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Russia: Reactors: Research: All-Russian Scientific Research Institute of Atomic Reactors (SRIAR) Russia: All-Russian Scientific Research Institute of Atomic Reactors (NIIAR)

Государственный научный центр Российской Федерации Научно-исследовательский институт атомных реакторов (ГНЦ РФ НИИАР)

To return to the research facilities with reactors overview, see the Research Facilities with Reactors and Critical/Subcritical Assemblies file.
For recent developments, see the Research Facilities with Reactors and Critical/Subcritical Assemblies Developments file.
SRIAR Background Activities Structure Fissile Material MPC&A Reactors Critical Assemblies

LOCATION:  Dimitrovgrad-10, Ulyanovsk Oblast
Address:  Dimitrovgrad-10  433510
Telephone:  (84235) 32021, 32727, 36620, 65502
Fax:  (84235) 35859, 35648
[SRIAR Homepage,  http://www.niiar.ru.] {Entered 10/12/99 MLB}
HOMEPAGE: http://www.niiar.ru
SUBORDINATION: SRIAR is subordinate to Minatom.
ADMINISTRATION:
Director: Aleksey Frolovich Grachev
Deputy Directors: Vladimir A. Tsykanov
Viktor A. Kupriyenko
Oleg V. Skiba
Viktor N. Golovanov
Anatoliy N. Kosorukov
Aleksandr N. Zakharov
Aleksandr A. Manuylov
Chief Engineer: Vladimir V. Kalygin
Sources:
[1] "Making Fuel from Warheads,"BBC News, online edition, http://news.bbc.co.uk/, 5 January 1999.
[2] Nikolay Senchev, "Made in Russia," Rossiyskaya Gazeta, 21 January 1999; in "Incineration of weapon-grade plutonium," FBIS Document FTS19990201001047. {Entered 5/24/99 VT}
[3] SRIAR  homepage, http://www.niiar.simbirsk.su/eng/struct.htm. {Updated 7/12/99 VT}
BACKGROUND:
According to a Vesti newscast, SRIAR is the world's largest research center devoted to nuclear power. [1] As of 2002, SRIAR employed some 6000 people, including 720 scientists, 2000 engineers and 3300 workers.[2]  The institute occupies 1.8 square kilometers and includes the following facilities:  eight reactors (two of which are shut down); two critical assemblies; a materials science facility with approximately 50 hot cells and over 100 shielded boxes; experimental facilities for fuel reprocessing, manufacturing fuel from plutonium, and fabricating fuel rods and assemblies; and facilities for developing and producing instruments.[3,4]
Sources:
[1] Vesti Newscast, 4 February 1997; in "Dmitrovgrad [sic] Atomic Center 'Dying' Due to Funds Shortage," FBIS-SOV-97-023. {Entered 2/20/97 LBN}
[2] SRIAR  homepage, http://www.niiar.simbirsk.su {Updated 7/12/99 VT} {Updated 9/23/02 NL}
[3]"All-Russian Scientific Research Institute of Atomic Reactors," Los Alamos National Laboratory Web Site, http://www.lanl.gov.
[4] V.A. Tsykanov, V.N. Golovanov, V.P. Smirnov, V.A. Ovchinnikov, and V.Sh. Sulaberidze, "Osnovnyye napravleniya rabot NIIAR dlya eksperimentalnogo obosnovaniya razrabotok sovremennykh yadernykh energeticheskikh ustanovok," SRIAR Web Site, http://www.niiar.simbirsk.su/eng/docl.htm. {updated 9/25/01 DK}
ACTIVITIES:
SRIAR conducts research on nuclear physics, reactor materials science, methods of testing nuclear power plant materials, nuclear reactors and safety issues, the nuclear fuel cycle, environmentally safe technologies, and other energy-related technologies.[1,2]  The institute tests different fuel compositions and fuel assemblies, including those used in VVER-440, VVER-1000, RBMK, and BN-600 reactors.[3]  In 1986, SRIAR installed a new hot cell line to produce fuel for fast reactors like the BN-600 and the future BN-800. SRIAR is working on contracts with various customers, mainly with Russian NPPs to investigate the safety of VVER-1000 and VVER-440 fuel. There are also plans to work with the United Kingdom, Finland (the Loviisa VVER plant), France (Fragema), and the United States.[4]
 
SRIAR produces various radionuclides on a commercial basis.[1]  In 1996, SRIAR's scientists designed and produced Curium-244 sources, which were used in a spectrometric complex and in an APX spectrometer as a source of alpha-particles to study Mars's surface on the NASA Pathfinder spacecraft.[2] The institute produces more than 50 different types of medical isotopes, including iodine-131, cobalt-6, and strontium-89 chloride. [5]  Isotope sales to the West average $7 million each year.[6]
 
SRIAR develops MOX fuel fabrication technologies. SRIAR's "Orel" experimental production complex produces MOX fuel.[7,8,9,10]  From 1993 to 1996 SRIAR took part in the joint Russian-French AIDA/MOX program aimed at researching the use of weapons-grade plutonium in MOX fuel for Russian light-water and fast reactors.[11]  In 1996, SRIAR scientists manufactured MOX fuel from weapons-grade plutonium and produced fuel elements using vibropacking technology. That same year, SRIAR scientists investigated an experimental fuel cycle for fast and thermal reactors involving pyroelectrochemically reprocessed irradiated MOX fuel.[2] On 18 May 1999, SRIAR and the Japan Nuclear Cycle Development Institute (JNC) signed a five-year contract on joint research on the conversion of excess weapons-grade plutonium into MOX fuel.[12]  Since 1997, SRIAR has been participating in implementation of the US-Russian plutonium disposition program, including the 2000 US-Russian Plutonium Disposition Agreement.[11,13]
 
