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- W2009244144 abstract "The advantages of a high-temperature inherently safe nuclear reactor are discussed. The characteristics of the two HTGRs being developed in the USSR, the 200 MW(t) VTR-M reactor and the 1060 MW(t) VG-400 reactor, are described. These prototype reactors will be built and utilized both for electrical power generation and for process heat application." @default.
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- W2009244144 date "1991-01-01" @default.
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- W2009244144 title "Development prospects of high-temperature gas-cooled reactors and their role in nuclear power" @default.
- W2009244144 doi "https://doi.org/10.1016/0360-5442(91)90092-z" @default.
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