Statistical analysis of fuel failures in large break loss-of-coolant accident (LBLOCA) in EPR type nuclear power plant

Asko Arkoma (Corresponding Author), Markku Hänninen, Karin Rantamäki, Joona Kurki, Anitta Hämäläinen

    Research output: Contribution to journalArticleScientificpeer-review

    12 Citations (Scopus)

    Abstract

    In this paper, the number of failing fuel rods in a large break loss-of-coolant accident (LB-LOCA) in EPR-type nuclear power plant is evaluated using statistical methods. For this purpose, a statistical fuel failure analysis procedure has been developed. The developed method utilizes the results of nonparametric statistics, the Wilks' formula in particular, and is based on the selection and variation of parameters that are important in accident conditions. The accident scenario is simulated with the coupled fuel performance - thermal hydraulics code FRAPTRAN-GENFLO using various parameter values and thermal hydraulic and power history boundary conditions between the simulations. The number of global scenarios is 59 (given by the Wilks' formula), and 1000 rods are simulated in each scenario. The boundary conditions are obtained from a new statistical version of the system code APROS. As a result, in the worst global scenario, 1.2% of the simulated rods failed, and it can be concluded that the Finnish safety regulations are hereby met (max. 10% of the rods allowed to fail).
    Original languageEnglish
    Pages (from-to)1-14
    JournalNuclear Engineering and Design
    Volume285
    DOIs
    Publication statusPublished - 2015
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    loss of coolant
    Loss of coolant accidents
    nuclear power plants
    electron spin resonance
    accidents
    nuclear power plant
    statistical analysis
    Nuclear power plants
    accident
    Paramagnetic resonance
    Statistical methods
    rods
    Accidents
    boundary condition
    Hydraulics
    Boundary conditions
    hydraulics
    nonparametric statistics
    failure analysis
    boundary conditions

    Keywords

    • loss-of-coolant accident
    • EPR
    • Wilks' formula
    • FRAPTRAN-GENFLO
    • APROS
    • statistical fuel failure analysis

    Cite this

    @article{7970032b9284495586b5b3dc2c07590b,
    title = "Statistical analysis of fuel failures in large break loss-of-coolant accident (LBLOCA) in EPR type nuclear power plant",
    abstract = "In this paper, the number of failing fuel rods in a large break loss-of-coolant accident (LB-LOCA) in EPR-type nuclear power plant is evaluated using statistical methods. For this purpose, a statistical fuel failure analysis procedure has been developed. The developed method utilizes the results of nonparametric statistics, the Wilks' formula in particular, and is based on the selection and variation of parameters that are important in accident conditions. The accident scenario is simulated with the coupled fuel performance - thermal hydraulics code FRAPTRAN-GENFLO using various parameter values and thermal hydraulic and power history boundary conditions between the simulations. The number of global scenarios is 59 (given by the Wilks' formula), and 1000 rods are simulated in each scenario. The boundary conditions are obtained from a new statistical version of the system code APROS. As a result, in the worst global scenario, 1.2{\%} of the simulated rods failed, and it can be concluded that the Finnish safety regulations are hereby met (max. 10{\%} of the rods allowed to fail).",
    keywords = "loss-of-coolant accident, EPR, Wilks' formula, FRAPTRAN-GENFLO, APROS, statistical fuel failure analysis",
    author = "Asko Arkoma and Markku H{\"a}nninen and Karin Rantam{\"a}ki and Joona Kurki and Anitta H{\"a}m{\"a}l{\"a}inen",
    note = "Project code: 83897",
    year = "2015",
    doi = "10.1016/j.nucengdes.2014.12.023",
    language = "English",
    volume = "285",
    pages = "1--14",
    journal = "Nuclear Engineering and Design",
    issn = "0029-5493",
    publisher = "Elsevier",

    }

    Statistical analysis of fuel failures in large break loss-of-coolant accident (LBLOCA) in EPR type nuclear power plant. / Arkoma, Asko (Corresponding Author); Hänninen, Markku; Rantamäki, Karin; Kurki, Joona; Hämäläinen, Anitta.

    In: Nuclear Engineering and Design, Vol. 285, 2015, p. 1-14.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Statistical analysis of fuel failures in large break loss-of-coolant accident (LBLOCA) in EPR type nuclear power plant

    AU - Arkoma, Asko

    AU - Hänninen, Markku

    AU - Rantamäki, Karin

    AU - Kurki, Joona

    AU - Hämäläinen, Anitta

    N1 - Project code: 83897

    PY - 2015

    Y1 - 2015

    N2 - In this paper, the number of failing fuel rods in a large break loss-of-coolant accident (LB-LOCA) in EPR-type nuclear power plant is evaluated using statistical methods. For this purpose, a statistical fuel failure analysis procedure has been developed. The developed method utilizes the results of nonparametric statistics, the Wilks' formula in particular, and is based on the selection and variation of parameters that are important in accident conditions. The accident scenario is simulated with the coupled fuel performance - thermal hydraulics code FRAPTRAN-GENFLO using various parameter values and thermal hydraulic and power history boundary conditions between the simulations. The number of global scenarios is 59 (given by the Wilks' formula), and 1000 rods are simulated in each scenario. The boundary conditions are obtained from a new statistical version of the system code APROS. As a result, in the worst global scenario, 1.2% of the simulated rods failed, and it can be concluded that the Finnish safety regulations are hereby met (max. 10% of the rods allowed to fail).

    AB - In this paper, the number of failing fuel rods in a large break loss-of-coolant accident (LB-LOCA) in EPR-type nuclear power plant is evaluated using statistical methods. For this purpose, a statistical fuel failure analysis procedure has been developed. The developed method utilizes the results of nonparametric statistics, the Wilks' formula in particular, and is based on the selection and variation of parameters that are important in accident conditions. The accident scenario is simulated with the coupled fuel performance - thermal hydraulics code FRAPTRAN-GENFLO using various parameter values and thermal hydraulic and power history boundary conditions between the simulations. The number of global scenarios is 59 (given by the Wilks' formula), and 1000 rods are simulated in each scenario. The boundary conditions are obtained from a new statistical version of the system code APROS. As a result, in the worst global scenario, 1.2% of the simulated rods failed, and it can be concluded that the Finnish safety regulations are hereby met (max. 10% of the rods allowed to fail).

    KW - loss-of-coolant accident

    KW - EPR

    KW - Wilks' formula

    KW - FRAPTRAN-GENFLO

    KW - APROS

    KW - statistical fuel failure analysis

    U2 - 10.1016/j.nucengdes.2014.12.023

    DO - 10.1016/j.nucengdes.2014.12.023

    M3 - Article

    VL - 285

    SP - 1

    EP - 14

    JO - Nuclear Engineering and Design

    JF - Nuclear Engineering and Design

    SN - 0029-5493

    ER -