SRIAR is a center for research on dry pyroprocessing of spent fuels using molten salts.[14]
Sources:
[1] Nuclear Business Directory (Moscow: IBR Corporation, 1995), p. 112-113.
[2] SRIAR  homepage, http://www.niiar.simbirsk.su {Updated 7/12/99 VT}
[3] V.A. Tsykanov, V.N. Golovanov, V.P. Smirnov, V.A. Ovchinnikov, and V.Sh. Sulaberidze, "Osnovnyye napravleniya rabot NIIAR dlya eksperimentalnogo obosnovaniya razrabotok sovremennykh yadernykh energeticheskikh ustanovok," SRIAR Web Site, http://www.niiar.simbirsk.su/eng/docl.htm.{updated 9/25/01 DK}
[4] Judith Perera, "RIAR Seeks Leading Research Role," Nuclear Engineering International, July 1998,  pp. 39-40. {Updated 6/24/99 VT}
[5] "Atomnyy udar po bolezni stoletiya," Vek, No. 42 (407), 2000.
[6] Sergey Leskov, "Sposobny li vysokiye tekhnologii stat v prirode vezhlivym gostem," Izvestiya, 20 January 2001, p. 8; in Integrum Techno, http://www.integrum.com. {Updated 9/25/01 DK}
[7] Slipchenko, "Russian Policies On The Disposal Of HEU And Plutonium From Retired Warheads And Other Sources," Soceco Agency Newsletter, 19 November 1997, p. 7.
[8] William J. Broad, "Russians Suspect 3 Sites As Source Of Seized A-Fuel," New York Times, 19 August 1994, p. 11.
[9] "En Russie, un nuage de gaz radioactif s'est echappe d'un centre d'essais," Le Monde,  February 1996, p. 15.
[10] Vsevolod Sementsov, "Nuclear Submarine Reactor Goes Ashore," Moskovskiye novosti, No. 16 (166), 4 May 1995, p. 18.
[11] Vladimir Rybachenkov, "O mezhdunarodnom sotrudnichestve Rossii v oblasti utilizatsii izbytochnogo oruzheynogo plutoniya," Yadernyy Kontrol, No. 6, November-December 2000; in Citizens Center on Nuclear Non-Proliferation Web Site, http://www.nuclearno.ru/2000/12/yadernyi_kontrol_2.htm. {Updated 9/28/01 DK}
[12] "Joint Russian-Japanese Research for Disposition of Excess Plutonium from Nuclear Dismantlement: JNC-Russian Research Institute Contract to Burn About 20kg in Fast-breeder Reactor," Genshiryoku Sangyo Shimbun, 27 May 1999, p. 1.
[13] "Oruzheinyy Plutoniy: 'Tayny' NIIARA," Grazhdanskaya Initsiativa, No.2 (6), October 2000, pp. 4-7.{Updated 9/28/01 DK}
[14] Correspondence with nuclear facility expert, 12 March 2002, RUS020312.{Updated 7/12/99 VT}{Updated
3/13/2002 KB}

 
STRUCTURE: SRIAR is divided into the following main departments:
REACTOR PHYSICS AND SAFETY DEPARTMENT
Director: Gadzhi I. Gadzhiyev
MATERIAL SCIENCE AND TECHNOLOGY DEPARTMENT: incorporates a complex of three buildings with 51 hot cells and over 100 shielded boxes
FUEL ELEMENTS AND FUEL ASSEMBLIES DEPARTMENT
Director: V.P. Smirnov
TECHNOLOGICAL RESEARCH DEPARTMENT
CONTROL EQUIPMENT DEPARTMENT
DESIGN DEPARTMENT
 
These departments are divided into the following subdivisions:
REACTOR MODELLING DIVISION
Director: Viktor Anatolyevich Kupriyenko
RADIONUCLIDE SOURCES AND PREPARATIONS DIVISION
CHEMICAL AND TECHNOLOGICAL DIVISION
NEUTRON METROLOGY LABORATORY
Head: Nataliya Vladimirovna Markina
FUEL RESEARCH LABORATORY [3]
 
The Nuclear Business Directory and Nuclear Engineering International list a number of other divisions, laboratories and supporting facilities:
Analytical Division
Division for Process Research
Instrumentation Division
Division for Centralized Processing of Radioactive Wastes
Division for Environmental Protection
Center for Standardization, Metrology, and Measuring Technique
Physical Engineering Laboratory[1]
Materials Science Laboratory (includes a hot materials laboratory)
Radiochemical Laboratory
Supporting Facilities: experimental production units, computer center, energy supply facilities, instrumental and repair shops, transport facilities, and waste disposal system[2,3]
Sources:
[1] Nuclear Business Directory (Moscow: IBR Corporation, 1995), p. 112.
[2] Judith Perera, "RIAR Seeks Leading Research Role," Nuclear Engineering International, July 1998,  pp. 39-40. {Updated 6/24/99 VT}
[3] SRIAR  homepage, http://www.niiar.simbirsk.su/eng/struct.htm {Updated 7/12/99 VT}
 
FISSILE MATERIAL: 
SRIAR has at least 100kg of plutonium in bulk form and in MOX fuel and more than 1000kg of HEU in various forms.[1,2]
Sources:
[1] Yuri I. Kharlanov et al., "US/Russia Cooperation in Material Protection, Control, and Accounting at the SSC-RIAR, Dimitrovgrad," Partnership for Nuclear Security: United States/ Former Soviet Union Program of Cooperation on Nuclear Material Protection, Control, and Accounting, (US Department of Energy, September 1998).
[2] Office of Nonproliferation and National Security, MPC&A Program Strategic Plan (US Department of Energy, January 1998), p.16. {entered 1/10/01 DK}
MPC&A:
This site participates in the US Department of Energy MPC&A program. Specialists have identified material balance areas. Perimeter personnel and vehicle portal monitors have been delivered. Physical protection upgrades have been installed. In addition, training has taken place and the central storage facility has been enhanced.
[US Department of Energy, Office of Arms Control and Nonproliferation, Partnership for Nuclear Material Security (Washington, D.C.,  1997),  p. 18.]{Entered 1/6/98 PBI}
 
For a description of the MPC&A work being performed at this site please see the Department of Energy's December 1997 document, United States/Former Soviet Union Program of Cooperation on Nuclear Material Protection, Control, and Accounting: Partnership for Nuclear Security, and the Department of Energy's September 1998 document, United States/ Former Soviet Union Program of Cooperation on Nuclear Material Protection, Control, and Accounting: Partnership for Nuclear Security.
COMMENTS:
In February 1999, Atompressa reported that approximately 100 highly-skilled specialists were moved from Kazakhstan to five Russian nuclear research institutes, including SRIAR.[1] Due to financial constraints, as of 4 February 1997, the Institute had virtually stopped doing research and instead produced radioactive sources and substances for export. Despite these severe financial difficulties, Minatom decided against closing the institute.[2] According to Izvestiya, as of 20 December 2000, the financial situation at SRIAR was stable. Wages were above the Russian average and were being paid regularly. Production of medical isotopes from weapons grade plutonium constitutes one of the main sources of income for SRIAR, bringing in $7 million annually in sales from foreign customers alone.[3]    
Sources:
[1] "The Motto 'Personnel Resolve Everything' Continues to be Important'," Atompressa, No. 4 (335) February 1999, p. 3; in "Minatom Collegium on Future Direction of Nuclear Sector," FBIS Document FTS19990324001362. {Updated 11/4/99 SS}
[2] Vesti Newscast, 4 February 1997; in "Dmitrovgrad [sic] Atomic Center 'Dying' Due to Funds Shortage," FBIS-SOV-97-023. 
[3] Sergey Leskov, "Uranovaya Mekka; sposobny li vysokiye tekhnologii stat v prirode vezhlivym gostem," Izvestiya, 20 January 2001; in Integrum Techno, http://www.integrum.ru.{updated 1/31/01 DK}

