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Atomic Energy

, Volume 104, Issue 5, pp 349–354 | Cite as

Neutron-physical and thermohydraulic calculations of VVR-SM with high-and low-enrichment uranium fuel assemblies

  • S. A. Baitelesov
  • A. A. Dosimbaev
  • F. R. Kungurov
  • U. S. Salikhbaev
Article

Abstract

The VVR-SM reactor at the Institute of Nuclear Physics of the Academy of Sciences of Uzbekistan is being converted from fuel assemblies with high-enrichment uranium (36% 235U) to fuel assemblies with low-enrichment uranium (19.7% 235U). During the conversion process consisting of nine cycles, the IRT-3M fuel assemblies with high-enrichment uranium, which are removed at the end of each cycle, will be replaced with IRT-4M fuel assemblies with low-enrichment uranium. This will require increasing the core size up to 20 fuel assemblies and increasing the power of the reactor to 11 MW. The methods used for and the results of neutron-physical calculations (burnup, power distribution, subcriticality), thermohydraulic analysis, and calculations of the kinetic parameters of a stable state are described for a core with high-enrichment uranium, a mixed core, and the first full core with low-enrichment uranium.

Keywords

Uranium Fuel Element Fuel Assembly Uranium Dioxide Fuel Layer 
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.
    B. Yuldashev, U. Salikhbaev, A. Dosimbaev, et al., “VVER-SM operation with 36% enrichment uranium dioxide fuel,” At. Énerg., 99, No. 2, 147–152 (2005).Google Scholar
  2. 2.
    IRT-3M Fuel Assemblies, Catalog Description 0019.08.00.000 DKO, NZKhK, Novosibirsk (2003).Google Scholar
  3. 3.
    IRT-4M Fuel Assemblies, Catalog Description 0019.20.00.000 DKO, NZKhK, Novosibirsk (2004).Google Scholar
  4. 4.
    WIMS, Rev. 6, ANL/TD/TM99-07 (2004).Google Scholar
  5. 5.
    IRT-2D Program for Performing Two-Dimensional Neutron Calculations for Reactors with IRT-M Fuel Assemblies in a Two-Group Diffusion Approximation, Preprint IAÉ-15/695 (1986).Google Scholar
  6. 6.
    MCNP — A General Monte Carlo N Particle Transport Code, Version 4C, LA-13709-M (2000).Google Scholar
  7. 7.
    A. Olson and A. Kalimullah, Users Guide to PLTEMP ANL V3.1 Code (2006).Google Scholar

Copyright information

© Springer Science+Business Media, Inc. 2008

Authors and Affiliations

  • S. A. Baitelesov
    • 1
  • A. A. Dosimbaev
    • 1
  • F. R. Kungurov
    • 1
  • U. S. Salikhbaev
    • 1
  1. 1.Institute of Nuclear PhysicsAcademy of Sciences of the Republic of UzbekistanTashkentUzbekistan

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