Transient behaviour of high burnup fuel (KOTO): Coupling of FRAPTRAN Fuel Rod for Transient Analysis with GENFLO Thermal Hydraulic Code (KOTO & READY)

Jan-Olof Stengård, Anitta Hämäläinen, Jaakko Miettinen

    Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

    Abstract

    Reactor analyses are becoming more and more challenging. Due to pursuing higher fuel discharge burnups, fuel designs and operational conditions are subject to constant upgrading. Advances in hardware have removed many of the limitations on detail of analyses, and best-estimate type applications have become a commonplace, a practice now increasingly adopted even in safety cases. At the same time there is a regulatory trend extending the range of events the licensee is to consider. Neutronics, thermal hydraulics, and fuel behaviour are closely interlinked during a reactor transient and cannot be generally separated in a realistic description. However, attempts to combine these into coupled models have been, even at their best, impracticably heavy to use. At VTT, in consent with the USNRC, an in-house general flow model GENFLO has now been coupled with the NRC's FRAPTRAN fuel performance code. The combination takes benefits of a fast-running non-iterative thermal hydraulic model and an updated fuel performance code validated for burnups of up to 65 MWd/kgU. A code description and results of two types of analyses are given. One is a hypothetical large break loss-of-coolant accident (LBLOCA) in a VVER reactor, the other is an instability transient in a Boiling Water Reactor (BWR), for which system conditions were separately available. A systematic validation and international peer review will follow.
    Original languageEnglish
    Title of host publicationFINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002
    Subtitle of host publicationFinal Report
    Place of PublicationEspoo
    PublisherVTT Technical Research Centre of Finland
    Pages104-111
    ISBN (Electronic)951-38-6086-8
    ISBN (Print)951-38-6085-X
    Publication statusPublished - 2002
    MoE publication typeNot Eligible

    Publication series

    SeriesVTT Tiedotteita - Research Notes
    Number2164
    ISSN1235-0605

    Fingerprint

    Transient analysis
    Hydraulics
    Loss of coolant accidents
    Boiling water reactors
    Hydraulic models
    Hot Temperature
    Hardware

    Cite this

    Stengård, J-O., Hämäläinen, A., & Miettinen, J. (2002). Transient behaviour of high burnup fuel (KOTO): Coupling of FRAPTRAN Fuel Rod for Transient Analysis with GENFLO Thermal Hydraulic Code (KOTO & READY). In FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report (pp. 104-111). Espoo: VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2164
    Stengård, Jan-Olof ; Hämäläinen, Anitta ; Miettinen, Jaakko. / Transient behaviour of high burnup fuel (KOTO) : Coupling of FRAPTRAN Fuel Rod for Transient Analysis with GENFLO Thermal Hydraulic Code (KOTO & READY). FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo : VTT Technical Research Centre of Finland, 2002. pp. 104-111 (VTT Tiedotteita - Research Notes; No. 2164).
    @inbook{334744b2dd8143e29e95ff154eb8b407,
    title = "Transient behaviour of high burnup fuel (KOTO): Coupling of FRAPTRAN Fuel Rod for Transient Analysis with GENFLO Thermal Hydraulic Code (KOTO & READY)",
    abstract = "Reactor analyses are becoming more and more challenging. Due to pursuing higher fuel discharge burnups, fuel designs and operational conditions are subject to constant upgrading. Advances in hardware have removed many of the limitations on detail of analyses, and best-estimate type applications have become a commonplace, a practice now increasingly adopted even in safety cases. At the same time there is a regulatory trend extending the range of events the licensee is to consider. Neutronics, thermal hydraulics, and fuel behaviour are closely interlinked during a reactor transient and cannot be generally separated in a realistic description. However, attempts to combine these into coupled models have been, even at their best, impracticably heavy to use. At VTT, in consent with the USNRC, an in-house general flow model GENFLO has now been coupled with the NRC's FRAPTRAN fuel performance code. The combination takes benefits of a fast-running non-iterative thermal hydraulic model and an updated fuel performance code validated for burnups of up to 65 MWd/kgU. A code description and results of two types of analyses are given. One is a hypothetical large break loss-of-coolant accident (LBLOCA) in a VVER reactor, the other is an instability transient in a Boiling Water Reactor (BWR), for which system conditions were separately available. A systematic validation and international peer review will follow.",
    author = "Jan-Olof Steng{\aa}rd and Anitta H{\"a}m{\"a}l{\"a}inen and Jaakko Miettinen",
    year = "2002",
    language = "English",
    isbn = "951-38-6085-X",
    series = "VTT Tiedotteita - Research Notes",
    publisher = "VTT Technical Research Centre of Finland",
    number = "2164",
    pages = "104--111",
    booktitle = "FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002",
    address = "Finland",

    }

    Stengård, J-O, Hämäläinen, A & Miettinen, J 2002, Transient behaviour of high burnup fuel (KOTO): Coupling of FRAPTRAN Fuel Rod for Transient Analysis with GENFLO Thermal Hydraulic Code (KOTO & READY). in FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita - Research Notes, no. 2164, pp. 104-111.