 
REACTORS: Eight (one shut down) and one planned

Table I:  Research Reactors, SRIAR, Dimitrovgrad

Unit Type Power Fuel Enrichment Status
MIR-1M channel or pool 100MW 90% HEU operational
SM-3 (formerly SM-2) tank, thermal/fast neutron 100MW 90% HEU operational
RBT-10/1 pool 10MW 50-85% HEU shut down
RBT-10/2 pool 7MWt 50-85% HEU operational
RBT-6 pool 6MW 63% HEU operational
BOR-60 liquid metal 60MWt, 10 MWe MOX, containing 45-90% HEU operational
VK-50 (BWR) tank, boiling water 200MWt 1.5-2% enriched U operational
ARBUS (formerly AST-1) organic coolant 5.5MW   shut down
Prima        

NAME: MIR-M1
TYPE:
Channel [1](Le Monde and Nuclear Engineering International both list MIR-M1 as a pool reactor.[2,3])
Sources:
[1] List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.
[2]"En Russie, un nuage de gaz radioactif s'est echappe d'un centre d'essais," Le Monde, February 1996, p. 15.
[3]"World Nuclear Industry Handbook 1996," Nuclear Engineering International, p. 106.
POWER: 100MW
["IAEA Research Reactor Database," IAEA Web Site, http://www.iaea.org/worldatom/rrdb/.] {entered 11/13/00 DK}
FUEL: The normal core loading is 48 fuel assemblies, containing 12.80kg of 90% HEU.[1,2] The minimal core loading is 2.3kg of 90% HEU.[2]
 Sources: 
[1] International Institute for Applied Systems Analysis, "International Science and Technology Center Project #245 Radleg," 1996, Kurchatov Institute Web Site, http://www.kiae.ru/radleg/ch6e.htm.
[2] "IAEA Research Reactor Database," IAEA Web Site, http://www.iaea.org/worldatom/rrdb/. {entered 11/13/00 DK}
OPERATOR: Minatom
 [List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.]
COMMENTS:
This research reactor was commissioned in 1966. The State Specialized Design Institute designed the reactor.[1] The reactor is used for loop testing of fuel elements and assemblies for power and research reactors, and the production of transuranium elements.[2] The reactor core is about 1m in diameter, and it is submerged in a pool under 9m of water. In 1975 the reactor was upgraded.[3]  The MIR reactor will be reconstructed by 2005, at an estimated cost of 1.5 trillion rubles.[4]
Sources:
[1] List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.
[2] "Dimitrovgrad: Major Center for Russian Nuclear Research," Nucnet, 1 February 1996, p.9.{Entered 2/20/97 LBN}{Cleared 7/21/97 JL}
[3] Judith Perera, "RIAR Seeks Leading Research Role," Nuclear Engineering International, July 1998,  pp. 39-40. {Updated 6/24/99 VT}
[4]  Vesti newscast, 4 February 1997; in "Dmitrovgrad [sic] Atomic Center 'Dying' Due to Funds Shortage," FBIS-SOV-97-023. {Entered 2/20/97 LBN}{Cleared 7/21/97 JL}
 
NAME: SM-3 (formerly SM-2)
TYPE: tank, thermal/fast neutron
[List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.]
POWER: 100MW
[List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.]
FUEL: 28 fuel assemblies each containing approximately 1kg of 90% enriched U-235 
[International Institute for Applied Systems Analysis, "International Science and Technology Center Project #245 Radleg," 1996, Kurchatov Institute Web Site, http://www.kiae.ru/radleg/ch6e.htm.] {entered 5/15/00 DK}
OPERATOR: Minatom
COMMENTS:
This thermal/fast neutron research reactor was commissioned in 1961.[1,2] It is used for irradiating samples of reactor materials, studying their properties, producing transuranic elements, and a number of other studies in nuclear physics.[2] In 1991-1992 it underwent reconstruction. The Scientific Research and Design Institute of Energy Technologies (NIKIET) designed the reactor. Nucnet reported that this high-flux reactor is used for irradiation of reactor materials and production of transuranium and transplutonium isotopes.[3]
Sources:
[1] List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.
[2] Judith Perera, "RIAR Seeks Leading Research Role," Nuclear Engineering International, July 1998,  pp. 39-40. 
[3] "Dimitrovgrad: Major Center for Russian Nuclear Research," Nucnet, 1 February 1996, p.9.{Updated 6/24/99 VT}
 
NAME: RBT-10/1
TYPE: pool
[US General Accounting Office, "Nuclear Safety:  Concerns with Nuclear Facilities and Other Sources of Radiation in the Former Soviet Union," GAO/RCED-96-4, November 1995, p. 24.] {updated 5/17/01 DK}
POWER: 10MW
[US General Accounting Office, "Nuclear Safety:  Concerns with Nuclear Facilities and Other Sources of Radiation in the Former Soviet Union," GAO/RCED-96-4, November 1995, p. 24.] {updated 5/17/01 DK}
FUEL: The RBT-10/1 reactor uses spent fuel from the SM-3 reactor,[1] containing 12 to 25kg of 50-85% HEU.[2]
Sources:
[1] Judith Perera, "RIAR Seeks Leading Research Role," Nuclear Engineering International, July 1998,  pp. 39-40.
[2] "Research Reactors in the Former Soviet Union," GAO/RCED-96-4 Nuclear Safety, p. 24  {Updated 6/24/99 VT; 6/1/01 DK}
OPERATOR: Minatom
COMMENTS:
This research reactor was commissioned in 1983.[1] The Scientific Research and Design Institute of Energy Technologies (NIKIET) designed the reactor.[1,2] This reactor is no longer operational.[3]
Sourced:
[1] List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.
[2] Judith Perera, "RIAR Seeks Leading Research Role," Nuclear Engineering International, July 1998,  pp. 39-40. {Updated 6/24/99 VT}
[3] "IAEA Research Reactor Database,"  IAEA Web Site, http://www.iaea.org/worldatom/rrdb/.{updated 1/2/01 DK}
 
NAME: RBT-10/2
TYPE: pool
[List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.]{updated 5/17/01 DK}
POWER: 7MWt
["IAEA Research Reactors Database," IAEA Web Site, http://www.iaea.org/worldatom/rrdb/.]
FUEL: The RBT-10/2 reactor uses spent fuel from the SM-3 reactor,[1] containing 18.4 to 50.7kg of 50-85% HEU.[2]
Sources:
[1] "IAEA Research Reactor Database," IAEA Web Site, http://www.iaea.org/worldatom/rrdb/.{updated 5/17/01 DK}
[2] Judith Perera, "RIAR Seeks Leading Research Role," Nuclear Engineering International, July 1998,  pp. 39-40. {Updated 6/24/99 VT}
OPERATOR: Minatom
COMMENTS:
This research reactor was commissioned in 1984.  The Scientific Research and Design Institute of Energy Technologies (NIKIET) designed the reactor.[1] The reactor has been used to investigate creep in VVER fuel element cladding materials.[2]
Sources:
[1] List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.]
[2] Judith Perera, "RIAR Seeks Leading Research Role," Nuclear Engineering International, July 1998,  pp. 39-40. {Updated 6/24/99 VT}
 
