| BOR-60 | |
|---|---|
| Reactor concept | Fast-neutron reactor1 |
| Status | Expected to shutdown in 20252 |
| Location | Dimitrovgrad, Russia, Russia |
| Main parameters of the reactor core | |
| Fuel (fissile material) | MOX (UO2-PuO2)3 |
| Neutron energy spectrum | Fast |
| Primary coolant | Sodium3 |
| Reactor usage | |
| Power (thermal) | 60 MW3 |
| Power (electric) | 12 MW3 |
The BOR-60 is an operational Russian research sodium-cooled fast reactor designed to test nuclear fuels, structural materials and coolants, as well as scientific experiments under fast neutron irradiation.1
History
The BOR-60 reactor was constructed to perform tests for the commercial BN-350, BN-600 and BN-800 reactors, which also use fast neutron breeding.4 Construction began in 1964, and it reached first criticality in 1968.4 It was commissioned the following year, in 1969.1
Originally it used highly enriched uranium, but in 1981 it switched over to burning MOX fuel containing weapons-grade plutonium from decommissioned nuclear warheads.5
BOR-60 was intended to be decommissioned in 2010,5 but was prolonged until 2025, after which the MBIR will replace it.2
In 2025 a new technology is being developed for processing of radioactive liquid sodium for proper decommissioning of fast neutron reactors such as BOR-60 and BN-350 (in future it can be used when BN-600 and BN-800 reach the end of life).6
Reactor design
The BOR-60 reactor is designed to operate on a mixed-oxide MOX fuel, based on UO2 (highly enriched uranium, 45%-90% 235U) and PuO2.7 The reactor is mainly constructed out of stainless steel.8
Core
Grey: fuel assemblies
White: blank assemblies
Blue: experimental material assemblies
Green: experimental fuel assemblies
Red: control rods
Yellow: experimentation channels source ↗
The core is made up of a hexagonal grid containing 265 separate elements, with fuel channels, control rods, various experimental assemblies and an outer section of solid blanket assemblies (blanks).8 The reactor vessel also has several experimentation channels in the outer hull, with widths varying from 90 mm to 230 mm.9
Coolant
The reactor is a sodium-cooled fast reactor, which uses liquid sodium as the coolant.4 It uses two separate sodium loops, and these are connected to a main water-cooled loop which feeds the steam generators and turbines for producing electricity.8 The sodium coolant is pressurized to 5.5 MPa, and is heated to over 500 °C in the reactor.7
Capabilities
BOR-60 allows for wide-scale tests of fuels, materials, coolants and detectors for various fast reactors.10 It is capable or burning a wide range of fuels, including weapons-grade material, as well as various metallic, oxide, nitride and carbide variations.5 Thus it has been used to test fuels and reactor physics for a wide array of reactors, such as the BN-350, BN-600 and BN-800, as well as the MBIR and proposed BREST-300 lead-cooled reactors.411
See also
See also
- MBIR - multi-loop research reactor intends to replace BOR-60. In construction since 2015, est. completion in 2027.
- BN-800 reactor - generation IV sodium-cooled fast breeder reactor, operational since 2016
- BREST-300 - generation IV lead-cooled fast reactor, in construction since 2020
- Versatile Test Reactor - a similar US project, the funding was canceled in 2022
References
References
- "Fast Reactor BOR-60". niiar.ru. Retrieved 14 September 2024.
- "Pilot fuel elements produced for MBIR reactor". www.neimagazine.com. Retrieved 14 September 2024.
- "Parameters". niiar.ru. Retrieved 14 September 2024.
- "Russia Completes Design Work For New Fast Reactor". nucnet.org. Retrieved 14 September 2024.
- "BOR-60 reactor as an instrument for experimental substantiation of fuel rods for advanced NPPs". inis.iaea.org. Retrieved 14 September 2024.
- "Rosatom develops technology for processing radioactive liquid sodium". world-nuclear-news.org. 2025-04-03. Retrieved 2025-04-03.
- "Parameters". niiar.ru. Retrieved 23 January 2025.
- "Prolongation of the BOR-60 reactor operation". Researchgate.net. Retrieved 23 January 2025.
- "Core Arrangement". niiar.ru. Retrieved 23 January 2025.
- "Experimental Capabilities". niiar.ru. Retrieved 14 September 2024.
- Grachev, A. F.; Zherebtsov, A. A.; Zabud'Ko, L. M.; Zvir, E. A.; Kryukov, F. N.; Nikitin, O. N.; Skupov, M. V.; Ivanov, Yu. A.; Porollo, S. I. (2019). "Results of Investigations of BREST-Type Reactor Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel, Irradiated in BOR-60 and BN-600". Atomic Energy. 125 (5): 314–321. doi:10.1007/s10512-019-00487-4. Retrieved 14 September 2024.