The Serpent Monte Carlo code: Status, development and applications in 2013

Jaakko Leppänen (Corresponding Author), Maria Pusa, Tuomas Viitanen, Ville Valtavirta, Toni Kaltiaisenaho

    Research output: Contribution to journalReview Articlepeer-review

    1281 Citations (Scopus)


    The Serpent Monte Carlo reactor physics burnup calculation code has been developed at VTT Technical Research Centre of Finland since 2004, and is currently used in over 100 universities and research organizations around the world. This paper presents the brief history of the project, together with the currently available methods and capabilities and plans for future work. Typical user applications are introduced in the form of a summary review on Serpent-related publications over the past few years.
    Original languageEnglish
    Pages (from-to)142-150
    JournalAnnals of Nuclear Energy
    Publication statusPublished - 2014
    MoE publication typeA2 Review article in a scientific journal
    EventJoint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013, SNA + MC 2013. Pluri- and Trans-disciplinarity, Towards New Modeling and Numerical Simulation Paradigms - Paris, France
    Duration: 27 Oct 201331 Oct 2013


    • Serpent
    • Monte Carlo
    • reactor physics
    • homogenization
    • burnup calculation


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