| 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.