BOR-60

BOR-60
Reactor conceptFast-neutron reactor[1]
StatusExpected to shutdown in 2025[2]
LocationDimitrovgrad, Russia, Russia
Main parameters of the reactor core
Fuel (fissile material)UO2-PuO2[3]
Neutron energy spectrumFast
Primary coolantsodium[3]
Reactor usage
Power (thermal)60 MW[3]
Power (electric)12 MW[3]

The BOR-60 is an experimental sodium-cooled fast reactor.

History

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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

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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

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References

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  1. ^ a b "Fast Reactor BOR-60". niiar.ru. Retrieved 14 September 2024.
  2. ^ a b "Pilot fuel elements produced for MBIR reactor". www.neimagazine.com. Retrieved 14 September 2024.
  3. ^ a b c d "Parameters". niiar.ru. Retrieved 14 September 2024.
  4. ^ "Russia Completes Design Work For New Fast Reactor". nucnet.org. Retrieved 14 September 2024.
  5. ^ a b "BOR-60 reactor as an instrument for experimental substantiation of fuel rods for advanced NPPs". inis.iaea.org. Retrieved 14 September 2024.
  6. ^ "Experimental Capabilities". niiar.ru. Retrieved 14 September 2024.
  7. ^ 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.
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