Similarity of high-temperature gas-cooled reactor technologies and designs in Russia and USA |
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| Authors: | N N Ponomarev-Stepnoi N G Abrosimov A V Vasyaev M E Ganin V F Golovko D L Zverev N G Kodochigov V V Petrunin |
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| Affiliation: | 1.Russian Science Center Kurchatov Institute,Moscow,Russia;2.Afrikantov Experimental Design Bureau of Mechanical Engineering,Nizhnii Novgorod,Russia |
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| Abstract: | 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. |
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