    Transient behaviour of high burnup fuel (KOTO) : Coupling of FRAPTRAN Fuel Rod for Transient Analysis with GENFLO Thermal Hydraulic Code (KOTO & READY). / Stengård, Jan-Olof; Hämäläinen, Anitta; Miettinen, Jaakko.

    FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo : VTT Technical Research Centre of Finland, 2002. p. 104-111 (VTT Tiedotteita - Research Notes; No. 2164).

    Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

    TY - CHAP

    T1 - Transient behaviour of high burnup fuel (KOTO)

    T2 - Coupling of FRAPTRAN Fuel Rod for Transient Analysis with GENFLO Thermal Hydraulic Code (KOTO & READY)

    AU - Stengård, Jan-Olof

    AU - Hämäläinen, Anitta

    AU - Miettinen, Jaakko

    PY - 2002

    Y1 - 2002

    N2 - Reactor analyses are becoming more and more challenging. Due to pursuing higher fuel discharge burnups, fuel designs and operational conditions are subject to constant upgrading. Advances in hardware have removed many of the limitations on detail of analyses, and best-estimate type applications have become a commonplace, a practice now increasingly adopted even in safety cases. At the same time there is a regulatory trend extending the range of events the licensee is to consider. Neutronics, thermal hydraulics, and fuel behaviour are closely interlinked during a reactor transient and cannot be generally separated in a realistic description. However, attempts to combine these into coupled models have been, even at their best, impracticably heavy to use. At VTT, in consent with the USNRC, an in-house general flow model GENFLO has now been coupled with the NRC's FRAPTRAN fuel performance code. The combination takes benefits of a fast-running non-iterative thermal hydraulic model and an updated fuel performance code validated for burnups of up to 65 MWd/kgU. A code description and results of two types of analyses are given. One is a hypothetical large break loss-of-coolant accident (LBLOCA) in a VVER reactor, the other is an instability transient in a Boiling Water Reactor (BWR), for which system conditions were separately available. A systematic validation and international peer review will follow.

    AB - Reactor analyses are becoming more and more challenging. Due to pursuing higher fuel discharge burnups, fuel designs and operational conditions are subject to constant upgrading. Advances in hardware have removed many of the limitations on detail of analyses, and best-estimate type applications have become a commonplace, a practice now increasingly adopted even in safety cases. At the same time there is a regulatory trend extending the range of events the licensee is to consider. Neutronics, thermal hydraulics, and fuel behaviour are closely interlinked during a reactor transient and cannot be generally separated in a realistic description. However, attempts to combine these into coupled models have been, even at their best, impracticably heavy to use. At VTT, in consent with the USNRC, an in-house general flow model GENFLO has now been coupled with the NRC's FRAPTRAN fuel performance code. The combination takes benefits of a fast-running non-iterative thermal hydraulic model and an updated fuel performance code validated for burnups of up to 65 MWd/kgU. A code description and results of two types of analyses are given. One is a hypothetical large break loss-of-coolant accident (LBLOCA) in a VVER reactor, the other is an instability transient in a Boiling Water Reactor (BWR), for which system conditions were separately available. A systematic validation and international peer review will follow.

    M3 - Chapter or book article

    SN - 951-38-6085-X

    T3 - VTT Tiedotteita - Research Notes

    SP - 104

    EP - 111

    BT - FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002

    PB - VTT Technical Research Centre of Finland

    CY - Espoo

    ER -

    Stengård J-O, Hämäläinen A, Miettinen J. Transient behaviour of high burnup fuel (KOTO): Coupling of FRAPTRAN Fuel Rod for Transient Analysis with GENFLO Thermal Hydraulic Code (KOTO & READY). In FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo: VTT Technical Research Centre of Finland. 2002. p. 104-111. (VTT Tiedotteita - Research Notes; No. 2164).