russian nuclear-powered icebreakers. The lead ship of the class, ''Arktika'', was delivered in 2020 and surpassed the preceding Soviet-built series of nuclear-powered icebreakers as the largest and most powerful icebreaker in the world. , three Project 22220 icebreakers (''Arktika'', ''Sibir'' and ''Ural'') are in service, fourth ( ''Yakutiya'') has been launched, fifth ( ''Chukotka'') has been laid down at Baltic Shipyard in Saint Petersburg, and a sixth and seventh are on order. Development LK-60Ya After the Second World War, the Soviet Union launched an ambitious marine ...
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KLT-40 Reactor
The KLT-40 family are nuclear fission reactors originating from OK-150 and OK-900 ship reactors. KLT-40 were developed to power the ''Taymyr''-class icebreakers (KLT-40M, 171 MW) and the LASH carrier '' Sevmorput'' (KLT-40, 135 MW).Nuclear icebreakers
. Bellona Foundation, 18 June 1997.
They are s (PWR) fueled by either 30–40% or 90%90 % according to information provided to Norwegian government in 1990, 30–40 % according to

Soviet Naval Reactors
Soviet naval reactors have been used to power both military and civilian vessels, including: * Nuclear submarines: ** Attack submarines. ** Cruise missile submarines. ** Ballistic missile submarines. * Nuclear icebreakers: ** ** s ** s * Russian floating nuclear power stations: ** * Nuclear cruisers: ** s * Merchant ship: ** * Command ship: ** ''SSV-33 Ural'' They have included both pressurized water reactors and a relatively few liquid metal fast reactors. OKBM Afrikantov has been the primary designer of naval reactors for the Soviet/Russian Navy for more than 60 years. Reactor types '**'KPM-6 is developed by OKBM Afrikantov. See also * List of commercial nuclear reactors * List of United States Naval reactors List of United States Naval reactors is a comprehensive annotated list of all naval reactors designed, built, or used by the United States Navy. Reactor designations Each nuclear reactor design is given a three-character designation consi ... * N ...
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Pressurized Water Reactor
A pressurized water reactor (PWR) is a type of light-water nuclear reactor. PWRs constitute the large majority of the world's nuclear power plants (with notable exceptions being the UK, Japan and Canada). In a PWR, the primary coolant (water) is pumped under high pressure to the reactor core where it is heated by the energy released by the fission of atoms. The heated, high pressure water then flows to a steam generator, where it transfers its thermal energy to lower pressure water of a secondary system where steam is generated. The steam then drives turbines, which spin an electric generator. In contrast to a boiling water reactor (BWR), pressure in the primary coolant loop prevents the water from boiling within the reactor. All light-water reactors use ordinary water as both coolant and neutron moderator. Most use anywhere from two to four vertically mounted steam generators; VVER reactors use horizontal steam generators. PWRs were originally designed to serve as nuclea ...
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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 reac ...
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Light-water Reactor
The light-water reactor (LWR) is a type of thermal-neutron reactor that uses normal water, as opposed to heavy water, as both its coolant and neutron moderator; furthermore a solid form of fissile elements is used as fuel. Thermal-neutron reactors are the most common type of nuclear reactor, and light-water reactors are the most common type of thermal-neutron reactor. There are three varieties of light-water reactors: the pressurized water reactor (PWR), the boiling water reactor (BWR), and (most designs of) the supercritical water reactor (SCWR). History Early concepts and experiments After the discoveries of fission, moderation and of the theoretical possibility of a nuclear chain reaction, early experimental results rapidly showed that natural uranium could only undergo a sustained chain reaction using graphite or heavy water as a moderator. While the world's first reactors ( CP-1, X10 etc.) were successfully reaching criticality, uranium enrichment began to develop fr ...
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Water
Water (chemical formula ) is an Inorganic compound, inorganic, transparent, tasteless, odorless, and Color of water, nearly colorless chemical substance, which is the main constituent of Earth's hydrosphere and the fluids of all known living organisms (in which it acts as a solvent). It is vital for all known forms of life, despite not providing food energy, food, energy or organic micronutrients. Its chemical formula, H2O, indicates that each of its molecules contains one oxygen and two hydrogen atoms, connected by covalent bonds. The hydrogen atoms are attached to the oxygen atom at an angle of 104.45°. "Water" is also the name of the liquid state of H2O at standard temperature and pressure. A number of natural states of water exist. It forms precipitation in the form of rain and aerosols in the form of fog. Clouds consist of suspended droplets of water and ice, its solid state. When finely divided, crystalline ice may precipitate in the form of snow. The gaseous state of ...
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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 r ...
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Pressurized Water Reactor
A pressurized water reactor (PWR) is a type of light-water nuclear reactor. PWRs constitute the large majority of the world's nuclear power plants (with notable exceptions being the UK, Japan and Canada). In a PWR, the primary coolant (water) is pumped under high pressure to the reactor core where it is heated by the energy released by the fission of atoms. The heated, high pressure water then flows to a steam generator, where it transfers its thermal energy to lower pressure water of a secondary system where steam is generated. The steam then drives turbines, which spin an electric generator. In contrast to a boiling water reactor (BWR), pressure in the primary coolant loop prevents the water from boiling within the reactor. All light-water reactors use ordinary water as both coolant and neutron moderator. Most use anywhere from two to four vertically mounted steam generators; VVER reactors use horizontal steam generators. PWRs were originally designed to serve as nuclea ...
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Uranium-235
Uranium-235 (235U or U-235) is an isotope of uranium making up about 0.72% of natural uranium. Unlike the predominant isotope uranium-238, it is fissile, i.e., it can sustain a nuclear chain reaction. It is the only fissile isotope that exists in nature as a primordial nuclide. Uranium-235 has a half-life of 703.8 million years. It was discovered in 1935 by Arthur Jeffrey Dempster. Its fission cross section for slow thermal neutrons is about 584.3±1 barns. For fast neutrons it is on the order of 1 barn. Most but not all neutron absorptions result in fission; a minority result in neutron capture forming uranium-236. Natural decay chain :\begin \ce \begin \ce \\ \ce \end \ce \\ \ce \begin \ce \\ \ce \end \ce \end Fission properties The fission of one atom of uranium-235 releases () inside the reactor. That corresponds to 19.54 TJ/ mol, or 83.14 TJ/kg.
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Small Modular Reactor
Small modular reactors (SMRs) are a proposed class of nuclear fission reactors, smaller than conventional nuclear reactors, which can be built in one location (such as a factory), then shipped, commissioned, and operated at a separate site. The term SMR refers to the size, capacity and modular construction only, not to the reactor type and the nuclear process which is applied. Designs range from scaled down versions of existing designs to generation IV designs. Both thermal-neutron reactors and fast-neutron reactors have been proposed, along with molten salt and gas cooled reactor models. SMRs are typically anticipated to have an electrical power output of less than 300 MWe (electric) or less than 1000 MWth (thermal). Many SMR proposals rely on a manufacturing-centric model, requiring many deployments to secure economies of unit production large enough to achieve economic viability. Some SMR designs, typically those using Generation IV technologies, aim to secure additional ...
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