At its peak in 1982, nuclear power in the Soviet Union accounted for 6.5% of total electricity consumption and the total nuclear capacity installed was 18 GW. [1] However, nuclear power within the Soviet Union declined severely as a result of the 1986 Chernobyl Disaster.
The first nuclear power plant constructed in the world was the Obninsk Nuclear Power Plant, built near Moscow on June 26, 1954. It was intended as an experiment to determine the capabilities of nuclear power in supplying a commercial grid. At the beginning of its operation, it produced 5 MWe. [2] The power plant proved successful in its experiment and four years later, the Siberian Nuclear Power Station with a 100 MWe capacity was installed and subsequently increased to 600 MWe. Following the development, commercial power stations were constructed in Beloyarsk, Novo-Voronezh, Kola, Leningrad, and Armenia. [3]
In the year 1960, the Soviet Union had a nuclear power capacity of 605 MWe. By 1975, this capacity was increased to 4.7 GW. [3] At this point, the Soviet Union was committed to developing an aggressive nuclear power program. Throughout the 1970s, approximately 10% of electricity powering the Soviet Union came from Nuclear Power Plants and predictions made by Deputy Minister of Power Energy aimed an increase by approximately 400-500% by the year 2000. [4]
All Soviet power reactors were designed by the Ministry of Medium Machine Building (Sredmash), the key Soviet ministry for administering the Soviet nuclear weapons complex from 1953 until 1989 (when it was reorganized into the Ministry of Atomic Energy and Industry of the USSR). The reactors were ordered and administered, however by the Ministry of Energy and Electrification (Minenergo), which was in charge of power production and plant operation. The differences in institutional culture, priorities, and expertise between these two industries have been argued to be core to understanding the choices made by the Soviet Union in the field of nuclear power, notably in its embrace of the controversial RBMK reactor design, which was developed with a priority on ease of local construction, economical value, and the possibility (never implemented) for dual-use plutonium production — with core safety concerns being either de-prioritized or kept secret. [2]
On April 26, 1986, an uncontrolled power increase occurred within the core of Reactor No. 4 at the Chernobyl Nuclear Power Plant causing an explosion within the core that destroyed the reactor itself, and vented radioactive materials into the atmosphere and surrounding environment, causing dozens of immediate deaths related to the containment of the accident, and potentially tens of thousands of later deaths from cancer. [5] [6] The Chernobyl disaster is one of two disasters ranked as a Level 7 on the International Nuclear Event Scale for the spread of radioactive material and environmental effects, and there are significant areas of Ukraine and Belarus that are still considered contaminated by the accident. [7]
Following the 1986 accident, stances on nuclear power changed, especially so in the USSR. [8] The incident highlighted the threat of the country's 24 RBMK reactors, which were found to have been created with major operational flaws that cause uncontrollable spikes in energy during a reactor's emergency shutdown procedure. [9] These required re-design or replacement to meet safety standards for operation. [4] [10]
The event slowed the nuclear energy program of the Soviet Union, which would not see reinvigoration until after the collapse of the Soviet Union in 1991.
Name | Location | SSR | Unit | Type | Gross Capacity (MWe) | Operational | Status | Notes |
---|---|---|---|---|---|---|---|---|
Armenian | Yerevan | Armenian | 1 | VVER | 408 | 1976-1988 | Closed | Shutdown after the Spitak Earthquake and Chernobyl accident |
2 | VVER | 440 | 1980-1988, 1995– | Operational | Shutdown after the Spitak Earthquake and Chernobyl accident, restarted in 1995. Shutdown expected 2026 | |||
Balakovo | Balakovo | Russian | 1 | VVER | 1000 | 1986– | Operational | |
2 | VVER | 1000 | 1988– | Operational | ||||
3 | VVER | 1000 | 1989– | Operational | ||||
4 | VVER | 1000 | 1993– | Operational | ||||
5 | VVER | 1000 | Planned 1970s | Cancelled | ||||
6 | VVER | 1000 | Planned 1970s | Cancelled | ||||
Beloyarsk | Zarechny, Sverdlovsk Oblast | Russian | 1 | AMB-100 | 108 | 1958-1983 | Closed | |
