Module for thermomechanical modeling of LWR fuel in multiphysics simulations

Timo Ikonen (Corresponding Author), Henri Loukusa, Elina Syrjälahti, Ville Valtavirta, Jaakko Leppänen, Ville Tulkki

    Research output: Contribution to journalArticleScientificpeer-review

    8 Citations (Scopus)

    Abstract

    We have developed a new light-weight fuel behavior code FINIX, specifically designed for modeling of LWR fuel rods in multiphysics simulations. A thermomechanical description of the rod is required especially in transient conditions, where the heat transfer and changes in the rod's physical dimensions are strongly coupled. In addition to the mechanical deformations, FINIX solves the temperature distribution in the rod and the heat flux from the cladding to the coolant, allowing two-way coupling of the fuel behavior simulation with both neutronics and thermal hydraulics simulations. In this paper, we describe the FINIX module and compare its performance with experimental data and FRAPTRAN-1.4, a widely used fuel behavior code. The comparison reveals good agreement in both cases. We also demonstrate how FINIX can be integrated into multiphysics simulations. Coupled with the Monte Carlo reactor physics code Serpent, we simulate a fast reactivity transient with the fuel temperature and fission power solved self-consistently. With the reactor dynamics codes TRAB-1D and TRAB3D/SMABRE, we simulate a fast power transient and a PWR main steam line break. The latter serves as an example of coupled fuel behavior, neutronics and system-level thermal hydraulics simulation.
    Original languageEnglish
    Pages (from-to)111-121
    JournalAnnals of Nuclear Energy
    Volume84
    DOIs
    Publication statusPublished - 2015
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Hydraulics
    Steam piping systems
    Coolants
    Heat flux
    Temperature distribution
    Physics
    Heat transfer
    Temperature
    Hot Temperature

    Keywords

    • fuel rod behavior
    • nuclear fuel modeling
    • multiphysics
    • FINIX

    Cite this

    @article{254bd4c37695490c837fd25ff7024a96,
    title = "Module for thermomechanical modeling of LWR fuel in multiphysics simulations",
    abstract = "We have developed a new light-weight fuel behavior code FINIX, specifically designed for modeling of LWR fuel rods in multiphysics simulations. A thermomechanical description of the rod is required especially in transient conditions, where the heat transfer and changes in the rod's physical dimensions are strongly coupled. In addition to the mechanical deformations, FINIX solves the temperature distribution in the rod and the heat flux from the cladding to the coolant, allowing two-way coupling of the fuel behavior simulation with both neutronics and thermal hydraulics simulations. In this paper, we describe the FINIX module and compare its performance with experimental data and FRAPTRAN-1.4, a widely used fuel behavior code. The comparison reveals good agreement in both cases. We also demonstrate how FINIX can be integrated into multiphysics simulations. Coupled with the Monte Carlo reactor physics code Serpent, we simulate a fast reactivity transient with the fuel temperature and fission power solved self-consistently. With the reactor dynamics codes TRAB-1D and TRAB3D/SMABRE, we simulate a fast power transient and a PWR main steam line break. The latter serves as an example of coupled fuel behavior, neutronics and system-level thermal hydraulics simulation.",
    keywords = "fuel rod behavior, nuclear fuel modeling, multiphysics, FINIX",
    author = "Timo Ikonen and Henri Loukusa and Elina Syrj{\"a}lahti and Ville Valtavirta and Jaakko Lepp{\"a}nen and Ville Tulkki",
    year = "2015",
    doi = "10.1016/j.anucene.2014.11.004",
    language = "English",
    volume = "84",
    pages = "111--121",
    journal = "Annals of Nuclear Energy",
    issn = "0306-4549",
    publisher = "Elsevier",

    }

    Module for thermomechanical modeling of LWR fuel in multiphysics simulations. / Ikonen, Timo (Corresponding Author); Loukusa, Henri; Syrjälahti, Elina; Valtavirta, Ville; Leppänen, Jaakko; Tulkki, Ville.

    In: Annals of Nuclear Energy, Vol. 84, 2015, p. 111-121.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Module for thermomechanical modeling of LWR fuel in multiphysics simulations

    AU - Ikonen, Timo

    AU - Loukusa, Henri

    AU - Syrjälahti, Elina

    AU - Valtavirta, Ville

    AU - Leppänen, Jaakko

    AU - Tulkki, Ville

    PY - 2015

    Y1 - 2015

    N2 - We have developed a new light-weight fuel behavior code FINIX, specifically designed for modeling of LWR fuel rods in multiphysics simulations. A thermomechanical description of the rod is required especially in transient conditions, where the heat transfer and changes in the rod's physical dimensions are strongly coupled. In addition to the mechanical deformations, FINIX solves the temperature distribution in the rod and the heat flux from the cladding to the coolant, allowing two-way coupling of the fuel behavior simulation with both neutronics and thermal hydraulics simulations. In this paper, we describe the FINIX module and compare its performance with experimental data and FRAPTRAN-1.4, a widely used fuel behavior code. The comparison reveals good agreement in both cases. We also demonstrate how FINIX can be integrated into multiphysics simulations. Coupled with the Monte Carlo reactor physics code Serpent, we simulate a fast reactivity transient with the fuel temperature and fission power solved self-consistently. With the reactor dynamics codes TRAB-1D and TRAB3D/SMABRE, we simulate a fast power transient and a PWR main steam line break. The latter serves as an example of coupled fuel behavior, neutronics and system-level thermal hydraulics simulation.

    AB - We have developed a new light-weight fuel behavior code FINIX, specifically designed for modeling of LWR fuel rods in multiphysics simulations. A thermomechanical description of the rod is required especially in transient conditions, where the heat transfer and changes in the rod's physical dimensions are strongly coupled. In addition to the mechanical deformations, FINIX solves the temperature distribution in the rod and the heat flux from the cladding to the coolant, allowing two-way coupling of the fuel behavior simulation with both neutronics and thermal hydraulics simulations. In this paper, we describe the FINIX module and compare its performance with experimental data and FRAPTRAN-1.4, a widely used fuel behavior code. The comparison reveals good agreement in both cases. We also demonstrate how FINIX can be integrated into multiphysics simulations. Coupled with the Monte Carlo reactor physics code Serpent, we simulate a fast reactivity transient with the fuel temperature and fission power solved self-consistently. With the reactor dynamics codes TRAB-1D and TRAB3D/SMABRE, we simulate a fast power transient and a PWR main steam line break. The latter serves as an example of coupled fuel behavior, neutronics and system-level thermal hydraulics simulation.

    KW - fuel rod behavior

    KW - nuclear fuel modeling

    KW - multiphysics

    KW - FINIX

    U2 - 10.1016/j.anucene.2014.11.004

    DO - 10.1016/j.anucene.2014.11.004

    M3 - Article

    VL - 84

    SP - 111

    EP - 121

    JO - Annals of Nuclear Energy

    JF - Annals of Nuclear Energy

    SN - 0306-4549

    ER -