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Assesment of advanced step models for steady state Monte Carlo burnup calculations in application to prismatic HTGR

Grzegorz Kępisty
  • Corresponding author
  • Department of Nuclear Engineering, Faculty of Energy and Fuels, AGH University of Science and Technology, 30 Mickiewicza Ave., 30-059 Krakow, Poland, Tel.: +48 12 617 2954
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/ Jerzy Cetnar
  • Department of Nuclear Engineering, Faculty of Energy and Fuels, AGH University of Science and Technology, 30 Mickiewicza Ave., 30-059 Krakow, Poland, Tel.: +48 12 617 2954
  • Other articles by this author:
  • De Gruyter OnlineGoogle Scholar
Published Online: 2015-09-25 | DOI: https://doi.org/10.1515/nuka-2015-0095


In this paper, we compare the methodology of different time-step models in the context of Monte Carlo burnup calculations for nuclear reactors. We discuss the differences between staircase step model, slope model, bridge scheme and stochastic implicit Euler method proposed in literature. We focus on the spatial stability of depletion procedure and put additional emphasis on the problem of normalization of neutron source strength. Considered methodology has been implemented in our continuous energy Monte Carlo burnup code (MCB5). The burnup simulations have been performed using the simplified high temperature gas-cooled reactor (HTGR) system with and without modeling of control rod withdrawal. Useful conclusions have been formulated on the basis of results.

Keywords: burnup · high temperature gas-cooled reactor (HTGR) · Monte Carlo · stability · step model


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About the article

Published Online: 2015-09-25

Published in Print: 2015-09-01

Citation Information: Nukleonika, ISSN (Online) 0029-5922, DOI: https://doi.org/10.1515/nuka-2015-0095.

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© by Grzegorz Kępisty. This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 3.0 License. BY-NC-ND 3.0

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G. Kępisty, M. Oettingen, P. Stanisz, and J. Cetnar
Annals of Nuclear Energy, 2017, Volume 105, Page 355

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