NAME: RBT-6
TYPE: pool
[List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.]
POWER: 6MW
FUEL: The RBT-6 reactor uses spent fuel from the SM-3 reactor.[1] According to the IAEA, the fuel is uranium enriched to 63%.[2]
Sources:
[1] US General Accounting Office, "Nuclear Safety:  Concerns with Nuclear Facilities and Other Sources of Radiation in the Former Soviet Union," GAO/RCED-96-4, November 1995, p. 24.]{updated 5/17/01 DK}
[2] "IAEA Research Reactor Database," IAEA Web Site, http://www.iaea.org/worldatom/rrdb/. {Updated 6/24/99 VT; 9/12/2001 KB} 
OPERATOR: Minatom
COMMENTS:
This research reactor was commissioned in 1975. The Scientific Research and Design Institute of Energy Technologies (NIKIET) designed the reactor.[1] All three RBT reactors are used for irradiation and testing of reactor materials and utilize spent fuel from the SM high-flux reactor. [2] A unique stand, called Korpus, has been added to RBT-6 to study materials in different neutron fluxes.[3]
Sources:
[1] List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.
[2] "Dimitrovgrad: Major Center for Russian Nuclear Research," Nucnet, 1 February 1996, p.9.
[3] Judith Perera, "RIAR Seeks Leading Research Role," Nuclear Engineering International, July 1998,  pp. 39-40. {Updated 6/24/99 VT}
 
NAME: BOR-60
TYPE: liquid metal
[List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.]
POWER: 60MWt, 10MWe
[SRIAR  homepage, http://www.niiar.simbirsk.su.]{Updated 7/12/99 VT}
FUEL: MOX fuel containing uranium enriched to 45-90 percent U-235
[SRIAR  homepage, http://www.niiar.simbirsk.su.] {Updated 7/12/99 VT}
OPERATOR: Minatom
COMMENTS:
This sodium-cooled fast breeder research reactor was commissioned in 1969.[1] The Scientific Research and Design Institute of Energy Technologies (NIKIET) designed the reactor.[1] BOR-60 was one of the first reactors of this type in the world to be used as a nuclear power plant.[2] The reactor was designed to test individual assemblies, whole complexes of equipment, control and measurement instruments, and sodium-water steam generators.[3] Yadernyy Kontrol reported that systematic research of plutonium fuel for the BOR-60 reactor began in 1970.[4] A number of fuel rods with various mixtures of plutonium MOX fuel have been tested in the BOR-60. (See the 1/99 developments entry for more information.) As an experimental heat-generating reactor, the BOR-60 provides heat and electricity to SRIAR and to the western part of Dimitrovgrad.[5,6]
Sources:
[1] List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.
[2] "Dimitrovgrad: Major Center for Russian Nuclear Research," Nucnet, 1 February 1996, p.9.
[3] Judith Perera, "RIAR Seeks Leading Research Role," Nuclear Engineering International, July 1998,  pp. 39-40.
[4] Valeriy Bogdan, Victor Murogov, Vladimir Kagramanyan, Mikhail Troyanov, "Use Of Plutonium In Russia," Yadernyy kontrol, November 1995, pp. 13-17. {Updated 6/24/99 VT}
[5] "Ulyanovskaya oblast. V NIIARe zavershilis planovo-profilakticheskiye raboty na reaktornoy ustanovke 'BOR-60'," Volgainform, 29 January 2001; in Integrum Techno, http://www.integrum.com
[6] "Dimitrovgrad otaplivayut plutoniyem," IMA-press, 30 January 2001; in Integrum Techno, http://www.integrum.com.{Updated 9/25/01 DK}

 
NAME: VK-50 (BWR)
TYPE: tank, boiling water
[List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.]
POWER: 200MWt
["IAEA Research Reactor Database," IAEA Web Site, http://www.iaea.org/rrdb.]{entered 5/17/01 DK}
FUEL: 1.5-2% enriched uranium
The core comprises 88 hexahedral fuel assemblies, each containing 162 fuel rods.
[Judith Perera, "RIAR Seeks Leading Research Role," Nuclear Engineering International, July 1998,  pp. 39-40.] {Updated 6/24/99 VT}
OPERATOR: Minatom
STATUS: Operational. The reactor was closed for brief periods in 1996 following two accidents.
[Judith Perera, "RIAR Seeks Leading Research Role," Nuclear Engineering International, July 1998,  pp. 39-40.]{Updated 6/24/99 VT}
COMMENTS:
This research reactor was commissioned in 1965. Scientific Research and Design Institute of Energy Technologies (NIKIET) designed the reactor. The VK-50 is used as an experimental heat-generating reactor.
[List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.]{Updated 6/24/99 VT}
 
NAME: ARBUS (formerly AST-1)
TYPE: organic coolant
[List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.]
POWER: 5.5 MW
[List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992]
COMMENTS:
According to Gosatomnadzor's list of reactors, this research reactor was commissioned in 1963. However, Nuclear Engineering International reports that a serious accident occurred in 1962, after which the reactor was rebuilt and restarted in 1979.[1,2] The Scientific Research and Design Institute of Energy Technologies (NIKIET) designed the reactor. It has been shut down and its core has been unloaded. AST-1 was used as an experimental heat-generating reactor.[1]
Sources:
[1] List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.
[2] Judith Perera, "RIAR Seeks Leading Research Role," Nuclear Engineering International, July 1998,  pp. 39-40. {Updated 6/24/99 VT}
 
NAME: Prima
COMMENTS:
The Scientific Research and Design Institute of Energy Technologies (NIKIET) created a design for this reactor, but the project has not moved past the development stage.[1,2]
Sources:
[1] List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.
[2] Judith Perera, "RIAR Seeks Leading Research Role," Nuclear Engineering International, July 1998,  pp. 39-40. {Updated 6/24/99 VT}
 
CRITICAL ASSEMBLIES: Two

Table II:  Critical Assemblies, Scientific Research Institute of Atomic Reactors, Dimitrovgrad
Unit Type Power Fuel Status
FM
 
