MBIR
Fast neutron research reactor
From Wikipedia, the free encyclopedia
The MBIR is a multi-loop research reactor capable of testing lead, lead-bismuth and gas coolants, and run on MOX fuel. MBIR intends to replace the old BOR-60 experimental fast reactor that started operations at RIAR's site in 1969. It will have a design life of 50 years.[3]
Reactor conceptFast-neutron reactor[1]
StatusUnder construction since 2015
LocationDimitrovgrad, Russia, Russia
Fuel (fissile material)vibropacked MOX fuel with plutonium content of 38%[1]
| MBIR | |
|---|---|
| Reactor concept | Fast-neutron reactor[1] |
| Status | Under construction since 2015 |
| Location | Dimitrovgrad, Russia, Russia |
| Main parameters of the reactor core | |
| Fuel (fissile material) | vibropacked MOX fuel with plutonium content of 38%[1] |
| Neutron energy spectrum | Fast |
| Primary coolant | sodium (Pb–Bi, gas)[1] |
| Reactor usage | |
| Power (thermal) | 150 MW[2] |
| Power (electric) | 55 MW[2] |
History
See also
- Generation IV reactor
- 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
