MBIR

Multipurpose fast neutron research reactor, in construction since 2015, estimated completion in 2027

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]

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]

History

Construction has started in 2015.^[4]

MBIR control assembly was installed in 2019.^[5]

Reactor vessel was installed in 2023.^[6]

Pilot fuel elements were produced in 2024. The MBIR is scheduled to begin operation in 2027.^[3]

Estimated commissioning date is 2028.^[2]

References

^ ^a ^b ^c "Fast Neutron Reactors". world-nuclear.org. Retrieved 31 August 2024.
^ ^a ^b ^c https://en.mbir-rosatom.ru/reactor/
^ ^a ^b https://www.world-nuclear-news.org/Articles/Pilot-fuel-produced-for-MBIR-fast-neutron-research
^ https://www.neimagazine.com/news/russia-begins-construction-of-mbir-4671316/
^ https://www.world-nuclear-news.org/Articles/Russia-starts-installing-MBIR-control-assembly
^ https://www.world-nuclear-news.org/Articles/MBIR-gets-its-reactor-vessel

External links

Official website

Nuclear power in Russia

Energy policy of Russia
Energy in Russia

Reactors

Active	Akademik Lomonosov Balakovo Beloyarsk Bilibino Dimitrovgrad Kalinin Kola Kursk Leningrad Leningrad II Novovoronezh Novovoronezh II Rostov Smolensk BOR-60
Under construction	Leningrad II Kursk II BREST-300 MBIR
Closed	Obninsk Siberian Troitsk
Canceled	Bashkir Crimean Gorky Kaliningrad Krasnodar Primorsk South Ural Tatar (Kama) Tver Volgograd Voronezh
Planned	Smolensk II BN-1200

Reactor types

Power plant reactors	BN-600 BN-800 RBMK EGP-6 VVER VVER-TOI KLT-40S
Research, experimental and prototype reactors	GT-MHR T-15

Research locations

Kurchatov Institute

Companies

Category

Types of nuclear fission reactor

Moderator

Light water

Aqueous homogeneous
Boiling
- BWR
- ABWR
- ESBWR
- Kerena
Natural fission
Pressurized
- AP1000
- APR-1400
- APR+
- APWR
- ATMEA1
- CAP1400
- CPR-1000
- EPR
- HPR-1000
  - ACPR1000
  - ACP1000
- VVER
- IPWR-900
- many others
Supercritical (SCWR)

Heavy water
by coolant

D₂O	Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken
H₂O	HWLWR ATR HW BLWR 250 Steam-generating (SGHWR) AHWR
Organic	WR-1
CO₂	HWGCR EL-4 KKN KS 150 Lucens

Graphite
by coolant

Water

H₂O	AM-1 AMB-X EGP-6 RBMK

Gas

CO₂	Uranium Naturel Graphite Gaz (UNGG) Magnox Advanced gas-cooled (AGR)
He	GTMHR MHR-T UHTREX VHTR (HTGR) PBR (PBMR) AVR HTR-10 HTR-PM THTR-300 PMR

Molten-salt

Fluorides	Fuji MSR Liquid-fluoride thorium reactor (LFTR) Molten-Salt Reactor Experiment (MSRE) Integral Molten Salt Reactor (IMSR) TMSR-500 TMSR-LF1

None
(fast-neutron)

Breeder (FBR) Integral (IFR) Liquid-metal-cooled (LMFR) Small sealed transportable autonomous (SSTAR) Traveling-wave (TWR) Energy Multiplier Module (EM2) Reduced-moderation (RMWR) Fast Breeder Test Reactor (FBTR) Dual fluid reactor (DFR)
Generation IV	Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead Helium gas (GFR) Stable Salt Reactor (SSR)