100W
90% HEU (UO2 + Al)
operational
FM SM-2
 
100W
90 % HEU (UO2)
operational

NAME: FM
[List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.]
POWER: 100W
[International Institute for Applied Systems Analysis, "International Science and Technology Center Project #245 Radleg," 1996, Kurchatov Institute Web Site, http://www.kiae.ru/radleg/ch6e.htm.]{entered 11/13/00 DK}
FUEL: 90% HEU (UO2 + Al)
[International Institute for Applied Systems Analysis, "International Science and Technology Center Project #245 Radleg," 1996, Kurchatov Institute Web Site, http://www.kiae.ru/radleg/ch6e.htm.]{entered 11/13/00 DK}
APPLICATION:
This critical assembly is used for conducting critical experiments, simulating MIR-M1 core loading configurations, and researching loop experiments.
[International Institute for Applied Systems Analysis, "International Science and Technology Center Project #245 Radleg," 1996, Kurchatov Institute Web Site, http://www.kiae.ru/radleg/ch6e.htm.]{entered 11/13/00 DK}
 
NAME: FM SM-2
[List of Research Reactors, Critical and Subcritical Assemblies Supervised by Gosatomnadzor, 13 July 1992.]
POWER: 100W
[International Institute for Applied Systems Analysis, "International Science and Technology Center Project #245 Radleg," 1996, Kurchatov Institute Web Site, http://www.kiae.ru/radleg/ch6e.htm.]{entered 11/13/00 DK}
FUEL: 90 % HEU (UO2)
[International Institute for Applied Systems Analysis, "International Science and Technology Center Project #245 Radleg," 1996, Kurchatov Institute Web Site, http://www.kiae.ru/radleg/ch6e.htm.]{entered 11/13/00 DK}
APPLICATION:
This critical assembly is used for conducting critical experiments, simulating SM-3 core loading, and researching ampoule and loop facilities
[International Institute for Applied Systems Analysis, "International Science and Technology Center Project #245 Radleg," 1996, Kurchatov Institute Web Site, http://www.kiae.ru/radleg/ch6e.htm.]{entered 11/13/00 DK}
 
ARCHIVED SRIAR DEVELOPMENTS
(For more recent developments, see the Research Facilities with Reactors and Critical/Subcritical Assemblies Developments file):

2/3-7/2003: MEETING OF RUSSIAN-FRENCH WORKING GROUP ON TRANSMUTATION HELD AT SRIAR
On 3-7 February 2003, a regular meeting of the Russian-French working group "Fuel and Materials" was held at SRIAR. This group was created by Minatom and the French Atomic Energy Commission (CEA) to study ways to process irradiated fuel and waste. According to the Nuclear.ru web site, a possible way to decrease the environmental impact of long-lived minor-actinides (americium, neptunium, curium) and fission products in irradiated fuel could be their transmutation and incineration in a special "burnout" fast neutron reactor. The Russian-French joint research program achieved progress in the development, manufacture, and reactor tests of promising fuel compositions. SRIAR has tested the first lot of uranium-neptunium fuel in the BOR-60 reactor and achieved a high degree of fuel burnout. In 2003, the Institute plans to test fuel compositions with another minor-actinide, americium.
["
V GNTs RF NIIAR proshlo rabocheye zasedaniye rossiysko-frantsuzskoy gruppy po problemam transmutatsii," 11 February 2003 News, Nuclear.ru Web Site, http://www.nuclear.ru.] {Entered 4/3/2003 NL}

9/3/2002: IAEA EXPERTS CHECK SECURITY OF YUGOSLAV FUEL
On 2-3 September 2002, experts from the IAEA visited SRIAR to inspect fuel transported from Yugoslavia at the end of August 2002. The experts found no variations between the results of the inspection and the consignment registration information (mass and enrichment of the fuel). They confirmed that the fuel is stored securely. [For more information, see the 8/22/2002 entry below.]
[Nuclear.ru Web Site; in FBIS Document CEP20020909000119.] {Entered 9/25/02 NL}

8/22/2002: SRIAR ACCEPTS 800KG OF NUCLEAR FUEL FROM BELGRADE
In a tripartate Russian-US-IAEA operation on 26 August 2002, 800kg of nuclear fuel, including 48.5kg of highly enriched uranium, was transferred from the Vinca Institute in Belgrade to Dmitrovgrad to be reprocessed at SRIAR reactors.[1] This effort was undertaken as part of the IAEA Action Plan against nuclear terrorism approved by IAEA's Board of Governors in March 2002.[2] The fuel for research reactors was originally supplied to Yugoslavia by the Soviet Union during the 1980s. After the Vinca reactors came to a standstill in 1984, fuel that had not been used was kept at the premises of the Vinca Institute, presenting an easy target for theft. The Yugoslav government could not ensure the proper level of security and, after the fall of the Milosevic regime, decided to get rid of the fuel. Russia agreed to repatriate and reprocess the fuel. The transportation costs were covered by the United States; a large part of the funds designated for the environmental cleanup in Yugoslavia was provided by the Nuclear Threat Initiative.[3,4] HEU from Yugoslavia will be turned into low-enriched uranium in SRIAR reactors making the material impossible for use in developing nuclear weapons. SRIAR is to receive $0.5 million for reprocessing the material.[5] The SRIAR press service reports that the LEU fuel that will be obtained from the Yugoslav HEU fuel is enough to run one reactor for one year. Transportation of nuclear fuel from abroad sparked protests in Ulyanovsk oblast. SRIAR made assurances that they received fresh fuel that had not been used in reactors, that the fuel does not contain plutonium, and that it is not highly radioactive. SRIAR is willing to participate in future IAEA programs for recycling nuclear fuel that can be used by terrorists. Nuclear fuel of Soviet origin from Vietnam, Uzbekistan, and Belarus is to be brought to Russia in the near future.[5]
Sources:
[1] "Novosti 26.08.2002," SRIAR Web Site, http://www.niiar.simbirsk.su/rus/nsr.htm.
[2] "IAEA Action Plan to combat nuclear terrorism," IAEA Web Site, http://www.iaea.org/worldatom/Press/Focus/Nuclear_Terrorism/.

[3] Michael Evans, "US and Russia in raid to snatch Serb uranium," The Times (London), 24 August 2002; in Lexis-Nexis Academic Universe, http://web.lexis-nexis.com.
[4] "NTI Commits $5 Million To Help Secure Vulnerable Nuclear Weapons Material," NTI Web Site, http://www.nti.org.
[5] "Segodnya news," NTV Mir, 3 September 2002; in "Enriched uranium from Yugoslavia delivered to Russia for recycling," FBIS Document CEP20020903000365. {9/25/02 NL}

9/5/2001: SRIAR AND JNC SIGN AN AGREEMENT ON MOX RESEARCH
On 5 September 2001 VolgaInform reported that the All-Russian Scientific Research Institute of Atomic Reactors (SRIAR) and the Japan Nuclear Cycle Development Institute (JNC) had signed an agreement to conduct joint research on vibrocompacted MOX fuel. According to the agreement, SRIAR will build an experimental line for the production of granulated fuel and fuel rods. For additional information on SRIAR-JNC cooperation in the area of MOX research, see the 5/18/99 entry below.
["Ulyanovsk. Novyye razrabotki v sfere mirnogo ispolzovaniya oruzheynogo plutoniya nachalis v dimitrovgradskom GNTs RF NII atomnykh reaktorov," VolgaInform, http://www.volgainform.ru/forprint/9571/, 9 September 2001.] {entered 10/2/2001 DK}
 