2 | AMB-200 | 160 | 1962-1990 | Closed | ||||
3 | BN-600 | 600 | 1969- | Operational | ||||
4 | BN-800 | 885 | 1987- | Operational | ||||
Chernobyl | Chernobyl | Ukrainian | 1 | RBMK | 1000 | 1977-1995 | Closed | Shutdown as a result of the Chernobyl Disaster |
2 | RBMK | 1000 | 1978-1991 | Closed | Shutdown as a result of fire damage | |||
3 | RBMK | 1000 | 1981-1995 | Closed | Shutdown as a result of the Chernobyl Disaster | |||
4 | RBMK | 1000 | 1983-1986 | Destroyed | Catastrophic meltdown and explosion — the reactor of the Chernobyl Disaster | |||
5 | RBMK | 1000 | Planned 1986 | Cancelled | Postponed to 1989, then cancelled by Chernobyl Disaster | |||
6 | RBMK | 1000 | Planned 1988 | Cancelled | Postponed to 1989, then cancelled by Chernobyl Disaster | |||
Ignalina | Visaginas | Lithuanian | 1 | RBMK-1500 | 1360 | 1983-2004 | Closed | Initially operated at 1500 MW, de-rated to 1360 after the Chernobyl accident. |
2 | RBMK-1500 | 1360 | 1987-2009 | Closed | Meant to come online in 1986, postponed for a year after the Chernobyl accident. | |||
3 | RBMK-1500 | 1500 | Planned 1991 | Cancelled | Construction cancelled in 1989 | |||
4 | RBMK-1500 | 1500 | Planned 1990s | Cancelled | Construction cancelled in 1989 | |||
Kalinin | Udomlya | Russian | 1 | VVER | 1000 | 1985- | Operational | Shutdown expected 2025 |
2 | VVER | 1000 | 1987- | Operational | Shutdown expected 2038 | |||
3 | VVER | 1000 | 2005- | Operational | ||||
4 | VVER | 1000 | 2012- | Operational | ||||
Khmelnytskyi | Netishyn | Ukrainian | 1 | VVER | 1000 | 1973- | Operational | |
2 | VVER | 1000 | 1973- | Operational | ||||
3 | VVER | 1000 | Est. 2027 | Under Construction | Construction stopped in 1980s, restarted in 2018 | |||
4 | VVER | 1000 | Est. 2028 | Under Construction | Construction stopped in 1980s, restarted in 2018 | |||
Kola | Polyarnye Zori | Russian | 1 | VVER | 440 | 1973- | Operational | Shutdown expected 2033 |
2 | VVER | 440 | 1975- | Operational | Shutdown expected 2035 | |||
3 | VVER | 440 | 1982- | Operational | Shutdown expected 2042 | |||
4 | VVER | 440 | 1984- | Operational | Shutdown expected 2044 | |||
Kursk | Kursk | Russian | 1 | RBMK | 1000 | 1977-2021 | Closed | |
2 | RBMK | 1000 | 1979-2024 | closed | Shutdown 2024 | |||
3 | RBMK | 1000 | 1983- | Operational | Shutdown expected 2033 [11] Originally expected in 2028, but prolonged by more 5 years | |||
4 | RBMK | 1000 | 1985- | Operational | Shutdown expected in 2035 [11] Originally expected in 2030, but prolonged by more 5 year | |||
5 | RBMK | 1000 | Planned 1991 | Cancelled | Construction cancelled in 2012, nearly 100% complete | |||
6 | RBMK | 1000 | Planned 1992 | Cancelled | Construction cancelled in 1993 | |||
Leningrad | Sosnovy Bor | Russian | 1 | RBMK | 1000 | 1974-2018 | Closed | |
2 | RBMK | 1000 | 1976-2020 | Closed | ||||
3 | RBMK | 1000 | 1980- | Operational | Shutdown expected 2025 | |||
4 | RBMK | 1000 | 1981- | Operational | Shutdown expected 2026 | |||
Mangyshlak | Aktau | Kazakh | 1 | BN-350 | 350 | 1973-1999 | Closed | |
Novovoronezh | Novovoronezh | Russian | 1 | VVER | 210 | 1964-1988 | Closed | |
2 | VVER | 365 | 1970-1990 | Closed | ||||
3 | VVER | 417 | 1972-2016 | Closed | ||||
4 | VVER | 417 | 1973- | Operational | Shutdown expected 2032 | |||
5 | VVER | 950 | 1981- | Operational | Shutdown expected 2035 | |||
Obninsk | Obninsk | Russian | 1 | AM-1 | 5 | 1954-2002 | Closed | World's first nuclear power plant |
Rivne | Varash | Ukrainian | 1 | VVER | 440 | 1981- | Operational | Shutdown expected in 2041 |
2 | VVER | 440 | 1982- | Operational | Shutdown expected in 2042 | |||
3 | VVER | 1000 | 1986- | Operational | Shutdown expected in 2041 | |||
4 | VVER | 1000 | 2004- | Operational | Shutdown expected in 2064 | |||
Smolensk | Smolensk | Russian | 1 | RBMK | 1000 | 1983- | Operational | Shutdown expected 2027 |
2 | RBMK | 1000 | 1985- | Operational | Shutdown expected 2030 | |||
3 | RBMK | 1000 | 1990- | Operational | Shutdown expected 2034 | |||
4 | RBMK | 1000 | Planned ~1994 | Cancelled | Construction cancelled 1993 | |||
South Ukraine | Yuzhnoukrainsk | Ukrainian | 1 | VVER | 1000 | 1983- | Operational | Shutdown expected in 2043 |
2 | VVER | 1000 | 1985- | Operational | Shutdown expected in 2045 | |||
3 | VVER | 1000 | 1989- | Operational | Shutdown expected in 2049 | |||
