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The VVER-TOI or WWER-TOI (Russian : Водо-водяной энергетический реактор типовой оптимизированный информатизированный, romanized: Vodo-Vodyanoi Energetichesky Reactor Tipovoi Optimizirovanniy Informatizirovanniy, lit. 'Water-Water Energy Reactor Universal [lower-alpha 1] Optimized Digital [lower-alpha 2] ') is a generation III+ nuclear power reactor based on VVER technology developed by Rosatom. [1] The VVER-TOI design is intended to improve the competitiveness of Russian VVER technology in international markets. It would use VVER-1300/510 water pressurized reactors constructed to meet modern nuclear and radiation safety requirements.
The VVER-TOI project is developed on the basis of the design documents worked out for AES-2006, considering the experience gained in development of projects based on VVER technology both in Russia and abroad, such as Novovoronezh Nuclear Power Plant II. The first VVER-TOI will be unit 1 of the Kursk II Nuclear Power Plant. [2]
The reactor design life is 60 years, with potential of life extension to 100 years, and a thermal capacity of 3300 MWt and a gross electrical capacity of 1300 MWe. [3]
Indicator | Value[ clarification needed ] |
---|---|
Safe Shutdown Earthquake of intensity on MSK-64 scale:
| 8 9 |
Design-Basis Earthquake of intensity on MSK-64 scale | 7 |
Time required to provide self-contained plant operation in case of beyond design basis accident, h | 72 |
Nuclear power plant(NPP) construction term from first concreting until physical starting-up (for serial unit), months | 40 |
Decrease in estimated cost of the serial Unit construction in comparison with the first Unit of Novovoronezh NPP-2, % | 20 |
Decrease in design operation expenditures of the Power Unit in comparison with the fourth Unit of Balakovo NPP, % | 10 |
The radiation safety measures are arranged and implemented to prevent inadmissible impacts caused by ionizing radiation sources on the materials, population and environment in the area that surrounds the Nuclear power plant.
The concept of providing radiation and nuclear safety in VVER-TOI project is based on the following:
VVER-TOI project shows implementation of the following principles ensuring the modern concept of the repetitive defense in depth:
Natural disasters and human-induced impacts specifying site conditions are accepted taking into account possibility of constructing Nuclear power plants with VVER-TOI reactors in various geographical regions, as well as in the regions characterized by different human-induced impacts.
The most important impacts, which parameters affected significantly technical solutions on VVER-TOI project are listed below:
Nuclear power plant systems and components as a part of the base - case project are developed by reference to the following natural disasters and design human-induced impacts:
Modern Nuclear power plants are characterized by the unprecedented low risk of ionizing radiation propagation and radionuclide emission to environment. This result is achieved through the newest protective and localizing technologies of the safety system. The VVER-TOI project shows, as a basis variant, the configuration based on the two channel structure of active safety systems without internal backup, and four channel structure of passive safety systems. The passive safety system provides a 72 hour period requiring no operator intervention. [3]
The profile of the active safety systems is as follows:
The profile of the passive safety systems is as follows:
The accident control facility of the VVER-TOI project includes a core catcher, which provides the guaranteed safety control through melt localizing and cooling in case of a severe accident at the beyond-vessel stage of core-melt localization. Within the frame of VVER-TOI, there are performed the works directed toward optimization of technical solutions made for corium trap project to decrease cost indicators and justify the corium trap operation efficiency. It is supposed to achieve a considerable decrease in the trap vessel overall sizes and sacrificed materials weight, as well as to transfer to module design of the trap vessel that make it possible to simplify transportation of the large-sized equipment to the construction site of a Nuclear power plant.
Combination of passive and active safety systems provided for in the VVER-TOI project ensures that core will not be destroyed for not less than 72 hours from the moment of severe accident happening in case of any possible scenario. The corresponding technical solutions guarantee that reactor plant will be transferred to safe conditions at any combination of initial events (natural and human-induced) triggering to loss of all the electric power sources. This fact increases considerably the project competitiveness both in foreign and domestic markets of electric power production. [4]
Framatome is supplying reactor protection systems for the VVER-TOI reactors at Kursk II. [5]
The VVER-TOI reactor pressure vessel has fewer welds than the VVER-1200, all out of the central area, and a more symmetric arrangement of coolant nozzles. This gives the potential for two 20 year life extensions, which could give a 100 year life. [3]
VVER-TOI is a basis for the development of Nuclear power plant serial construction projects at the sites located within a wide range of natural-climatic conditions, considering the whole spectrum of internal extreme and external human-induced impacts, which are specific for all eventual construction sites. The project is developed to the intent that its application in individual Nuclear power plant projects would not require change of the main conceptual, engineering and layout solutions, as well as additional safety analysis and other justifying documents to be submitted to the state supervisory authorities for receiving construction licenses.
