Modeling of the SPERT transients using Serpent 2 with time-dependent capabilities

Alex Levinsky (Corresponding Author), Ville Valtavirta, Frederick P. Adams, Vinicius N.P. Anghel

    Research output: Contribution to journalArticleResearchpeer-review

    Abstract

    Monte Carlo multi-physics modeling of reactor transients is being made feasible by the advancement of computer capacities. Developments have recently been made in the area of dynamic Monte Carlo methods, and corresponding new algorithms have been implemented in a number of transport codes. In particular, a time-dependent simulation mode has been implemented in the Serpent 2 code. This paper is focused on time-dependent simulations of the SPERT experiments. The results of reactor-physics simulations are presented. The modeling has been performed using Serpent 2. The results of the reactor physics simulations without fuel temperature feedback are in very good agreement with the experimental data.

    LanguageEnglish
    Pages80-98
    Number of pages19
    JournalAnnals of Nuclear Energy
    Volume125
    DOIs
    Publication statusPublished - Mar 2019
    MoE publication typeNot Eligible

    Fingerprint

    Physics
    Monte Carlo methods
    Feedback
    Experiments
    Temperature

    Keywords

    • Pressurized water reactor
    • Reactor kinetics
    • Reactor period
    • Reactor transient
    • Serpent
    • Time-dependent Monte Carlo

    OKM Publication Types

    • A1 Refereed journal article

    OKM Open Access Status

    • 0 Not Open Access

    ASJC Scopus subject areas

    • Nuclear Energy and Engineering

    Cite this

    Levinsky, Alex ; Valtavirta, Ville ; Adams, Frederick P. ; Anghel, Vinicius N.P. / Modeling of the SPERT transients using Serpent 2 with time-dependent capabilities. In: Annals of Nuclear Energy. 2019 ; Vol. 125. pp. 80-98.
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    Modeling of the SPERT transients using Serpent 2 with time-dependent capabilities. / Levinsky, Alex (Corresponding Author); Valtavirta, Ville; Adams, Frederick P.; Anghel, Vinicius N.P.

    In: Annals of Nuclear Energy, Vol. 125, 03.2019, p. 80-98.

    Research output: Contribution to journalArticleResearchpeer-review

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