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

Author

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

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.

Suggested Citation

  • Ponomarev-Stepnoy, N.N. & Grebennik, V.N. & Glushkov, E.S. & Khrulev, A.A. & Kiryushin, A.I. & Bulygin, V.V., 1991. "Development prospects of high-temperature gas-cooled reactors and their role in nuclear power," Energy, Elsevier, vol. 16(1), pages 119-127.
    • Handle: RePEc:eee:energy:v:16:y:1991:i:1:p:119-127
    DOI: 10.1016/0360-5442(91)90092-Z
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    Cited by:

    1. Liu, Hongbing & Du, Dong & Han, Zandong & Zou, Yirong & Pan, Jiluan, 2015. "Dynamic analysis and application of fuel elements pneumatic transportation in a pebble bed reactor," Energy, Elsevier, vol. 79(C), pages 33-39.
    2. Yang, Min & Liu, Qi & Zhao, Hongsheng & Li, Ziqiang & Liu, Bing & Li, Xingdong & Meng, Fanyong, 2014. "Automatic X-ray inspection for escaped coated particles in spherical fuel elements of high temperature gas-cooled reactor," Energy, Elsevier, vol. 68(C), pages 385-398.

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