9/3/2001: MINISTER OF INDUSTRY, SCIENCE, AND TECHNOLOGIES VISITS SRIAR
During a two-day trip to Ulyanovsk Oblast, Russian Minister of Industry, Science, and Technologies Aleksandr Dondukov visited SRIAR. Dondukov agreed to provide government aid to SRIAR and to preserve the institute's status as a State Scientific Center. He lent his support to the proposed creation of a scientific-industrial complex comprised of SRIAR, Ulyanovsk State University, and the Aviastar aviation production facility.
["Ulyanovsk. Zakonchilsya vizit ministra promyshlennosti, nauki i tekhnologiy RF Aleksandra Dondukova," VolgaInform, http://www.volgainform.ru/forprint/9507/, 3 September 2001.] {entered 10/2/2001 DK}
 
6/2001: SRIAR SELLS PLUTONIUM OXIDE SALTWASHER TO LAWRENCE LIVERMORE NATIONAL LABORATORY
In June 2000 the Lawrence Livermore National  Laboratory (LLNL) purchased a plutonium saltwasher from SRIAR.  This purchase was a part of US-Russian plutonium disposition cooperation.  The equipment will wash plutonium oxides free of contaminating chloride salts, so that plutonium can be immobilized and stored until final disposal.  According to LLNL representatives, this automated piece of equipment, made of stainless steel and titanium, is faster and more efficient than LLNL's current systems.  This is the first Russian-made plutonium processing equipment to be used at LLNL.
["Russian Machine Puts Out the Wash with U.S. Plutonium," Lawrence Livermore National Laboratory Web Site, http://www.llnl.gov/llnl/06news/
NewsReleases/2000/NR-00-06-01.html.] {entered 9/28/01 DK}

 
2/20/2001: ULYANOVSK OBLAST AND MINATOM SIGN AN AGREEMENT ON SRIAR
On 20 February 2001, Russian Minister of Atomic Energy Yevgeniy Adamov and Ulyanovsk Oblast Governor Vladimir Shamanov signed an agreement stipulating the full use of SRIAR's scientific potential.[1] According to the agreement, Minatom will coordinate its programs for SRIAR with the Ulyanovsk Oblast administration.  The appointment or firing of SRIAR's director will require consultation with the Ulyanovsk Oblast governor.  Ulyanovsk Oblast will provide financial and other support for Minatom facilities located in the region.[2]
Sources:
[1]"Moskva. Podpisano soglasheniye mezhdu Minatomom Rossii i administratsiyey oblasti, predusmatrivayushcheye maksimalnoye ispolzovaniye nauchnogo potentsiala dimitrovgradskogo NIIARa," VolgaInform, http://www.volgainform.ru/forprint/6014/, 21 February 2001.
[2]"GNTs RF NIIAR," Ministry of Atomic Energy of Russia Web Site, http://www.minatom.ru/presscenter/text.php?ssd=3010.txt. {entered 10/2/2001 DK}
 
1/2001: FINANCIAL SITUATION AT SRIAR STABLE  
On 22 January 2001 Izvestiya reported that the financial situation at SRIAR was stable. Wages are being paid regularly and were far above average for the region where the institute is located.  SRIAR experienced a financial crisis in the early 1990s, which resulted in 1500 employees leaving the institute.  The improvement of the institute's financial situation was largely due to the sale of isotopes produced by the institute from weapons-grade plutonium.  Each year SRIAR sells $7 million worth of isotopes to international buyers. 
[Sergey Leskov, "Uranovaya Mekka; sposobny li vysokiye tekhnologii stat v prirode vezhlivym gostem," Izvestiya, 20 January 2001; in Integrum Techno, http://www.integrum.ru.] {updated 9/25/01 DK}
 
10/9/2000: INTERNATIONAL WORKING GROUP ON FAST REACTORS MEETS AT SRIAR
From 9 to 15 October 2000, SRIAR hosted a meeting of a Russian-French working group on the operation of fast reactors.  The working group is one of  nine that were created in accordance with a 1993 agreement on the exchange of information related to fast reactors between the Ministry of Atomic Energy of Russia and the Commission on Atomic Energy of France.
["Novosti," SRIAR Website, http://www.niiar.simbirsk.su/rus/nsr_arh.htm.] {entered 9/28/01 DK}
 
10/2000: MORE THAN 100KG OF PLUTONIUM CONVERTED AT SRIAR  
As of October 2000, SRIAR had converted more than 100kg of weapons-grade plutonium to reactor fuel. SRIAR is the leading research center in Russia in the area of using plutonium for producing nuclear energy.  The institute converts weapons-grade plutonium to MOX fuel for use in its BOR-60 research reactor.  According to SRIAR Director Aleksey Grachev, the institute plans to produce annually up to 40 fuel assemblies (25-35kg Pu) for its BOR-60 reactor and four to 10 fuel assemblies (25-60kg Pu) for the BN-600 reactor at the Beloyarsk nuclear power plant.  Many Russian environmental nongovernmental organizations oppose SRIAR's MOX program.
["Oruzheynyy Plutoniy: 'Tayny' NIIARa," Grazhdanskaya Initsiativa, No.2 (6), October 2000, pp. 4-7.] {entered  9/25/01 DK}
 
9/30/99: RICHARDSON VISITS SRIAR
On 30 September, a delegation led by US Secretary of Energy Bill Richardson visited SRIAR where they were shown advanced weapons-grade plutonium processing technology and discussed an agreement for cooperation between the US Department of Energy and the Institute.
["Energetiki SShA obsuzhdayut vozmozhnost sotrudnichestva s rossiyskimi yadershchikami," Interfax, 30 September 1999.] {Entered 12/7/99 LWB}
 
