| BOR-60 | |
|---|---|
| Reactor concept | Fast-neutron reactor [1] |
| Status | Expected to shutdown in 2025 [2] |
| Location | Dimitrovgrad, Russia, Russia |
| Main parameters of the reactor core | |
| Fuel (fissile material) | UO2-PuO2 [3] |
| Neutron energy spectrum | Fast |
| Primary coolant | sodium [3] |
| Reactor usage | |
| Power (thermal) | 60 MW [3] |
| Power (electric) | 12 MW [3] |
The BOR-60 is an experimental sodium-cooled fast reactor.
Construction has started in 1964. Reactor reached first criticality in 1968 [4] . Commissioned in 1969 [1] .
From 1969 to 1981 the BOR-60 used the pellet uranium fuel [5] .
Since 1981 BOR-60 has been using the vibropac oxide mixed fuel with the power grade plutonium [5] .
BOR-60 is expected to be closed in 2025. Currently constructed MBIR should replace it [2] .
BOR-60 allows wide-scale tests of fuels for fast reactors [6] .
BOR-60 was used for testing of fuel rods for BREST-300 [7] .
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. The efficiency of energy conversion in nuclear reactors is significantly higher compared to conventional fossil fuel plants; a kilo of uranium-235 can release millions of times more energy than a kilo of coal.
A breeder reactor is a nuclear reactor that generates more fissile material than it consumes. These reactors can be fueled with more-commonly available isotopes of uranium and thorium, such as uranium-238 and thorium-232, as opposed to the rare uranium-235 which is used in conventional reactors. These materials are called fertile materials since they can be bred into fuel by these breeder reactors.
A fast-neutron reactor (FNR) or fast-spectrum reactor or simply a fast reactor is a category of nuclear reactor in which the fission chain reaction is sustained by fast neutrons, as opposed to slow thermal neutrons used in thermal-neutron reactors. Such a fast reactor needs no neutron moderator, but requires fuel that is relatively rich in fissile material when compared to that required for a thermal-neutron reactor. Around 20 land based fast reactors have been built, accumulating over 400 reactor years of operation globally. The largest was the Superphénix sodium cooled fast reactor in France that was designed to deliver 1,242 MWe. Fast reactors have been studied since the 1950s, as they provide certain advantages over the existing fleet of water-cooled and water-moderated reactors. These are:
The integral fast reactor (IFR), originally the advancedliquid-metal reactor (ALMR), is a design for a nuclear reactor using fast neutrons and no neutron moderator. IFRs can breed more fuel and are distinguished by a nuclear fuel cycle that uses reprocessing via electrorefining at the reactor site.
Rosatom, also known as Rosatom State Nuclear Energy Corporation, the State Atomic Energy Corporation Rosatom, 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.
Nuclear fuel is material used in nuclear power stations to produce heat to power turbines. Heat is created when nuclear fuel undergoes nuclear fission. Nuclear fuel has the highest energy density of all practical fuel sources. The processes involved in mining, refining, purifying, using, and disposing of nuclear fuel are collectively known as the nuclear fuel cycle.
Generation IVreactors are nuclear reactor design technologies that are envisioned as successors of generation III reactors. The Generation IV International Forum (GIF) – an international organization that coordinates the development of generation IV reactors – specifically selected six reactor technologies as candidates for generation IV reactors. The designs target improved safety, sustainability, efficiency, and cost. The World Nuclear Association in 2015 suggested that some might enter commercial operation before 2030.
The lead-cooled fast reactor is a nuclear reactor design that use molten lead or lead-bismuth eutectic coolant. These materials can be used as the primary coolant because they have low neutron absorption and relatively low melting points. Neutrons are slowed less by interaction with these heavy nuclei so these reactors operate with fast neutrons.
Experimental Breeder Reactor-II (EBR-II) was a sodium-cooled fast reactor designed, built and operated by Argonne National Laboratory at the National Reactor Testing Station in Idaho. It was shut down in 1994. Custody of the reactor was transferred to Idaho National Laboratory after its founding in 2005.
A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium.
The BN-600 reactor is a sodium-cooled fast breeder reactor, built at the Beloyarsk Nuclear Power Station, in Zarechny, Sverdlovsk Oblast, Russia. It has a 600 MWe gross capacity and a 560 MWe net capacity, provided to the Middle Urals power grid. It has been in operation since 1980 and represents an improvement to the preceding BN-350 reactor. In 2014, its larger sister reactor, the BN-800 reactor, began operation.
The BN-350 was a sodium-cooled, fast reactor located at the Mangyshlak Nuclear Power Plant, located in Aktau, Kazakhstan, on the shore of the Caspian Sea.
The Prototype Fast Breeder Reactor (PFBR) is a 500 MWe sodium-cooled, fast breeder reactor that is being constructed at Kokkilamedu, near Kalpakkam, in Tamil Nadu state, India. The Indira Gandhi Centre for Atomic Research (IGCAR) is responsible for the design of this reactor, the Advanced Fuel Fabrication Facility at the Bhabha Atomic Research Centre in Tarapur is responsible for MOX fuel fabrication and BHEL is providing technology and equipment for construction of the reactor. The facility builds on the decades of experience gained from operating the lower power Fast Breeder Test Reactor (FBTR). At first, the reactor's construction was supposed to be completed in September 2010, but there were several delays. The Prototype Fast Breeder Reactor is scheduled to be put into service in December 2024, which is more than 20 years after construction began and 14 years after the original commissioning date, as of December 2023. The project's cost has doubled from ₹3,500 crore to ₹7,700 crore due to the multiple delays. The construction was completed on 4th March 2024 with commencement of core loading of the reactor hence paving the way for the eventual full utilization of India’s abundant thorium reserves.
The BN-800 reactor 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. The reactor is part of the final step for a plutonium-burner core 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.
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.
ASTRID was a proposal for a 600 MW sodium-cooled fast breeder reactor, 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 BREST reactor is a Russian conceptual design for a lead-cooled fast reactor based on a generation IV reactor. Two designs are planned, the BREST-300 and the BREST-1200. The main characteristics of the BREST reactor are passive safety and a closed fuel cycle.
The CFR-600 is a sodium-cooled pool-type fast-neutron nuclear reactor under construction in Xiapu County, Fujian province, China, on Changbiao Island. It is a generation IV demonstration project by the China National Nuclear Corporation (CNNC). Construction started in late 2017. These reactors are expected to be connected to the grid in 2023 and 2025. The reactor will have an output of 1500 MW thermal power and 600 MW electric power. The fuel will be supplied by TVEL, subsidiary of Rosatom, according to the agreement signed in 2019.
The utilization of nuclear power in Kazakhstan began with Kazakhstan's first nuclear power plant, the BN-350 fast-neutron reactor in Aktau, operating from 1973 to 1999, a Soviet era prototype investment preceding the BN-600 reactor. Since then, it has only operated four smaller research reactors and did not have nuclear electricity production capabilities. Kazakhstan is the number one country in the world for uranium production volumes, which is used for nuclear fuel. Current plans, reaching back to 1997, foresee the construction of two new nuclear power plants near the towns of Ulken and Kurchatov.
The MBIR is a multi-loop research reactor capable of testing lead, lead-bismuth and gas coolants, and run on MOX fuel. MBIR intends to replace the old BOR-60 experimental fast reactor that started operations at RIAR's site in 1969. It will have a design life of 50 years.
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