54 The atomic power plant VG-400: scheme and construction features
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Published:1983
J. N. Koshkin, J. V. Komarov, A. I. Kirjushin, N. N. Ponomarjev-Stepnoj, A. N. Prozenko, 1983. "54 The atomic power plant VG-400: scheme and construction features", Gas-cooled reactors today
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There are given the basic characteristics of the Nuclear Process Heat and Electricity Generating Plant VG-400 designed for electricity and high potential heat production. There are presented the thermal scheme and the layout of equipment in a multicavity prestressed concrete pressure vessel. There is shown the necessity of fuel element unloading through three tubes in order to ensure their uniform movement along the core cross section. The desired helium temperature at core outlet is assured without exceeding the permissible fuel temperature and with the use of one fuel element type.
The main purpose of high temperature gas cooled reactors (HTGRs) is to generate high temperature heat for process heat applications to conserve scarce organic fuels. The most profitable is the co-generation of high potential heat and electricity that allows to use the generated heat with high efficiency. The co-generation nuclear plant VG-400 is designed to generate high temperature heat for industry and electricity production. Its operation experience must verify the main design solutions and become the basis for more powerful plants in the future.
