Sensitivity analysis of local uncertainties in large break loss-of-coolant accident (LB-LOCA) thermo-mechanical simulations

Asko Arkoma (Corresponding Author), Timo M. J. Ikonen

    Research output: Contribution to journalArticleScientificpeer-review

    4 Citations (Scopus)

    Abstract

    In this paper, a sensitivity analysis for the data originating from a large break loss-of-coolant accident (LB-LOCA) analysis of an EPR-type nuclear power plant is presented. In the preceding LOCA analysis, the number of failing fuel rods in the accident was established (Arkoma et al., 2015). However, the underlying causes for rod failures were not addressed. It is essential to bring out which input parameters and boundary conditions have significance to the outcome of the analysis, i.e. the ballooning and burst of the rods. Due to complexity of the existing data, the first part of the analysis consists of defining the relevant input parameters for the sensitivity analysis. Then, selected sensitivity measures are calculated between the chosen input and output parameters. The ultimate goal is to develop a systematic procedure for the sensitivity analysis of statistical LOCA simulation that takes into account the various sources of uncertainties in the calculation chain. In the current analysis, the most relevant parameters with respect to the cladding integrity are the decay heat power during the transient, the thermal hydraulic conditions in the rod's location in reactor, and the steady-state irradiation history of the rod. Meanwhile, the tolerances in fuel manufacturing parameters were found to have negligible effect on cladding deformation
    Original languageEnglish
    Pages (from-to)293-302
    JournalNuclear Engineering and Design
    Volume305
    DOIs
    Publication statusPublished - 2016
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    loss of coolant
    Loss of coolant accidents
    sensitivity analysis
    accidents
    Sensitivity analysis
    accident
    rods
    simulation
    Nuclear power plants
    Paramagnetic resonance
    Accidents
    Hydraulics
    Boundary conditions
    Irradiation
    nuclear power plants
    electron spin resonance
    nuclear power plant
    hydraulics
    integrity
    bursts

    Keywords

    • loss-of-coolant accident
    • LOCA
    • sensitivity analysis
    • Borgonovo's delta
    • Sobol' sensitivity index
    • FRAPTRAN - GENFLO
    • EPR

    Cite this

    @article{583f44ff4a7e4f21afeddd67108a3abc,
    title = "Sensitivity analysis of local uncertainties in large break loss-of-coolant accident (LB-LOCA) thermo-mechanical simulations",
    abstract = "In this paper, a sensitivity analysis for the data originating from a large break loss-of-coolant accident (LB-LOCA) analysis of an EPR-type nuclear power plant is presented. In the preceding LOCA analysis, the number of failing fuel rods in the accident was established (Arkoma et al., 2015). However, the underlying causes for rod failures were not addressed. It is essential to bring out which input parameters and boundary conditions have significance to the outcome of the analysis, i.e. the ballooning and burst of the rods. Due to complexity of the existing data, the first part of the analysis consists of defining the relevant input parameters for the sensitivity analysis. Then, selected sensitivity measures are calculated between the chosen input and output parameters. The ultimate goal is to develop a systematic procedure for the sensitivity analysis of statistical LOCA simulation that takes into account the various sources of uncertainties in the calculation chain. In the current analysis, the most relevant parameters with respect to the cladding integrity are the decay heat power during the transient, the thermal hydraulic conditions in the rod's location in reactor, and the steady-state irradiation history of the rod. Meanwhile, the tolerances in fuel manufacturing parameters were found to have negligible effect on cladding deformation",
    keywords = "loss-of-coolant accident, LOCA, sensitivity analysis, Borgonovo's delta, Sobol' sensitivity index, FRAPTRAN - GENFLO, EPR",
    author = "Asko Arkoma and Ikonen, {Timo M. J.}",
    year = "2016",
    doi = "10.1016/j.nucengdes.2016.06.002",
    language = "English",
    volume = "305",
    pages = "293--302",
    journal = "Nuclear Engineering and Design",
    issn = "0029-5493",
    publisher = "Elsevier",

    }

    Sensitivity analysis of local uncertainties in large break loss-of-coolant accident (LB-LOCA) thermo-mechanical simulations. / Arkoma, Asko (Corresponding Author); Ikonen, Timo M. J.

    In: Nuclear Engineering and Design, Vol. 305, 2016, p. 293-302.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Sensitivity analysis of local uncertainties in large break loss-of-coolant accident (LB-LOCA) thermo-mechanical simulations

    AU - Arkoma, Asko

    AU - Ikonen, Timo M. J.

    PY - 2016

    Y1 - 2016

    N2 - In this paper, a sensitivity analysis for the data originating from a large break loss-of-coolant accident (LB-LOCA) analysis of an EPR-type nuclear power plant is presented. In the preceding LOCA analysis, the number of failing fuel rods in the accident was established (Arkoma et al., 2015). However, the underlying causes for rod failures were not addressed. It is essential to bring out which input parameters and boundary conditions have significance to the outcome of the analysis, i.e. the ballooning and burst of the rods. Due to complexity of the existing data, the first part of the analysis consists of defining the relevant input parameters for the sensitivity analysis. Then, selected sensitivity measures are calculated between the chosen input and output parameters. The ultimate goal is to develop a systematic procedure for the sensitivity analysis of statistical LOCA simulation that takes into account the various sources of uncertainties in the calculation chain. In the current analysis, the most relevant parameters with respect to the cladding integrity are the decay heat power during the transient, the thermal hydraulic conditions in the rod's location in reactor, and the steady-state irradiation history of the rod. Meanwhile, the tolerances in fuel manufacturing parameters were found to have negligible effect on cladding deformation

    AB - In this paper, a sensitivity analysis for the data originating from a large break loss-of-coolant accident (LB-LOCA) analysis of an EPR-type nuclear power plant is presented. In the preceding LOCA analysis, the number of failing fuel rods in the accident was established (Arkoma et al., 2015). However, the underlying causes for rod failures were not addressed. It is essential to bring out which input parameters and boundary conditions have significance to the outcome of the analysis, i.e. the ballooning and burst of the rods. Due to complexity of the existing data, the first part of the analysis consists of defining the relevant input parameters for the sensitivity analysis. Then, selected sensitivity measures are calculated between the chosen input and output parameters. The ultimate goal is to develop a systematic procedure for the sensitivity analysis of statistical LOCA simulation that takes into account the various sources of uncertainties in the calculation chain. In the current analysis, the most relevant parameters with respect to the cladding integrity are the decay heat power during the transient, the thermal hydraulic conditions in the rod's location in reactor, and the steady-state irradiation history of the rod. Meanwhile, the tolerances in fuel manufacturing parameters were found to have negligible effect on cladding deformation

    KW - loss-of-coolant accident

    KW - LOCA

    KW - sensitivity analysis

    KW - Borgonovo's delta

    KW - Sobol' sensitivity index

    KW - FRAPTRAN - GENFLO

    KW - EPR

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    DO - 10.1016/j.nucengdes.2016.06.002

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    JO - Nuclear Engineering and Design

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