Atomic Energy

, Volume 118, Issue 6, pp 436–441 | Cite as

Selecting Concrete for Radiation Protection for New-Generation NPP

  • B. K. Bylkin
  • A. N. Kozhevnikov
  • I. A. Engovatov
Article

Computational studies of the activation of a radiological protection structure made with widely used compositions of concrete are presented. The calculations were performed for a one-dimensional reactor–radiological-thermal and biological protection geometry typical for NPP with VVER. The investigations showed that the induced activity and therefore the volume of radioactive wastes can be reduced by picking a low-activation composition for the protective concrete used for the shaft of a VVER reactor.

Keywords

Radioactive Waste Boron Carbide Recycle Material Radiological Protection Protective Material 
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.
    Decommissioning of Nuclear Power Plants and Research Reactors, IAEA Safety Standards Ser. 0 WS-G-2.1, IAEA, Vienna (1999).Google Scholar
  2. 2.
    Decommissioning Strategies for Facilities Using Radioactive Material, Safety Rep. Ser. 0 50, IAEA, Vienna (2007).Google Scholar
  3. 3.
    NP 012–99, Safety Regulations for Decommissioning Nuclear Power Plant Units, GAN Rossii, Moscow (1999).Google Scholar
  4. 4.
    J. Evans, E. Lepel, R. Sundens, et al., “Long-lived activation products in light-water reactor construction materials: implication for decommissioning,” Radioactive Waste Management and the Nuclear Fuel Cycle (1988), Vol. 11(1), pp. 1–39.Google Scholar
  5. 5.
    I. A. Engovatov, V. P. Mashkovich, Y. V. Orlov, et al., Radiation Safety Assurance: Decommissioning Nuclear Reactors at Civil and Military Installations, Monographia, USA (2005).Google Scholar
  6. 6.
    I. A. Engovatov, “Radwaste volumes and activation of the radiological protection of reactor facilities,” Vest. MGSU, No. 8, 320–325 (2011).Google Scholar
  7. 7.
    B. K. Bylkin and I. A. Engovatov, Decommissioning of Reactor Facilities, MGSU, Moscow (2014).Google Scholar
  8. 8.
    Federal Law of the Russian Federation No. 190-FZ, On the Management of Radioactive Wastes and On Making Changes in Individual Legislative Acts of the Russian Federation, July 11, 2011.Google Scholar
  9. 9.
    DOORS 3.2: One- Two- and Three Dimensional Discrete Ordinates Neutron/Photon Transport Code System, ORNL-RSICC C-650 (1998).Google Scholar
  10. 10.
    BUGLE-96: Coupled 47 Neutron, 20 Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications, ORNL-RSICC DLC-185 (1999).Google Scholar
  11. 11.
    SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, NUREG/CR-200, Rev. 5 (1995).Google Scholar
  12. 12.
    G. A. Voitkevich, A. E. Miroshnikov, A. S. Povarennykh, and V. G. Prokhorov, Concise Handbook of Geochemistry, Nedra, Moscow (1977).Google Scholar
  13. 13.
    I. A. Ingovatov, B. K. Bylkin, and A. N. Kozhevnikov, “Composition optimization of concretes for radiological protection of NPP,” 9th Int. Sci.-Techn. Conf. Safety, Efficiency, and Economics of Nuclear Power MNTK-2014, Moscow (2014), pp. 305–309.Google Scholar

Copyright information

© Springer Science+Business Media New York 2015

Authors and Affiliations

  • B. K. Bylkin
    • 1
  • A. N. Kozhevnikov
    • 1
  • I. A. Engovatov
    • 2
  1. 1.National Research Center Kurchatov InstituteMoscowRussia
  2. 2.Moscow State University of Civil Engineering (MGSU)MoscowRussia

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