VVER-TOI power unit circuits, equipment, systems and structures design make it possible to upgrade it allowing for:
Virtual Prototyping Center is a complex of soft-and-hardware facilities making it possible to visualize design and engineering models. It represents a 6-metre-diameter (20 ft) sphere, in which center attendance being at 2-metre (6.6 ft) height at a transparent glass platform can see 3D-format picture. It allows everyone to go into virtual worlds.
The complex practical use includes the following:
At the present moment there are no analogous technical implementations in Russia while designing complicated technological objects. This demonstration method is used only by defense industry, large automobile corporations and aircraft engineering companies. [6]
2009:
2010:
2011:
2012:
The project was realized in 2009 and completed in 2012.
The first VVER-TOI construction began in April 2018 at the Kursk Nuclear Power Plant, with a predicted completion date of late 2022. [7]
In addition, there are an additional 11 VVER-TOI units planned. [7]
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. 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.
A nuclear meltdown is a severe nuclear reactor accident that results in core damage from overheating. The term nuclear meltdown is not officially defined by the International Atomic Energy Agency or by the United States Nuclear Regulatory Commission. It has been defined to mean the accidental melting of the core of a nuclear reactor, however, and is in common usage a reference to the core's either complete or partial collapse.
A nuclear power plant (NPP), also known as a nuclear power station (NPS), nuclear generating station (NGS) or atomic power station (APS) is a thermal power station in which the heat source is a nuclear reactor. As is typical of thermal power stations, heat is used to generate steam that drives a steam turbine connected to a generator that produces electricity. As of September 2023, the International Atomic Energy Agency reported that there were 410 nuclear power reactors in operation in 32 countries around the world, and 57 nuclear power reactors under construction.
The RBMK is a class of graphite-moderated nuclear power reactor designed and built by the Soviet Union. It is somewhat like a boiling water reactor as water boils in the pressure tubes. It is one of two power reactor types to enter serial production in the Soviet Union during the 1970s, the other being the VVER reactor. The name refers to its design where instead of a large steel pressure vessel surrounding the entire core, the core is surrounded by a cylindrical annular steel tank inside a concrete vault and each fuel assembly is enclosed in an individual 8 cm (inner) diameter pipe. The channels also contain the coolant, and are surrounded by graphite.
Passive nuclear safety is a design approach for safety features, implemented in a nuclear reactor, that does not require any active intervention on the part of the operator or electrical/electronic feedback in order to bring the reactor to a safe shutdown state, in the event of a particular type of emergency. Such design features tend to rely on the engineering of components such that their predicted behaviour would slow down, rather than accelerate the deterioration of the reactor state; they typically take advantage of natural forces or phenomena such as gravity, buoyancy, pressure differences, conduction or natural heat convection to accomplish safety functions without requiring an active power source. Many older common reactor designs use passive safety systems to a limited extent, rather, relying on active safety systems such as diesel-powered motors. Some newer reactor designs feature more passive systems; the motivation being that they are highly reliable and reduce the cost associated with the installation and maintenance of systems that would otherwise require multiple trains of equipment and redundant safety class power supplies in order to achieve the same level of reliability. However, weak driving forces that power many passive safety features can pose significant challenges to effectiveness of a passive system, particularly in the short term following an accident.
State Atomic Energy Corporation Rosatom, also known as Rosatom State Nuclear Energy Corporation,, or Rosatom State Corporation, is a Russian state corporation headquartered in Moscow that specializes in nuclear energy, nuclear non-energy goods and high-tech products. It was established in 2007 and comprises more than 350 enterprises, including scientific research organizations, a nuclear weapons complex, and the world's only nuclear icebreaker fleet.
A containment building is a reinforced steel, concrete or lead structure enclosing a nuclear reactor. It is designed, in any emergency, to contain the escape of radioactive steam or gas to a maximum pressure in the range of 275 to 550 kPa. The containment is the fourth and final barrier to radioactive release, the first being the fuel ceramic itself, the second being the metal fuel cladding tubes, the third being the reactor vessel and coolant system.
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