BOR-60
Appearance
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.
History
[edit]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]
Capabilities
[edit]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]
See also
[edit]- 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
References
[edit]- ^ a b "Fast Reactor BOR-60". niiar.ru. Retrieved 14 September 2024.
- ^ a b "Pilot fuel elements produced for MBIR reactor". www.neimagazine.com. Retrieved 14 September 2024.
- ^ a b c d "Parameters". niiar.ru. Retrieved 14 September 2024.
- ^ "Russia Completes Design Work For New Fast Reactor". nucnet.org. Retrieved 14 September 2024.
- ^ a b "BOR-60 reactor as an instrument for experimental substantiation of fuel rods for advanced NPPs". inis.iaea.org. Retrieved 14 September 2024.
- ^ "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.