On the use of the Serpent Monte Carlo code for few-group cross section generation

E. Fridman (Corresponding Author), Jaakko Leppänen

    Research output: Contribution to journalArticleScientificpeer-review

    59 Citations (Scopus)

    Abstract

    Serpent is a recently developed 3D continuous-energy Monte Carlo (MC) reactor physics burnup calculation code. Serpent is specifically designed for lattice physics applications including generation of homogenized few-group constants for full-core core simulators.

    Currently in Serpent, the few-group constants are obtained from the infinite-lattice calculations with zero neutron current at the outer boundary. In this study, in order to account for the non-physical infinite-lattice approximation, B1 methodology, routinely used by deterministic lattice transport codes, was considered for generation of leakage-corrected few-group cross sections in the Serpent code. A preliminary assessment of the applicability of the B1 methodology for generation of few-group constants in the Serpent code was carried out according to the following steps. Initially, the two-group constants generated by Serpent were compared with those calculated by Helios deterministic lattice transport code. Then, a 3D analysis of a Pressurized Water Reactor (PWR) core was performed by the nodal diffusion code DYN3D employing two-group cross section sets generated by Serpent and Helios. At this stage thermal–hydraulic (T-H) feedback was neglected. The DYN3D results were compared with those obtained from the 3D full core Serpent MC calculations. Finally, the full core DYN3D calculations were repeated taking into account T-H feedback and assuming Hot Full Power (HFP) conditions.

    The B1 two-group cross sections and diffusion coefficients generated by the Serpent and Helios codes agree within less than 2.5%. The results of the DYN3D calculations with the Serpent B1 cross section sets agree very well with those of the Serpent full core MC calculations. The relative difference in keff is below 300 pcm. The maximum and root mean square (RMS) difference in the radial power distribution is 2.7% and 1.1% respectively. The results of the DYN3D full core calculations with T-H feedback obtained with Helios and Serpent generated cross section libraries show an excellent agreement as well. The estimated critical boron concentration agrees within 5 ppm. The maximum and RMS difference in the core radial power peaking factors is 0.8% and 0.4% respectively.

    In this study, a Matlab script was used for calculation of the leakage-corrected few-group cross sections, however, the B1 methodology has recently been implemented directly in the Serpent code.
    Original languageEnglish
    Pages (from-to)1399-1405
    Number of pages7
    JournalAnnals of Nuclear Energy
    Volume38
    Issue number6
    DOIs
    Publication statusPublished - 2011
    MoE publication typeA1 Journal article-refereed

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    Physics
    Reactor cores
    Pressurized water reactors
    Boron
    Neutrons
    Simulators

    Keywords

    • Monte Carlo
    • Lattice physics
    • Few-group cross section generation
    • Critical spectrum
    • 3D core analysis

    Cite this

    @article{1377e7ff9db74e5eb5941d63fb3f09d8,
    title = "On the use of the Serpent Monte Carlo code for few-group cross section generation",
    abstract = "Serpent is a recently developed 3D continuous-energy Monte Carlo (MC) reactor physics burnup calculation code. Serpent is specifically designed for lattice physics applications including generation of homogenized few-group constants for full-core core simulators.Currently in Serpent, the few-group constants are obtained from the infinite-lattice calculations with zero neutron current at the outer boundary. In this study, in order to account for the non-physical infinite-lattice approximation, B1 methodology, routinely used by deterministic lattice transport codes, was considered for generation of leakage-corrected few-group cross sections in the Serpent code. A preliminary assessment of the applicability of the B1 methodology for generation of few-group constants in the Serpent code was carried out according to the following steps. Initially, the two-group constants generated by Serpent were compared with those calculated by Helios deterministic lattice transport code. Then, a 3D analysis of a Pressurized Water Reactor (PWR) core was performed by the nodal diffusion code DYN3D employing two-group cross section sets generated by Serpent and Helios. At this stage thermal–hydraulic (T-H) feedback was neglected. The DYN3D results were compared with those obtained from the 3D full core Serpent MC calculations. Finally, the full core DYN3D calculations were repeated taking into account T-H feedback and assuming Hot Full Power (HFP) conditions.The B1 two-group cross sections and diffusion coefficients generated by the Serpent and Helios codes agree within less than 2.5{\%}. The results of the DYN3D calculations with the Serpent B1 cross section sets agree very well with those of the Serpent full core MC calculations. The relative difference in keff is below 300 pcm. The maximum and root mean square (RMS) difference in the radial power distribution is 2.7{\%} and 1.1{\%} respectively. The results of the DYN3D full core calculations with T-H feedback obtained with Helios and Serpent generated cross section libraries show an excellent agreement as well. The estimated critical boron concentration agrees within 5 ppm. The maximum and RMS difference in the core radial power peaking factors is 0.8{\%} and 0.4{\%} respectively.In this study, a Matlab script was used for calculation of the leakage-corrected few-group cross sections, however, the B1 methodology has recently been implemented directly in the Serpent code.",
    keywords = "Monte Carlo, Lattice physics, Few-group cross section generation, Critical spectrum, 3D core analysis",
    author = "E. Fridman and Jaakko Lepp{\"a}nen",
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    language = "English",
    volume = "38",
    pages = "1399--1405",
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    On the use of the Serpent Monte Carlo code for few-group cross section generation. / Fridman, E. (Corresponding Author); Leppänen, Jaakko.