4 | VVER | 1000 | Planned 1991 | Cancelled | Construction halted in 1989 - cooling capability problem | |||
Zaporizhzhia | Enerhodar | Ukrainian | 1 | VVER | 1000 | 1985- | Operations Suspended | Controlled by Russia since 2022 |
2 | VVER | 1000 | 1986- | Operations Suspended | Controlled by Russia since 2022 | |||
3 | VVER | 1000 | 1987- | Operations Suspended | Controlled by Russia since 2022 | |||
4 | VVER | 1000 | 1988- | Operations Suspended | Controlled by Russia since 2022 | |||
5 | VVER | 1000 | 1989- | Operations Suspended | Controlled by Russia since 2022 | |||
6 | VVER | 1000 | 1996- | Operations Suspended | Controlled by Russia since 2022 |
A nuclear reactor is a device used to initiate and control a fission nuclear chain reaction. Nuclear reactors are used at nuclear power plants for electricity generation and in nuclear marine propulsion. When a fissile nucleus like uranium-235 or plutonium-239 absorbs a neutron, it splits into lighter nuclei, releasing energy, gamma radiation, and free neutrons, which can induce further fission in a self-sustaining chain reaction. The process is carefully controlled using control rods and neutron moderators to regulate the number of neutrons that continue the reaction, ensuring the reactor operates safely, although inherent control by means of delayed neutrons also plays an important role in reactor output control. The efficiency of energy conversion in nuclear reactors is significantly higher compared to conventional fossil fuel plants; a kilo of uranium-235, if all the atoms were split, would release about three million times more energy than a kilo of coal.
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.
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.
A nuclear and radiation accident is defined by the International Atomic Energy Agency (IAEA) as "an event that has led to significant consequences to people, the environment or the facility." Examples include lethal effects to individuals, large radioactivity release to the environment, or a reactor core melt. The prime example of a "major nuclear accident" is one in which a reactor core is damaged and significant amounts of radioactive isotopes are released, such as in the Chernobyl disaster in 1986 and Fukushima nuclear disaster in 2011.
The International Nuclear and Radiological Event Scale (INES) was introduced in 1990 by the International Atomic Energy Agency (IAEA) in order to enable prompt communication of safety significant information in case of nuclear accidents.
The Chernobyl Nuclear Power Plant (ChNPP) is a nuclear power plant undergoing decommissioning. ChNPP is located near the abandoned city of Pripyat in northern Ukraine, 16.5 kilometers (10 mi) northwest of the city of Chernobyl, 16 kilometers (10 mi) from the Belarus–Ukraine border, and about 100 kilometers (62 mi) north of Kyiv. The plant was cooled by an engineered pond, fed by the Pripyat River about 5 kilometers (3 mi) northwest from its juncture with the Dnieper River.
The Chernobyl disaster began on 26 April 1986 with the explosion of the No. 4 reactor of the Chernobyl Nuclear Power Plant near the city of Pripyat in northern Ukraine, near the Belarus border in the Soviet Union. It is one of only two nuclear energy accidents rated at the maximum severity on the International Nuclear Event Scale, the other being the 2011 Fukushima nuclear accident. The response involved more than 500,000 personnel and cost an estimated 18 billion rubles. It remains the worst nuclear disaster in history, and the costliest disaster in human history, with an estimated cost of $700 billion USD.
The water-water energetic reactor (WWER), or VVER is a series of pressurized water reactor designs originally developed in the Soviet Union, and now Russia, by OKB Gidropress. The idea of such a reactor was proposed at the Kurchatov Institute by Savely Moiseevich Feinberg. VVER were originally developed before the 1970s, and have been continually updated. They were one of the initial reactors developed by the USSR, the other being the infamous RBMK. As a result, the name VVER is associated with a wide variety of reactor designs spanning from generation I reactors to modern generation III+ reactor designs. Power output ranges from 70 to 1300 MWe, with designs of up to 1700 MWe in development. The first prototype VVER-210 was built at the Novovoronezh Nuclear Power Plant.
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