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Monte Carlo criticality calculations accelerated by a growing neutron population
KTH, School of Engineering Sciences (SCI). (Nuclear Reactor Technology)ORCID iD: 0000-0002-7943-7517
Tallinn University of Technology.
2016 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 94, 16-21 p.Article in journal (Refereed) Published
Abstract [en]

We propose a fission source convergence acceleration method for Monte Carlo criticality simulation. As the efficiency of Monte Carlo criticality simulations is sensitive to the selected neutron population size, the method attempts to achieve the acceleration via on-the-fly control of the neutron population size. The neutron population size is gradually increased over successive criticality cycles so that the fission source bias amounts to a specific fraction of the total error in the cumulative fission source. An optimal setting then gives a reasonably small neutron population size, allowing for an efficient source iteration; at the same time the neutron population size is chosen large enough to ensure a sufficiently small source bias, such that does not limit accuracy of the simulation.

Place, publisher, year, edition, pages
Elsevier, 2016. Vol. 94, 16-21 p.
Keyword [en]
Monte Carlo criticality, Fission source, Convergence, Bias, Convergence acceleration
National Category
Other Engineering and Technologies not elsewhere specified
Research subject
URN: urn:nbn:se:kth:diva-192580DOI: 10.1016/j.anucene.2016.02.015OAI: diva2:971102
Available from: 2016-09-15 Created: 2016-09-15 Last updated: 2016-09-19Bibliographically approved

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Dufek, Jan
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