5/18/99: JAPAN AND RUSSIA TO COOPERATE ON PU CONVERSION RESEARCH
On 18 May 1999, the All-Russian Scientific and Research Institute of Atomic Reactors (SRIAR) and the Japan Nuclear Cycle Development Institute (JNC) signed a five-year contract on joint research on the conversion of excess weapons-grade plutonium into MOX fuel. By 2003, about 20kg of plutonium will be used in this research. Russia will produce MOX fuel using its vibration compaction technology and burn it in the BN-600 fast-breeder reactor. Then the efficiency of this method of plutonium disposition will be tested in post-irradiation experiments.[1] Japan will invest about $1.7 million into the implementation of this contract, and send experts to Russia.[2,3] Both countries will own the results of this research. The further development of this technology will make possible the disposition of 1.3MT of plutonium per year.[3] According to Nihon Keizai, Japan and Russia, in partnership with France, will conduct a feasibility study for the construction of a MOX fuel burning reactor.[4]
Sources:
[1] "Joint Russian-Japanese Research for Disposition of Excess Plutonium from Nuclear Dismantlement: JNC-Russian Research Institute Contract to Burn About 20kg in Fast-breeder Reactor," Genshiryoku Sangyo Shimbun, 27 May 1999, p. 1.
[2] Anatoliy Krasnov, ITAR-TASS, 19 May 1999; in "Russia, Japan Sign Accord on Weapons-Grade Plutonium," FBIS Document FTS19990519001527.
[3] Andrey Ilyashenko, RIA Novosti, 18 May 1999; in "Russia, Japan To Use Weapons-Grade Plutonium For Power," FBIS Document FTS19990518000294.
[4] "France, Japan and Russia Co-operate on 'breeder'," Bellona Nuclear Chronicle From Russia, April/May 1999, p. 10. {Entered 6/22/99 VT}
 
5/99: ENVIRONMENTALISTS CONCERNED ABOUT WEAPONS PU CONVERSION AT SRIAR
The environmental organization Center for Assistance to People's Initiatives, in partnership with other environmental organizations, is concerned about the conversion of weapons-grade plutonium into nuclear reactor fuel at SRIAR. The groups plan to disseminate information on SRIAR activities to residents of the Povolzhye region. According to Mikhail Piskunov of AVE-info, the environmentalists suggest that weapons-grade plutonium be buried with other highly radioactive waste.[1] According to Ivan Miroshnikov, Chief State Inspector of the Oblast Committee for Environmental Protection, SRIAR's new plutonium conversion technology is cleaner and more environmentally safe than others used at SRIAR. He added that SRIAR is only interested in selling the results of its research, and does not use plutonium in industrial units. Ivan Pogodin, chairman of the Ulyanovsk Oblast legislative assembly's committee on the environment, sent inquiries to the Environmental Prosecutor and SRIAR Director Aleksey Grachev, asking whether the new technological process had been approved by a State Environmental Impact Study. Both the Environmental Prosecutor's office and SRIAR are currently studying the environmental impact of the new technology.[2] Another SRIAR activity that concerns environmentalists is the disposal of liquid radioactive waste in deep geological formations, including water-bearing strata. Piskunov states that official documents state that all aquifers used by Dimitrovgrad are outside SRIAR's "sanitary zone."  Piskunov, however, states that the main source of Dimitrovgrad's water supply is only 2-2.5km from waste-disposal boreholes.[3]
Sources:
[1] Mikhail Piskunov, "Strashnaya Ugroza Navisla," Zelenyy Mir, No. 12, 25 May 1999, p. 2.
[2] Yelena Fadeyeva, "NIIARu Snova Grozit Skandal," Simbirskiy Kuryer, 4 February 1999, p. 1; in WPS Yadenyye Materialy, No. 7, 19 February 1999.
[3] Mikhail Piskunov, "Smertonosnoye Nasledstvo," Yadernaya bezopasnost, No. 9-10, February-March 1998, p. 10. {Entered 6/21/99 VT}
 
4/3/99: JAPAN WANTS TO HELP RUSSIA REPROCESS ITS WEAPONS-GRADE  PLUTONIUM
According to Mr. Yamato, a member of the Japan Nuclear Cycle Development Institute (JNC) board of directors, and Mr. Tsutomu Imamura, deputy director general of the Science and Technology Agency (STA), Japan and Russia are in the process of concluding an agreement on disposition of plutonium from dismantled nuclear weapons.[1] According to the 3 April 1999 issue of Nihon Keizai Shimbun, the STA has already sent the Russian Ministry of Atomic Energy a plan for cooperation in carrying out this agreement.[2] Under the agreement, the JNC will assist Russia in remodeling the core of the BN-600 fast breeder reactor (FBR) at the Beloyarsk NPP so that it can be loaded with mixed oxide (MOX) fuel.[1,2] The primary objective is to help Russia burn a total of 20 MT of excess plutonium in the BN-600 reactor by 2020 and reduce the proliferation risk by converting weapons-grade plutonium removed from dismantled Russian nuclear weapons into fuel for nuclear power stations.[1,3] The first stage of the conversion requires the All-Russian Scientific and Research Institute of Atomic Reactors (SRIAR) in Dimitrovgrad to increase its annual manufacturing capacity four to five times in order to process weapons-grade plutonium into enough MOX fuel, using vibration packing technology. By 2002, the second stage of the project, converting 20 percent of the BN-600 core to use MOX fuel, will be completed. At that point, the reactor will burn 0.3 MT of plutonium annually.[4] In the last stage, the entire core will be converted to use MOX fuel. When this process is finished, 1.3 MT of plutonium will be burned per year.[1] Japan is also interested in acquiring the technology for this "advanced recycling system." According to Anatoliy Zrodnikov, Director of the Obninsk Institute of Physics and Power Engineering (IPPE), JNC will conduct joint research with IPPE on the vibration packing processing technology.[4]
Sources:
[1]"JNC to Help Dispose of Pu from Dismantled Russian Weapons," Atoms in Japan, April 1999, p. 10.
[2] "Japan Offers Russia Plutonium Recycling Project," BBC Soviet Union Economic, 5 April 1999; in Inquisit Agent Report, http://www.inquisit.com/.
[3] Vladimir Solntsev, "Russia, Japan to research into reprocessing plutonium," ITAR-TASS, 5 February 1999; in Lexis-Nexis Academic Universe, http://web.lexis-nexis.com/.
[4] Nikkan Kogyo Shimbun, 24 February 1999; in "STA To Help Russia Process 0.3 Ton of Plutonium Annually," FBIS Document FTS 19990316001878. {Entered 5/24/99 VT}
 
1/99: SRIAR WILL EXPORT FUEL RODS TO JAPAN
The All-Russian Scientific and Research Institute of Atomic Reactors (SRIAR) signed a contract worth $1 million for supplying fuel rods to Japan in January 1999.  The fuel rods are to be manufactured from weapons-grade plutonium.  SRIAR, which was recently conferred the status of State Research Center, is actively exploring international markets.
["Yapontsy Zrya Ne Platyat," Rossiyskaya gazeta, 9 June 1999.]{entered 7/7/99 FW}
 
