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