Applying thermal hydraulics modeling in coupled processes of nuclear power plants: Dissertation

    Research output: ThesisDissertationCollection of Articles

    Abstract

    This thesis focuses on the validation of the coupled codes developed in Finland for the safety analyses of the lLight wWater rReactors in design basis accidents. The validation efforts and applications of the thermal hydraulics code SMABRE and the three-dimensional neutron kinetics codes are introduced for both the separate and coupled codes. The code development and coupling of codes for the safety analyses in Finland are discussed, and the present situation and possible future directions are described. The data for the code validation consists of the experimental data from test facilities, numerical benchmarks and data measured in real nuclear power plants. The nuclear core is relevant for the couplings of neutron kinetics and thermal hydraulics codes. Two European Union projects, in which ten transients at real VVER plants have been documented, as well as the other international benchmarks are dealt with as useful forums in the code validation. The simulation of plant measurements and several plant modeling aspects emerging from the validation work are gathered together. The main steam line break in different kinds of plants is dealt as an example of the application of the coupled codes in safety analysis. The coupling of a thermal hydraulic code with a fuel transient performance code is illustrated in the thesis as a new approach to performing the safety analyses. Another new approach is the sensitivity and uncertainty analyses performed for a Loviisa plant turbine trip case. In addition to this summary, the thesis consists of seven publications in appendices: five articles in scientific journals and two conference papers.
    Original languageEnglish
    QualificationDoctor Degree
    Awarding Institution
    • Lappeenranta University of Technology
    Supervisors/Advisors
    • Kyrki-Rajamäki, Riitta, Supervisor, External person
    Award date4 Nov 2005
    Place of PublicationEspoo
    Publisher
    Print ISBNs951-38-6667-X
    Electronic ISBNs951-38-6668-8
    Publication statusPublished - 2005
    MoE publication typeG5 Doctoral dissertation (article)

    Fingerprint

    Nuclear power plants
    Hydraulics
    Neutrons
    Steam piping systems
    Kinetics
    Test facilities
    Accidents
    Turbines
    Hot Temperature

    Keywords

    • thermal hydraulics
    • modeling
    • coupled processes
    • nuclear power plants
    • code validation
    • coupled codes
    • safety analysis
    • neutron kinetics
    • SMABRE
    • HEXTRAN

    Cite this

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    title = "Applying thermal hydraulics modeling in coupled processes of nuclear power plants: Dissertation",
    abstract = "This thesis focuses on the validation of the coupled codes developed in Finland for the safety analyses of the lLight wWater rReactors in design basis accidents. The validation efforts and applications of the thermal hydraulics code SMABRE and the three-dimensional neutron kinetics codes are introduced for both the separate and coupled codes. The code development and coupling of codes for the safety analyses in Finland are discussed, and the present situation and possible future directions are described. The data for the code validation consists of the experimental data from test facilities, numerical benchmarks and data measured in real nuclear power plants. The nuclear core is relevant for the couplings of neutron kinetics and thermal hydraulics codes. Two European Union projects, in which ten transients at real VVER plants have been documented, as well as the other international benchmarks are dealt with as useful forums in the code validation. The simulation of plant measurements and several plant modeling aspects emerging from the validation work are gathered together. The main steam line break in different kinds of plants is dealt as an example of the application of the coupled codes in safety analysis. The coupling of a thermal hydraulic code with a fuel transient performance code is illustrated in the thesis as a new approach to performing the safety analyses. Another new approach is the sensitivity and uncertainty analyses performed for a Loviisa plant turbine trip case. In addition to this summary, the thesis consists of seven publications in appendices: five articles in scientific journals and two conference papers.",
    keywords = "thermal hydraulics, modeling, coupled processes, nuclear power plants, code validation, coupled codes, safety analysis, neutron kinetics, SMABRE, HEXTRAN",
    author = "Anitta H{\"a}m{\"a}l{\"a}inen",
    note = "Project code: C3SU00180",
    year = "2005",
    language = "English",
    isbn = "951-38-6667-X",
    series = "VTT Publications",
    publisher = "VTT Technical Research Centre of Finland",
    number = "578",
    address = "Finland",
    school = "Lappeenranta University of Technology",

    }

    Applying thermal hydraulics modeling in coupled processes of nuclear power plants : Dissertation. / Hämäläinen, Anitta.

    Espoo : VTT Technical Research Centre of Finland, 2005. 153 p.

    Research output: ThesisDissertationCollection of Articles

    TY - THES

    T1 - Applying thermal hydraulics modeling in coupled processes of nuclear power plants

    T2 - Dissertation

    AU - Hämäläinen, Anitta

    N1 - Project code: C3SU00180

    PY - 2005

    Y1 - 2005

    N2 - This thesis focuses on the validation of the coupled codes developed in Finland for the safety analyses of the lLight wWater rReactors in design basis accidents. The validation efforts and applications of the thermal hydraulics code SMABRE and the three-dimensional neutron kinetics codes are introduced for both the separate and coupled codes. The code development and coupling of codes for the safety analyses in Finland are discussed, and the present situation and possible future directions are described. The data for the code validation consists of the experimental data from test facilities, numerical benchmarks and data measured in real nuclear power plants. The nuclear core is relevant for the couplings of neutron kinetics and thermal hydraulics codes. Two European Union projects, in which ten transients at real VVER plants have been documented, as well as the other international benchmarks are dealt with as useful forums in the code validation. The simulation of plant measurements and several plant modeling aspects emerging from the validation work are gathered together. The main steam line break in different kinds of plants is dealt as an example of the application of the coupled codes in safety analysis. The coupling of a thermal hydraulic code with a fuel transient performance code is illustrated in the thesis as a new approach to performing the safety analyses. Another new approach is the sensitivity and uncertainty analyses performed for a Loviisa plant turbine trip case. In addition to this summary, the thesis consists of seven publications in appendices: five articles in scientific journals and two conference papers.

    AB - This thesis focuses on the validation of the coupled codes developed in Finland for the safety analyses of the lLight wWater rReactors in design basis accidents. The validation efforts and applications of the thermal hydraulics code SMABRE and the three-dimensional neutron kinetics codes are introduced for both the separate and coupled codes. The code development and coupling of codes for the safety analyses in Finland are discussed, and the present situation and possible future directions are described. The data for the code validation consists of the experimental data from test facilities, numerical benchmarks and data measured in real nuclear power plants. The nuclear core is relevant for the couplings of neutron kinetics and thermal hydraulics codes. Two European Union projects, in which ten transients at real VVER plants have been documented, as well as the other international benchmarks are dealt with as useful forums in the code validation. The simulation of plant measurements and several plant modeling aspects emerging from the validation work are gathered together. The main steam line break in different kinds of plants is dealt as an example of the application of the coupled codes in safety analysis. The coupling of a thermal hydraulic code with a fuel transient performance code is illustrated in the thesis as a new approach to performing the safety analyses. Another new approach is the sensitivity and uncertainty analyses performed for a Loviisa plant turbine trip case. In addition to this summary, the thesis consists of seven publications in appendices: five articles in scientific journals and two conference papers.

    KW - thermal hydraulics

    KW - modeling

    KW - coupled processes

    KW - nuclear power plants

    KW - code validation

    KW - coupled codes

    KW - safety analysis

    KW - neutron kinetics

    KW - SMABRE

    KW - HEXTRAN

    M3 - Dissertation

    SN - 951-38-6667-X

    T3 - VTT Publications

    PB - VTT Technical Research Centre of Finland

    CY - Espoo

    ER -