BOR-60 - Misplaced Pages

Multipurpose fast neutron research reactor, in operation since 1968, expected shutdown in 2025

BOR-60
Reactor concept	Fast-neutron reactor
Status	Expected to shutdown in 2025
Location	Dimitrovgrad, Russia, Russia
Main parameters of the reactor core
Fuel (fissile material)	UO2-PuO2
Neutron energy spectrum	Fast
Primary coolant	sodium
Reactor usage
Power (thermal)	60 MW
Power (electric)	12 MW

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

History

Construction has started in 1964. Reactor reached first criticality in 1968. Commissioned in 1969.

From 1969 to 1981 the BOR-60 used the pellet uranium fuel.

Since 1981 BOR-60 has been using the vibropac oxide mixed fuel with the power grade plutonium.

BOR-60 is expected to be closed in 2025. Currently constructed MBIR should replace it.

BOR-60 allows wide-scale tests of fuels for fast reactors.

BOR-60 was used for testing of fuel rods for BREST-300.

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

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 ADE-2
Canceled	Bashkir 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

Companies

Category

Types of nuclear fission reactor

Moderator

Light water

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

Water

H₂O	AM-1 AMB-X EGP-6 RBMK

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

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

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)

Others