1/99: SRIAR TURNS WEAPONS PLUTONIUM INTO REACTOR FUEL FOR THE FIRST TIME
For the first time, scientists at SRIAR were able to use weapons-grade plutonium in fuel elements for the BOR-60 heat-generating fast neutron nuclear reactor.[1] They have processed eight kilograms of plutonium into MOX fuel, and have used it to heat the institute building and adjacent residential areas since the beginning of January 1999, and it will be enough to heat them until April, according to ITAR-TASS.[2] However, SRIAR director Aleksey Frolovich Grachev said that the fuel elements would stay in the BOR-60 reactor for at least two years.[1] SRIAR scientists used a new "dry" technology to turn weapon-grade plutonium into fuel for nuclear reactors. This technology is pyrochemical, and materials are heated to extremely high temperatures. It reduces the amount of waste to be disposed of because it uses very little liquid, it is much cheaper than the "wet" technology currently in use, and can operate on a small scale.[2] The MOX fuel is in the form of "densified" (presumably high-density) powder, which ecologically is much safer and economically more advantageous than pellets. Grachev said that SRIAR might prepare several fuel assemblies for the BN-600 fast reactor at the Beloyarsk NPP, which will use MOX fuel.[1]
Sources:
[1] Nikolay Senchev, "Made in Russia," Rossiyskaya Gazeta, 21 January 1999; in "Incineration of weapon-grade plutonium," FBIS Document FTS19990201001047.
[2] "Making Fuel from Warheads," BBC News, online edition, http://news.bbc.co.uk/, 5 January 1999. {Entered 5/24/99 VT}
 
2/18/98: DEPUTY KRUGLIKOV SUBMITS FUNDING REQUEST
On 18 February 1998, Duma Deputy A.L. Kruglikov requested that Russian Prime Minister Viktor Chernomyrdin obtain 6-8 million rubles (approximately $988,800 to $1.32 million) to repair and rebuild SRIAR. Radioactive gas discharges in 1996 and 1997 resulted in damage to the facility.  Federal, regional, and municipal government bodies owe SRIAR a total of over 60 billion nondenominated rubles as payment for heat and electricity it produced.  Additionally, SRIAR's seven nuclear reactors depend on power generated by institute turbogenerators and boilers for safe operations.  The institute is responsible for providing heat to 55,000 residents of Dimitrovgrad and is unable to fulfill its obligations.
[Deputatskiy Zapros No. VS-9836k To V.S. Chernomyrdin from A.L. Kruglikov, 18 February 1998] {Entered 1/29/99 LBB}
 
11/28/97: ENGINEER EXPOSED TO RADIATION AT SRIAR
On 28 November1997, an engineer at SRIAR was exposed to 3.5 rem of radiation.  According to Minatom spokesman Georgiy Kaurov, the accident occurred because of a gross violation of safety rules.  The engineer was not hospitalized.  The accident was registered by the institute's radiation-monitoring system.
[Interfax, 28 November 1997; in "Russian Engineer Exposed to Radiation in Research Institute," FBIS-SOV-97-334.] {Entered 2/24/98 IY}
 
7/25/97: MIR REACTOR DISCHARGES IODINE-131
On the night of 25 July 1997, the MIR reactor at SRIAR began discharging radioactive gases.[1,2]  The discharge lasted over a period of ten days.[2]  Experts do not know the exact cause of the accident but suspect that it occurred because of  improperly sealed fuel rods.  On the night of the accident, fuel assemblies were scheduled to be reloaded.  In compliance with the standard procedure, the water from the primary circuit was drained into a pool.  The pool began to emit inert gases followed by the extremely harmful radioactive isotope iodine-131. The iodine-131 was discharged through the ventilation system and spread over hundreds of kilometers in the surrounding area.[1,2]  For several days the level of iodine-131 in the air exceeded the maximum permitted concentration established by SRIAR by a factor 15 to 20.[1]  The local population was not warned about the radioactive discharge, and no preventive measures were taken, because environmental oversight agencies in Dimitrovgrad do not have the necessary equipment to measure the radioactive background.  Officials used ordinary personal dosimeters, which are not capable of measuring the level of iodine-131.
Sources:
[1] Mikhail Piskunov, "ChP v yadernom tsentre," Agenstvo Volzhskoy ekologicheskoy informatsii, 30 July 1997.
[2] Mikhail Piskunov, "Deadly Camouflage.  Nuclear Center in Central Volga Region Poses Threat to Population," Rossiyskiye Vesti, 15 August 1997, p. 2; in " Dimitrovgrad nuclear power woes," FBIS-SOV-97-238.  {Entered 11/20/97 IY}
 
3/96: FIRE CAUSES SHUTDOWN
The VK-50 reactor was shut down indefinitely after an air conditioner in the reactor building caught fire. This was the second accident in less than two months.
["Dimitrovgrad Reactor Shut Down Indefinitely," Post-Soviet Nuclear & Defense Monitor, 5 April 1996, p.13.]

1/31/96: ACCIDENT AT VK-50 REACTOR CAUSES RADIOACTIVE RELEASE
An accident occurred at the VK-50 reactor, followed by the release of a radioactive mix into the atmosphere. A safety precaution valve was activated, reducing pressure in the reactor, causing an emergency shutdown which resulted in the leakage of 100 tons of a steam and gas mixture which measured at 100 millicuries, contaminating some 200 sq. meters around the facility. According to official reports, 80 percent of the discharge was made up of manganese-56, which has a half-life of only 2.5 hours. A. Baryshev, Deputy Chief Engineer, blamed the incident on personnel error. By 1 February 1996, the radiation level in the contaminated area had fallen to 30-40 microroentgens per hour. The accident rated a one according to the INES scale. During January 1996, the reactors underwent three additional unplanned shutdowns.
Sources:
[1]"All Is Quiet In Dimitrovgrad," Komsomolskaya pravda, 3 February 1996, p. 1.
[2] "Russia: Official: 10 Sq. Km. Of Dimitrovgrad Contaminated," FBIS-SOV-96-023, 1 February 1996.
[3] "Russia: Radiation Level In Dimitrovgrad Complex Is Normal," FBIS-SOV-96-023, 1 February 1996.
[4] "Russia: Dimitrovgrad Incident Blamed On Personnel," FBIS-SOV-96-023, 1 February 1996.
[5] "Russia: Details Of Dimitrovgrad Leak, Aftermath Reported," FBIS-SOV-96-023, 2 February 1996.
[6] "Consequences Of Radioactive Emission In Ulyanovsk Region Are Eliminated," Izvestiya, 2 February 1996, p. 2.
[7] "Radiation In Dimitrovgrad Escaped But Not For Long," Rossiyskaya gazeta, 2 February 1996, p. 3.
[8] "En Russie, un nuage de gaz radioactif s'est echappe d'un centre d'essais," Le Monde, February 1996, p. 15.

Last updated 9 March 2004 
For recent developments, see the Research Facilities with Reactors and Critical/Subcritical Assemblies Developments file.

Comments or questions? Contact Kenley Butler at MIIS CNS: Kenley.Butler@miis.edu


CNSThis material is produced independently for NTI by the Center for Nonproliferation Studies at the Monterey Institute of International Studies and does not necessarily reflect the opinions of and has not been independently verified by NTI or its directors, officers, employees, agents. Copyright © 2002 by MIIS.

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