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Burnup Credit in the Criticality Safety Analysis of Spent Fuel in Transportation and Storage Systems

[+] Author Affiliations
Vladyslav Soloviov

National Technical University of Ukraine “Kyiv Polytechnic Institute”, Kyiv, Ukraine

Paper No. ICONE21-15127, pp. V006T16A002; 8 pages
  • 2013 21st International Conference on Nuclear Engineering
  • Volume 6: Beyond Design Basis Events; Student Paper Competition
  • Chengdu, China, July 29–August 2, 2013
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5583-6
  • Copyright © 2013 by ASME


In this paper accounting of spent nuclear fuel (SNF) burnup of RBMK-1000 only with actinides has been performed.

The following characteristics were analyzed: initial fuel enrichment, burnup fraction, axial burnup profile in the fuel assembly (FA) and fuel weight.

As the results show, in the first 400 hours after stopping the reactor, there is an increase in the effective neutron multiplication factor (keff) due to beta decay of 239Np into 239Pu. Further, from 5 to 50 years, there is a decrease in keff due to beta decay of 241Pu into 241Am. Beyond 50 years there is a slight change in the criticality of the system.

Accounting for nuclear fuel burnup in the justification of nuclear safety of SNF systems will provide an opportunity to increase the volume of loaded fuel and thus significantly reduce technology costs of handling of SNF.

Copyright © 2013 by ASME



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