Table of Contents Author Guidelines Submit a Manuscript
Science and Technology of Nuclear Installations
Volume 2009 (2009), Article ID 459139, 5 pages
Research Article

New Methods for Evaluation of Spent Fuel Condition during Long-Term Storage in Slovakia

1Reactor services division, Nuclear Research Institute Řež plc, Husinec-Řež 130, 250 68 Řež, Czech Republic
2Division of Safety of Future Nuclear Reactors, Institute for Energy, Joint Research Centre of the European Commission, P.O. Box 2, 1755ZG Petten, The Netherlands

Received 13 March 2008; Accepted 11 June 2009

Academic Editor: Kannan Iyer

Copyright © 2009 M. Mikloš and V. Kršjak. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Linked References

  1. Regulations for the Safe Transport of Radioactive Material, IAEA Safety Standards Series, International Atomic Energy Agency, Vienna, Austria, 1996.
  2. M. Šeliga and V. Slugeň, “Radioactive waste and spent fuel,” EE—Odborný Časopis pre Elektrotechniku a Energetiku, vol. 4, pp. 50–51, 1998 (Slovak). View at Google Scholar
  3. V. Slugeň et al., “Long-term storage of the spent nuclear fuel in Slovakia,” Research Report, FEI STU Bratislava, Bratislava, Slovakia, November 1998. View at Google Scholar
  4. V. Slugeň, M. Mikloň, B. Božik, and D. Važina, “Monitoring and leak testing of WWER-440 fuel assemblies in Slovak wet interim spent fuel storage facility,” Acta Montanistica Slovaka, vol. 12, pp. 187–191, 2007. View at Google Scholar
  5. V. Slugeň, I. Smieško, and D. Belko, “VVER-440 fuel leak testing experience at NPP Jaslovské Bohunice,” Journal of Electrical Engineering, vol. 46, pp. 29–31, 1995. View at Google Scholar
  6. V. Slugeň, M. Kalousek, and M. Rajčok, “Thermophysical verification of continuous hermetic sealling of fuel elements by coating control in the VVER-440 nuclear reactor,” Journal of Radioanalytical and Nuclear Chemistry, vol. 164, no. 2, pp. 71–80, 1992. View at Publisher · View at Google Scholar
  7. V. Slugeň, “Mast-sipping for VVER-440 fuel assemblies,” Nuclear Engineering International, vol. 39, pp. 29–31, 1994. View at Google Scholar
  8. “SCALE: a modular code system for performing standardized computer analyses for licensing evaluation,” Tech. Rep. NUREG/CR-0200, Rev. 6, ORNL/NUREG/CSD-2/R6, 1998.
  9. S. M. Bowman and L. C. Leal, “ORIGEN-ARP—automatic rapid process for spent fuel depletion, decay, and source term analysis,” NUREG/CR-0200, Revision 6, vol. 3, S.D1, ORNL/NUREG/CSD-2/V3/R6, 1998.