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

• Published in: Atomic energy (New York, N.Y.) Vol. 108; no. 2; pp. 89 - 96
• Main Authors: 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: Journal Article
• Language: English
• Published: Boston Springer US 01.06.2010; Springer; Springer Nature B.V
• Subjects: 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; United States > US; Russia; Fuel Assembly; Energy Conversion System; Reactor Facility; Steam Generator; Pyrolytic Carbon
• ISSN: 1063-4258; 1573-8205
• DOI: 10.1007/s10512-010-9261-8

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.