Similarity of high-temperature gas-cooled reactor technologies and designs in Russia and USA

Similarity of high-temperature gas-cooled reactor technologies and designs in Russia and USA

Historical information concerning the development of high-temperature gas-cooled reactors in the USA and Russia is presented. The reactor facilities MHTGR (USA), VG-400 (Russia), VGM (Russia), GT-MGR (Russia, USA), and at the Fort St. Vrain nuclear power plant (USA) are described. The US programs fo...

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Veröffentlicht in:Atomic energy (New York, N.Y.) N.Y.), 2010-06, Vol.108 (2), p.89-96
Hauptverfasser: Ponomarev-Stepnoi, N. N., Abrosimov, N. G., Vasyaev, A. V., Ganin, M. E., Golovko, V. F., Zverev, D. L., Kodochigov, N. G., Petrunin, V. V.
Format: Artikel
Sprache:eng
Schlagworte:
Alternative energy sources
Design
Design engineering
Efficiency
Electricity
Energy consumption
Energy conversion
Engineering
Forts
Generators
Graphite
Hadrons
Heat
Heavy Ions
Helium
High technology
High temperature
Nuclear Chemistry
Nuclear Energy
Nuclear engineering
Nuclear Physics
Nuclear power generation
Nuclear power plants
Nuclear reactor components
Nuclear reactors
Physics
Physics and Astronomy
Reactors
Reinforced concrete
Similarity
Studies
Turbines
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Beschreibung
Zusammenfassung:Historical information concerning the development of high-temperature gas-cooled reactors in the USA and Russia is presented. The reactor facilities MHTGR (USA), VG-400 (Russia), VGM (Russia), GT-MGR (Russia, USA), and at the Fort St. Vrain nuclear power plant (USA) are described. The US programs for developing innovative high-temperature nuclear reactor technologies are examined. It is shown that the Russian and US technological developments for the fuel, reactor system, energy conversion system, and fission-product transport are similar.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-010-9261-8