Calculation of effective point kinetics parameters in the Serpent 2 Monte Carlo code

Jaakko Leppänen (Corresponding Author), M. Aufiero, E. Fridman, R. Rachamin, S. Van Der Marck

    Research output: Contribution to journalArticleScientificpeer-review

    50 Citations (Scopus)

    Abstract

    This paper presents the methodology developed for the Serpent 2 Monte Carlo code for the calculation of adjoint-weighted reactor point kinetics parameters: effective generation time and delayed neutron fractions. The calculation routines were implemented at the Politecnico di Milano, and they are based on the iterated fission probability (IFP) method. The developed methodology is mainly intended for the modeling of small research reactor cores, and the results are validated by comparison to experimental data and MCNP5 calculations in 31 critical configurations.
    Original languageEnglish
    Pages (from-to)272-279
    JournalAnnals of Nuclear Energy
    Volume65
    DOIs
    Publication statusPublished - 2014
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Kinetic parameters
    Research reactors
    Reactor cores
    Neutrons

    Keywords

    • Adjoint-weighted time constants
    • Effective delayed neutron fraction
    • Effective generation time
    • Monte Carlo
    • Serpent

    Cite this

    Leppänen, Jaakko ; Aufiero, M. ; Fridman, E. ; Rachamin, R. ; Van Der Marck, S. / Calculation of effective point kinetics parameters in the Serpent 2 Monte Carlo code. In: Annals of Nuclear Energy. 2014 ; Vol. 65. pp. 272-279.
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    Calculation of effective point kinetics parameters in the Serpent 2 Monte Carlo code. / Leppänen, Jaakko (Corresponding Author); Aufiero, M.; Fridman, E.; Rachamin, R.; Van Der Marck, S.

    In: Annals of Nuclear Energy, Vol. 65, 2014, p. 272-279.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Calculation of effective point kinetics parameters in the Serpent 2 Monte Carlo code

    AU - Leppänen, Jaakko

    AU - Aufiero, M.

    AU - Fridman, E.

    AU - Rachamin, R.

    AU - Van Der Marck, S.

    PY - 2014

    Y1 - 2014

    N2 - This paper presents the methodology developed for the Serpent 2 Monte Carlo code for the calculation of adjoint-weighted reactor point kinetics parameters: effective generation time and delayed neutron fractions. The calculation routines were implemented at the Politecnico di Milano, and they are based on the iterated fission probability (IFP) method. The developed methodology is mainly intended for the modeling of small research reactor cores, and the results are validated by comparison to experimental data and MCNP5 calculations in 31 critical configurations.

    AB - This paper presents the methodology developed for the Serpent 2 Monte Carlo code for the calculation of adjoint-weighted reactor point kinetics parameters: effective generation time and delayed neutron fractions. The calculation routines were implemented at the Politecnico di Milano, and they are based on the iterated fission probability (IFP) method. The developed methodology is mainly intended for the modeling of small research reactor cores, and the results are validated by comparison to experimental data and MCNP5 calculations in 31 critical configurations.

    KW - Adjoint-weighted time constants

    KW - Effective delayed neutron fraction

    KW - Effective generation time

    KW - Monte Carlo

    KW - Serpent

    U2 - 10.1016/j.anucene.2013.10.032

    DO - 10.1016/j.anucene.2013.10.032

    M3 - Article

    VL - 65

    SP - 272

    EP - 279

    JO - Annals of Nuclear Energy

    JF - Annals of Nuclear Energy

    SN - 0306-4549

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