RIAR

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The Research Institute of Atomic Reactors ( RIAR / Research Institute of Atomic Reactors for short ; Russian: Научно-исследовательский институт атомных реакторов ) is an institute for reactor research in Dimitroviangrad (formerly Melekess ) in the Oblastian Oblast . The institute owns eight nuclear reactors : SM, ARBUS (ACT-1), MIR.M1, RBT-6, RBT-10/1, RBT-10/2, BOR-60 and VK-50. All reactors are experimental research reactors. The institute has mainly dealt with the problem of nuclear energy since the 1950s.

history

The institute was founded in 1954 shortly after the commissioning of the first nuclear power plant in Obninsk to research the problems of nuclear energy. Several facilities were built, including special buildings for recycling nuclear fuel to reduce the amount of nuclear waste.

In October 1961 the first research reactor called SM was put into operation. In 1992 this reactor was upgraded to a modern safety level. It is intended for the irradiation of materials with neutrons in order to test the effects on them. The reactor can also be used to study the neutron flux through fuel elements.

In 1963, the ARBUS (ACT-1) nuclear reactor went into operation. This is an organically cooled reactor.

In January 1964 the first phase of the Materials Science complex went into operation. The second phase of the complex was built for the non-destructive investigation of full-scale fuel assemblies. The complex makes it possible to simulate the full cycle of a reactor and to test different materials for heat resistance, flux density and neutron spectrum. Fuel elements from VVER reactors, RBMK reactors and BN reactors can also be tested in this complex. The equipment is also sufficient to study the behavior of the reactor core as well as the functions of fuel assemblies in emergency situations and the disposal of fused fuel assemblies from a reactor core.

Shortly afterwards the radiochemical complex was put into operation. In this complex, the reprocessed fuel elements are studied and the behavior of the radionuclides and their benefits for nuclear medicine are investigated.

On May 18, 1965, the VK-50 reactor went into operation. This is an experimental but commercial reactor and has therefore been registered with the IAEA. The thermal power of the reactor was 270 MW. In 1989 it was shut down. Ultimately, this resulted in the VK-300 reactor with a capacity of 300 megawatts. This is to be used commercially for the first time in the Northwest nuclear power plant , which is to be commissioned in 2011 as part of the 2007-2015 project . Today the VK-50 is back in operation and provides district heating for the city of Dimitrovgrad and electricity for the surrounding area. This reactor is currently the only thermal nuclear power plant in the world.

In December 1966 the MIR.M1 reactor went into operation. In 1979 the structure of the facility was redesigned. This reactor is one of the largest in the world. Its purpose is to develop new fuel tablets for future nuclear power plants.

In December 1969, the reactor BOR-60 ( Bystrij Opytnyj Reaktor ; freely translated, fast experimental reactor ) was put into operation. The reactor is a breeder reactor . This should serve for the better research of breeder reactors and the neutron technology. The reactor is cooled with sodium. The reactor is used to test new fuel for breeder reactors. Among other things, the fuel was developed in this reactor for the not yet commercially used BREST breeder reactor . When the reactor is in normal operation, it uses a fuel specially developed for that reactor, simply called BOR-60 fuel.

In 1975 the RBT-6 went into operation. This reactor is one of the pool-type reactors ( swimming pool reactor ). He should irradiate samples of structural materials and determine changes. In 1983 and 1984 the reactors RBT-10/1 and RBT-10/2 went into operation. These are further developments of the RBT-6 .

In 1977 the chemical-technical complex was put into operation. This is the only one in the world. Research is being conducted there into how nuclear fuel could be reprocessed by melting salt.

Today all systems are still or are in operation again. The KNK II in Germany was created on the basic model of the BOR-60. The BOR-60 is considered a revolution in breeder reactor technology. Almost all breeder reactors worldwide are based on this principle.

Accidents

The worst incident to date occurred in the VK-50. On May 7, 1966, there was a performance excursion through fast neutrons. The shift supervisor received a high dose of radioactivity. The incident was rated INES 3 to 4.

Data of the reactors

reactor Reactor type thermal power Net power Gross output start of building Start of operations (Shutdown) shutdown
SM PRESS. VESSEL 100 MWt - - 01/01/1956 01/10/1961 -
ARBUS (ACT-1) TANK 12 MWt - - 01/01/1963 01/01/1963 05/01/1988
VK-50 VK reactor 200 MWt 50 MW 62 MW 10/01/1965 01/01/1966 01/01/1989
MIR.M1 Swimming pool / channels 100 MWt - - 01/01/1958 December 01, 1966 -
BOR-60 Fast breeder 60 MWt 10 MW 12 MW 07/01/1965 December 01, 1969 -
RBT-6 swimming pool 6 MWt - - 10/10/1970 01/10/1975 -
RBT-10/1 swimming pool 10 MWt - - 07/01/1982 December 01, 1983 (03/01/1994)
RBT-10/2 swimming pool 7 MWt - - 06/01/1983 December 01, 1984 -

See also

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  1. Research Reactor Database (RRDB) of IAEA
  2. a b c d e f g h i j k History of the Institute (English) ( Memento from April 24, 2009 in the Internet Archive ).
  3. Nuclear power plants with boiling water reactors for electricity generation (English) (PDF)
  4. World Nuclear Association (English)
  5. ^ IAEA: Nuclear Knowledge Management.
  6. IAEA: Summary of all reactors and their status (PDF)
  7. IAEA: Information on Fast Breeders in the World (English) (PDF)
  8. IAEA: Status of National Programs on Fast Breeder Reactors (PDF) (English)
  9. IAEA: Commissioning and planning of the KNK and in comparison with other reactors (PDF)
  10. Mikhail V. MALKO: The Chernobyl Reactor: Design Features and Reasons for Accident
  11. ^ IAEA: The VK-50 at the PRIS of the IAEA ( Memento from December 24, 2008 in the Internet Archive )
  12. a b This reactor is registered with the IAEA as both a commercial reactor and a research reactor.
  13. Initial phases of development and mastering SFR technology BOR -60
  14. Prolongation of the BOR-60 reactor operation doi : 10.1016 / j.net.2015.03.002

Web links

Coordinates: 54 ° 11 ′ 4 ″  N , 49 ° 28 ′ 1 ″  E