Development of Monte Carlo neutron transport methods for reactor physics applications

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    Abstract

    PSG (Probabilistic Scattering Game) is a new Monte Carlo neutron transport code, developed at the VTT Technical Research Centre of Finland. The code is specifically designed for reactor physics applications, particularly at the fuel assembly level. Group constant generation for deterministic reactor simulator codes is considered as one of the main motivations for PSG development. This paper presents an overview of the main features of PSG, together with some typical results.
    Original languageEnglish
    Title of host publicationSAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006
    Subtitle of host publicationFinal Report
    Place of PublicationEspoo
    PublisherVTT Technical Research Centre of Finland
    Pages41-47
    ISBN (Electronic)951-38-6887-7
    ISBN (Print)951-38-6886-9
    Publication statusPublished - 2006
    MoE publication typeNot Eligible

    Publication series

    SeriesVTT Tiedotteita - Research Notes
    Number2363
    ISSN1235-0605

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    Cite this

    Leppänen, J. (2006). Development of Monte Carlo neutron transport methods for reactor physics applications. In SAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006: Final Report (pp. 41-47). VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2363 http://www.vtt.fi/inf/pdf/tiedotteet/2006/T2363.pdf