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BN-600 reactor

The BN-600 reactor is a sodium-cooled fast breeder reactor, built at the Beloyarsk Nuclear Power Station, in Zarechny, Sverdlovsk Oblast, Russia. Designed to generate electrical power of 600 MW in total, the plant dispatches 560 MW to the Middle Urals power grid. It has been in operation since 1980 and represents an evolution on the preceding BN-350 reactor. In 2014, its larger sister reactor, the BN-800 reactor began operation.

Main building of Beloyarsk Nuclear Power Station as seen from the Beloyarskoye Reservoir near Zarechny, Sverdlovsk Oblast, Russia. Beloyarsk has the largest fast breeder reactor, the (BN-600), at 600 MW it is the second-most powerful breeder in the world. Construction of a second breeder reactor, the BN-800 reactor, was completed in 2016.
A cutaway model of the reactor. The core, that is the nuclear fuel at the heart of the reactor has dimensions of 2 meters in height by 0.75 meters in diameter, similar to the BN-800 reactor.[1]

The plant is a pool type LMFBR, where the reactor, coolant pumps, intermediate heat exchangers and associated piping are all located in a common liquid sodium pool. This is essentially the same general design as EBR-II, which went into service in 1963. The reactor system is housed in a concrete rectilinear building, and provided with filtration and gas containment features. In the first 15 years of operation, there have been 12 incidents involving sodium/water interactions from tube breaks in the steam generators,[2] a sodium-air oxidation/"fire" from a leak in an auxiliary system, and a sodium "fire" from a leak in a secondary coolant loop while shut down. All these incidents were classified at the lowest level on the International Nuclear Event Scale, and none of the events prevented restarting operation of the facility after repairs. As of 1997, there had been 27 sodium leaks, 14 of which resulted in sodium-air oxidations/"fires". The steam generators are separated in modules so they can be repaired without shutting down the reactor.[3] As of 2020, the cumulative "energy Availability factor" calculated up to year 2019 and recorded by the IAEA was 75.6%.[4]

The reactor core is 1.03 meters tall with a diameter of 2.05 meters.[5] It has 369 fuel assemblies, mounted vertically, each consisting of 127 fuel rods enriched to between 17–26% 235U. In comparison, normal enrichment in other Russian reactors is between 3–4% 235U. The control and scram system comprises 27 reactivity control elements including 19 shimming rods, two automatic control rods, and six automatic emergency shut-down rods. On-power refueling equipment allows for charging the core with fresh fuel assemblies, repositioning and turning the fuel assemblies within the reactor, and changing control and scram system elements remotely.

The unit employs a three-circuit coolant arrangement; sodium coolant circulates in both the primary and secondary circuits. Water and steam flow in the third circuit. The sodium is heated to a maximum of 550 °C in the reactor during normal operations. This heat is transferred from the reactor core via three independent circulation loops. Each comprises a primary sodium pump, two intermediate heat exchangers, a secondary sodium pump with an expansion tank located upstream, and an emergency pressure discharge tank. These feed a steam generator, which in turn supplies a condensing turbine that turns the generator.

There is much international interest in the fast-breeder reactor at Beloyarsk. Japan has its own prototype fast-breeder reactors. Japan paid 1 billion[6][clarification needed] for the technical documentation of the BN-600. The operation of the reactor is an international study in progress; Russia, France, Japan, and the United Kingdom currently participate.

The reactor has been licensed to operate up to 2025.[7]

See also

References

  1. ^ "Fast Neutron Reactors - article from World-Nuclear".
  2. ^ "12 water-into-sodium leaks occurred; from google (bn-600 tube leak) result 5" (PDF).
  3. ^ Frank von Hippel; et al. (February 2010). Fast Breeder Reactor Programs: History and Status (PDF). International Panel on Fissile Materials. ISBN 978-0-9819275-6-5. Retrieved 28 April 2014.
  4. ^ "Beloyarsk-3". PRIS. IAEA. Retrieved 17 September 2020.
  5. ^ Status of Fast Reactor Research and Technology Development (PDF). International Atomic Energy Agency. 2012. p. 130. ISBN 978-92-0-130610-4. Retrieved 11 November 2014.
  6. ^ Bellona Foundation, an international environmental NGO based in Norway. . Archived from the original on 2013-11-10.
  7. ^ "Russian Fast Reactor Connected to the Grid". powermag.com. 1 February 2016. Retrieved 22 April 2018.

