Dynamic post-analysis of a feed water pipe at the Loviisa nuclear power plant

Arja Saarenheimo, Lauri Eerikäinen, Rauli Keskinen

    Research output: Contribution to journal › Article › Scientific › peer-review

    Abstract

    A dynamic post-analysis is presented for a sudden pipe break which occurTed in the main feed water ~ystem of the VVER 440 type PWR plant Loviisa 2 on February 25, 1993. A thermal hydraulic code TMOC, based on the method of characteristics, is first used to determine the induced rapid two phase fluid transients. The resulting pressure and momentum flux histories are then applied as an excitation in a nonlinear structural dynamic analysis which makes use of the general purpose finite element code ABAQUS. The permanent relative displacement of the broken pipe ends is finally compared with the value observed after the event. An underestimate of some 30% may for the most part be attributed to scant experimental data and uncertainties in boundary conditions. Assumptions regarding impact against a nearby beam structure and the dynamic stress-strain curve of the fenitic pipe material strongly affect this comparison.
    Original languageEnglish
    Pages (from-to)41-55
    Number of pages15
    JournalRakenteiden Mekaniikka
    Volume27
    Issue number2
    Publication statusPublished - 1994
    MoE publication typeNot Eligible

    Fingerprint

    Nuclear power plants
    Pipe
    Water
    Structural dynamics
    ABAQUS
    Stress-strain curves
    Dynamic analysis
    Momentum
    Hydraulics
    Boundary conditions
    Fluxes
    Fluids
    Hot Temperature
    Uncertainty

    Cite this

    Saarenheimo, Arja ; Eerikäinen, Lauri ; Keskinen, Rauli. / Dynamic post-analysis of a feed water pipe at the Loviisa nuclear power plant. In: Rakenteiden Mekaniikka. 1994 ; Vol. 27, No. 2. pp. 41-55.
    @article{f71f12798ecd48aeb6db7dd4306bfc8e,
    title = "Dynamic post-analysis of a feed water pipe at the Loviisa nuclear power plant",
    abstract = "A dynamic post-analysis is presented for a sudden pipe break which occurTed in the main feed water ~ystem of the VVER 440 type PWR plant Loviisa 2 on February 25, 1993. A thermal hydraulic code TMOC, based on the method of characteristics, is first used to determine the induced rapid two phase fluid transients. The resulting pressure and momentum flux histories are then applied as an excitation in a nonlinear structural dynamic analysis which makes use of the general purpose finite element code ABAQUS. The permanent relative displacement of the broken pipe ends is finally compared with the value observed after the event. An underestimate of some 30{\%} may for the most part be attributed to scant experimental data and uncertainties in boundary conditions. Assumptions regarding impact against a nearby beam structure and the dynamic stress-strain curve of the fenitic pipe material strongly affect this comparison.",
    author = "Arja Saarenheimo and Lauri Eerik{\"a}inen and Rauli Keskinen",
    note = "Project code: VAL37051",
    year = "1994",
    language = "English",
    volume = "27",
    pages = "41--55",
    journal = "Rakenteiden Mekaniikka",
    issn = "0783-6104",
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    Saarenheimo, A, Eerikäinen, L & Keskinen, R 1994, 'Dynamic post-analysis of a feed water pipe at the Loviisa nuclear power plant', Rakenteiden Mekaniikka, vol. 27, no. 2, pp. 41-55.

    Dynamic post-analysis of a feed water pipe at the Loviisa nuclear power plant. / Saarenheimo, Arja; Eerikäinen, Lauri; Keskinen, Rauli.

    In: Rakenteiden Mekaniikka, Vol. 27, No. 2, 1994, p. 41-55.

    Research output: Contribution to journal › Article › Scientific › peer-review

    TY - JOUR

    T1 - Dynamic post-analysis of a feed water pipe at the Loviisa nuclear power plant

    AU - Saarenheimo, Arja

    AU - Eerikäinen, Lauri

    AU - Keskinen, Rauli

    N1 - Project code: VAL37051

    PY - 1994

    Y1 - 1994

    N2 - A dynamic post-analysis is presented for a sudden pipe break which occurTed in the main feed water ~ystem of the VVER 440 type PWR plant Loviisa 2 on February 25, 1993. A thermal hydraulic code TMOC, based on the method of characteristics, is first used to determine the induced rapid two phase fluid transients. The resulting pressure and momentum flux histories are then applied as an excitation in a nonlinear structural dynamic analysis which makes use of the general purpose finite element code ABAQUS. The permanent relative displacement of the broken pipe ends is finally compared with the value observed after the event. An underestimate of some 30% may for the most part be attributed to scant experimental data and uncertainties in boundary conditions. Assumptions regarding impact against a nearby beam structure and the dynamic stress-strain curve of the fenitic pipe material strongly affect this comparison.

    AB - A dynamic post-analysis is presented for a sudden pipe break which occurTed in the main feed water ~ystem of the VVER 440 type PWR plant Loviisa 2 on February 25, 1993. A thermal hydraulic code TMOC, based on the method of characteristics, is first used to determine the induced rapid two phase fluid transients. The resulting pressure and momentum flux histories are then applied as an excitation in a nonlinear structural dynamic analysis which makes use of the general purpose finite element code ABAQUS. The permanent relative displacement of the broken pipe ends is finally compared with the value observed after the event. An underestimate of some 30% may for the most part be attributed to scant experimental data and uncertainties in boundary conditions. Assumptions regarding impact against a nearby beam structure and the dynamic stress-strain curve of the fenitic pipe material strongly affect this comparison.

    M3 - Article

    VL - 27

    SP - 41

    EP - 55

    JO - Rakenteiden Mekaniikka

    JF - Rakenteiden Mekaniikka

    SN - 0783-6104

    IS - 2

    ER -

    Saarenheimo A, Eerikäinen L, Keskinen R. Dynamic post-analysis of a feed water pipe at the Loviisa nuclear power plant. Rakenteiden Mekaniikka. 1994;27(2):41-55.

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