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Conference Article: Main characteristics and design features of steam generators for VG-400 plant

Golovko, V.F.; Grebennik, V.N.; Gol'tsev, A.O.; Ivanov, S.M.; Sergeev, A.I.; Pospelov, V.N. (I.V. Kurchatov Institute of Atomic Energy, Moscow (Russian Federation))

Abstract

The description of a steam generator for the VG-400 plant performed in two variants depending on a heat-exchange surface arrangement (one-bundle coil and module-cassette construction) is given.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Specialists' meeting on technology of steam generators for gas-cooled reactors Winterthur (Switzerland) 9-12 Mar 1987
International Atomic Energy Agency, International Working Group on Gas-Cooled Reactors, Vienna (Austria)
IWGGCR--15, pp:175-181