External links

  • Overview of Fast Reactors in Russia and the Former Soviet Union
  • BN-600 Hybrid Core Benchmark Analyses (IAEA TECDOC 1623)
  • BN-600 Fuel (Russian firm that produces fuel for the BN-600)
  • Liquid Metal Cooled Reactors: Experience in Design and Operation (IAEA TECDOC 1529)
  • Operating experience from the BN600 sodium fast reactor, IAEA
  • Assessment of changes to the BN-600 to operate with a plutonium burner core

Coordinates: 56°50′30″N 61°19′21″E / 56.8416°N 61.3224°E / 56.8416; 61.3224

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This article includes a list of general references but it lacks sufficient corresponding inline citations Please help to improve this article by introducing more precise citations July 2009 Learn how and when to remove this template message The BN 600 reactor is a sodium cooled fast breeder reactor built at the Beloyarsk Nuclear Power Station in Zarechny Sverdlovsk Oblast Russia Designed to generate electrical power of 600 MW in total the plant dispatches 560 MW to the Middle Urals power grid It has been in operation since 1980 and represents an evolution on the preceding BN 350 reactor In 2014 its larger sister reactor the BN 800 reactor began operation Main building of Beloyarsk Nuclear Power Station as seen from the Beloyarskoye Reservoir near Zarechny Sverdlovsk Oblast Russia Beloyarsk has the largest fast breeder reactor the BN 600 at 600 MW it is the second most powerful breeder in the world Construction of a second breeder reactor the BN 800 reactor was completed in 2016 A cutaway model of the reactor The core that is the nuclear fuel at the heart of the reactor has dimensions of 2 meters in height by 0 75 meters in diameter similar to the BN 800 reactor 1 The plant is a pool type LMFBR where the reactor coolant pumps intermediate heat exchangers and associated piping are all located in a common liquid sodium pool This is essentially the same general design as EBR II which went into service in 1963 The reactor system is housed in a concrete rectilinear building and provided with filtration and gas containment features In the first 15 years of operation there have been 12 incidents involving sodium water interactions from tube breaks in the steam generators 2 a sodium air oxidation fire from a leak in an auxiliary system and a sodium fire from a leak in a secondary coolant loop while shut down All these incidents were classified at the lowest level on the International Nuclear Event Scale and none of the events prevented restarting operation of the facility after repairs As of 1997 there had been 27 sodium leaks 14 of which resulted in sodium air oxidations fires The steam generators are separated in modules so they can be repaired without shutting down the reactor 3 As of 2020 the cumulative energy Availability factor calculated up to year 2019 and recorded by the IAEA was 75 6 4 The reactor core is 1 03 meters tall with a diameter of 2 05 meters 5 It has 369 fuel assemblies mounted vertically each consisting of 127 fuel rods enriched to between 17 26 235U In comparison normal enrichment in other Russian reactors is between 3 4 235U The control and scram system comprises 27 reactivity control elements including 19 shimming rods two automatic control rods and six automatic emergency shut down rods On power refueling equipment allows for charging the core with fresh fuel assemblies repositioning and turning the fuel assemblies within the reactor and changing control and scram system elements remotely The unit employs a three circuit coolant arrangement sodium coolant circulates in both the primary and secondary circuits Water and steam flow in the third circuit The sodium is heated to a maximum of 550 C in the reactor during normal operations This heat is transferred from the reactor core via three independent circulation loops Each comprises a primary sodium pump two intermediate heat exchangers a secondary sodium pump with an expansion tank located upstream and an emergency pressure discharge tank These feed a steam generator which in turn supplies a condensing turbine that turns the generator There is much international interest in the fast breeder reactor at Beloyarsk Japan has its own prototype fast breeder reactors Japan paid 1 billion 6 clarification needed for the technical documentation of the BN 600 The operation of the reactor is an international study in progress Russia France Japan and the United Kingdom currently participate The reactor has been licensed to operate up to 2025 7 See also Edit Energy portal Nuclear technology portal Russia portalGeneration IV reactor BN Reactor BN 350 reactor Russian fast breeder reactor operated from 1973 to 1993 BN 800 reactor Russian fast breeder nuclear reactor operating since 2016 BN 1200 reactor Fast breeder nuclear reactor under development in Russia Prototype Fast Breeder Reactor Indian fast breeder nuclear reactor designReferences Edit Fast Neutron Reactors article from World Nuclear 12 water into sodium leaks occurred from google bn 600 tube leak result 5 PDF Frank von Hippel et al February 2010 Fast Breeder Reactor Programs History and Status PDF International Panel on Fissile Materials ISBN 978 0 9819275 6 5 Retrieved 28 April 2014 Beloyarsk 3 PRIS IAEA Retrieved 17 September 2020 Status of Fast Reactor Research and Technology Development PDF International Atomic Energy Agency 2012 p 130 ISBN 978 92 0 130610 4 Retrieved 11 November 2014 Bellona Foundation an international environmental NGO based in Norway Factsheet on the Beloyarsk Nuclear Power Plant Archived from the original on 2013 11 10 Russian Fast Reactor Connected to the Grid powermag com 1 February 2016 Retrieved 22 April 2018 External links EditRosenergoatom the Reactor BN 600 Overview of Fast Reactors in Russia and the Former Soviet Union BN 600 Hybrid Core Benchmark Analyses IAEA TECDOC 1623 BN 600 Fuel Russian firm that produces fuel for the BN 600 Liquid Metal Cooled Reactors Experience in Design and Operation IAEA TECDOC 1529 Operating experience from the BN600 sodium fast reactor IAEA Assessment of changes to the BN 600 to operate with a plutonium burner core Coordinates 56 50 30 N 61 19 21 E 56 8416 N 61 3224 E 56 8416 61 3224 Retrieved from https en wikipedia org w index php title BN 600 reactor amp oldid 1069916222, wikipedia, wiki, book, books, library,

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