Revised methods for few-group cross sections generation in the Serpent Monte Carlo code

E. Fridman, Jaakko Leppänen

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

    13 Citations (Scopus)


    This paper presents new calculation methods, recently implemented in the Serpent Monte Carlo code, and related to the production of homogenized few-group constants for deterministic 3D core analysis. The new methods fall under three topics: 1) Improved treatment of neutron-multiplying scattering reactions, 2) Group constant generation in reflectors and other non-fissile regions and 3) Homogenization in leakage-corrected criticality spectrum. The methodology is demonstrated by a numerical example, comparing a deterministic nodal diffusion calculation using Serpent-generated cross sections to a reference full-core Monte Carlo simulation. It is concluded that the new methodology improves the results of the deterministic calculation, and paves the way for Monte Carlo based group constant generation
    Original languageEnglish
    Title of host publicationProceedings
    Subtitle of host publicationInternational Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012
    PublisherAmerican Nuclear Society (ANS)
    ISBN (Print)978-1-6227-6389-4
    Publication statusPublished - 2012
    MoE publication typeA4 Article in a conference publication
    EventInternational Conference on the Physics of Reactors, PHYSOR 2012: Advances in Reactor Physics - Knoxville, United States
    Duration: 15 Apr 201220 Apr 2012


    ConferenceInternational Conference on the Physics of Reactors, PHYSOR 2012
    Country/TerritoryUnited States


    • 3D core analysis
    • criticality spectrum
    • few-group cross-section generation
    • lattice physics
    • Monte Carlo
    • reflector cross sections
    • serpent


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