    In: Annals of Nuclear Energy, Vol. 38, No. 6, 2011, p. 1399-1405.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - On the use of the Serpent Monte Carlo code for few-group cross section generation

    AU - Fridman, E.

    AU - Leppänen, Jaakko

    PY - 2011

    Y1 - 2011

    N2 - Serpent is a recently developed 3D continuous-energy Monte Carlo (MC) reactor physics burnup calculation code. Serpent is specifically designed for lattice physics applications including generation of homogenized few-group constants for full-core core simulators.Currently in Serpent, the few-group constants are obtained from the infinite-lattice calculations with zero neutron current at the outer boundary. In this study, in order to account for the non-physical infinite-lattice approximation, B1 methodology, routinely used by deterministic lattice transport codes, was considered for generation of leakage-corrected few-group cross sections in the Serpent code. A preliminary assessment of the applicability of the B1 methodology for generation of few-group constants in the Serpent code was carried out according to the following steps. Initially, the two-group constants generated by Serpent were compared with those calculated by Helios deterministic lattice transport code. Then, a 3D analysis of a Pressurized Water Reactor (PWR) core was performed by the nodal diffusion code DYN3D employing two-group cross section sets generated by Serpent and Helios. At this stage thermal–hydraulic (T-H) feedback was neglected. The DYN3D results were compared with those obtained from the 3D full core Serpent MC calculations. Finally, the full core DYN3D calculations were repeated taking into account T-H feedback and assuming Hot Full Power (HFP) conditions.The B1 two-group cross sections and diffusion coefficients generated by the Serpent and Helios codes agree within less than 2.5%. The results of the DYN3D calculations with the Serpent B1 cross section sets agree very well with those of the Serpent full core MC calculations. The relative difference in keff is below 300 pcm. The maximum and root mean square (RMS) difference in the radial power distribution is 2.7% and 1.1% respectively. The results of the DYN3D full core calculations with T-H feedback obtained with Helios and Serpent generated cross section libraries show an excellent agreement as well. The estimated critical boron concentration agrees within 5 ppm. The maximum and RMS difference in the core radial power peaking factors is 0.8% and 0.4% respectively.In this study, a Matlab script was used for calculation of the leakage-corrected few-group cross sections, however, the B1 methodology has recently been implemented directly in the Serpent code.

    AB - Serpent is a recently developed 3D continuous-energy Monte Carlo (MC) reactor physics burnup calculation code. Serpent is specifically designed for lattice physics applications including generation of homogenized few-group constants for full-core core simulators.Currently in Serpent, the few-group constants are obtained from the infinite-lattice calculations with zero neutron current at the outer boundary. In this study, in order to account for the non-physical infinite-lattice approximation, B1 methodology, routinely used by deterministic lattice transport codes, was considered for generation of leakage-corrected few-group cross sections in the Serpent code. A preliminary assessment of the applicability of the B1 methodology for generation of few-group constants in the Serpent code was carried out according to the following steps. Initially, the two-group constants generated by Serpent were compared with those calculated by Helios deterministic lattice transport code. Then, a 3D analysis of a Pressurized Water Reactor (PWR) core was performed by the nodal diffusion code DYN3D employing two-group cross section sets generated by Serpent and Helios. At this stage thermal–hydraulic (T-H) feedback was neglected. The DYN3D results were compared with those obtained from the 3D full core Serpent MC calculations. Finally, the full core DYN3D calculations were repeated taking into account T-H feedback and assuming Hot Full Power (HFP) conditions.The B1 two-group cross sections and diffusion coefficients generated by the Serpent and Helios codes agree within less than 2.5%. The results of the DYN3D calculations with the Serpent B1 cross section sets agree very well with those of the Serpent full core MC calculations. The relative difference in keff is below 300 pcm. The maximum and root mean square (RMS) difference in the radial power distribution is 2.7% and 1.1% respectively. The results of the DYN3D full core calculations with T-H feedback obtained with Helios and Serpent generated cross section libraries show an excellent agreement as well. The estimated critical boron concentration agrees within 5 ppm. The maximum and RMS difference in the core radial power peaking factors is 0.8% and 0.4% respectively.In this study, a Matlab script was used for calculation of the leakage-corrected few-group cross sections, however, the B1 methodology has recently been implemented directly in the Serpent code.

    KW - Monte Carlo

    KW - Lattice physics

    KW - Few-group cross section generation

    KW - Critical spectrum

    KW - 3D core analysis

    U2 - 10.1016/j.anucene.2011.01.032

    DO - 10.1016/j.anucene.2011.01.032

    M3 - Article

    VL - 38

    SP - 1399

    EP - 1405

    JO - Annals of Nuclear Energy

    JF - Annals of Nuclear Energy

    SN - 0306-4549

    IS - 6

    ER -