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Atomic Energy

, Volume 73, Issue 1, pp 552–557 | Cite as

VPBÉR-600 new-generation enhanced-safety power reactor

  • F. M. Mitenkov
  • G. M. Antonovskii
  • V. S. Kuul'
  • Yu. K. Panov
  • O. B. Samoilov
  • L. N. Frelov
  • N. N. Ponomarev-Stepnoi
  • N. E. Kukharkin
  • Yu. G. Nikoporets
Third Annual Conference of the Nuclear Society “Nuclear Technology in the World of Tomorrow”

Keywords

Power Reactor 
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Literature Cited

  1. 1.
    F. M. Mitenkov, E. V. Kulikov, V. A. Sidorenko, et al., “Reactor apparatus of AST-500 nuclear-powered heating station,” At. Énerg.,58, No. 5, 308–313 (1985).Google Scholar
  2. 2.
    F. M. Mitenkov and O. B. Samoilov, “Improved new-generation enhanced-safety water-moderated-water-cooled reactors,” Paper at IAEA Conference, Vienna, November 18–21 (1991).Google Scholar

Copyright information

© Plenum Publishing Corporation 1993

Authors and Affiliations

  • F. M. Mitenkov
  • G. M. Antonovskii
  • V. S. Kuul'
  • Yu. K. Panov
  • O. B. Samoilov
  • L. N. Frelov
  • N. N. Ponomarev-Stepnoi
  • N. E. Kukharkin
  • Yu. G. Nikoporets

There are no affiliations available

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