Development prospects of high-temperature gas-cooled reactors and their role in nuclear power

N.N. Ponomarev-Stepnoy, V.N. Grebennik, E.S. Glushkov, A.A. Khrulev, A.I. Kiryushin and V.V. Bulygin

Energy, 1991, vol. 16, issue 1, 119-127

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.

Date: 1991
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Persistent link: https://EconPapers.repec.org/RePEc:eee:energy:v:16:y:1991:i:1:p:119-127

DOI: 10.1016/0360-5442(91)90092-Z

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