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Atomic Energy

, Volume 101, Issue 2, pp 606–610 | Cite as

Neutron-physical and heat-engineering aspects of uranium-graphite reactors loaded with enriched-uranium fuel elements

  • Yu. A. Artel’nyi
  • P. M. Gavrilov
  • A. A. Tsyganov
Scientific and Technical Communications
  • 30 Downloads

Keywords

Energy Release Flux Density Thermal Neutron Fuel Element Fast Neutron 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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References

  1. 1.
    A. S. Zaimovskii, V. V. Kalashnikov, and I. S. Golovnin, Fuel Elements of Nuclear Reactors, Atomizdat, Moscow (1966).Google Scholar
  2. 2.
    L. Petrie and N. Landers, KENO V.a: An Improved Monte Carlo Criticality Program with Supergrouping, US Department of Energy (2000).Google Scholar
  3. 3.
    N. N. Ponomarev-Stepnoi, G. L. Lunin, A. G. Morozov, et al., “VVÉR-T light-water thorium reactor,” At. Énerg., 85, No. 4, 263–271 (1998).Google Scholar

Copyright information

© Springer Science+Business Media, Inc. 2006

Authors and Affiliations

  • Yu. A. Artel’nyi
    • 1
  • P. M. Gavrilov
    • 1
  • A. A. Tsyganov
    • 1
  1. 1.Siberian Integrated Chemical PlantRussia

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