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Optimal neutron population growth in accelerated Monte Carlo criticality calculations
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.ORCID iD: 0000-0003-4878-6711
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.ORCID iD: 0000-0002-7943-7517
2018 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 117, p. 297-304Article in journal (Refereed) Published
Abstract [en]

We present a source convergence acceleration method for Monte Carlo criticality calculations. The method gradually increases the neutron population size over the successive inactive as well as active criticality cycles. This helps to iterate the fission source faster at the beginning of the simulation where the source may contain large errors coming from the initial cycle; and, as the neutron population size grows over the cycles, the bias in the source gets reduced. Unlike previously suggested acceleration methods that aim at optimisation of the neutron population size, the new method does not have any significant computing overhead, and moreover it can be easily implemented into existing Monte Carlo criticality codes. The effectiveness of the method is demonstrated on a number of PWR full-core criticality calculations using a modified SERPENT 2 code.

Place, publisher, year, edition, pages
Elsevier, 2018. Vol. 117, p. 297-304
Keyword [en]
Monte Carlo criticality; Fission source; Convergence; Bias; Efficiency
National Category
Energy Engineering
Identifiers
URN: urn:nbn:se:kth:diva-225829DOI: 10.1016/j.anucene.2018.03.046ISI: 000431469900029Scopus ID: 2-s2.0-85044790843OAI: oai:DiVA.org:kth-225829DiVA, id: diva2:1196075
Note

QC 20180412

Available from: 2018-04-09 Created: 2018-04-09 Last updated: 2018-05-21Bibliographically approved

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Dufek, Jan

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