Reactor physics and dynamics (READY): Validation of TRAB-3D

Antti Daavittila, Hanna Räty

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

    Abstract

    TRAB-3D is a reactor dynamics code with three-dimensional neutronics coupled to core and circuit thermal-hydraulics. The code, entirely developed at VTT, can be used in transient and accident analyses of boiling (BWR) and pressurized water (PWR) reactors with rectangular fuel bundle geometry. The validation history of TRAB-3D includes calculation of international benchmark exercises, as well as comparisons with measured data from real plant transients. The most recent validation case is a load rejection test performed at the Olkiluoto 1 nuclear power plant in 1998 in connection with the power uprating project. The fact that there is local power measurement data available from this test makes it a suitable case for three-dimensional core model validation. The agreement between the results of the TRAB-3D calculation and the measurements is very good.
    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
    Pages127-133
    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

    Physics
    Pressurized water reactors
    Boiling liquids
    Nuclear power plants
    Accidents
    Hydraulics
    Geometry
    Networks (circuits)
    Hot Temperature

    Cite this

    Daavittila, A., & Räty, H. (2002). Reactor physics and dynamics (READY): Validation of TRAB-3D. In FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report (pp. 127-133). Espoo: VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2164
    Daavittila, Antti ; Räty, Hanna. / Reactor physics and dynamics (READY) : Validation of TRAB-3D. FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo : VTT Technical Research Centre of Finland, 2002. pp. 127-133 (VTT Tiedotteita - Research Notes; No. 2164).
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    abstract = "TRAB-3D is a reactor dynamics code with three-dimensional neutronics coupled to core and circuit thermal-hydraulics. The code, entirely developed at VTT, can be used in transient and accident analyses of boiling (BWR) and pressurized water (PWR) reactors with rectangular fuel bundle geometry. The validation history of TRAB-3D includes calculation of international benchmark exercises, as well as comparisons with measured data from real plant transients. The most recent validation case is a load rejection test performed at the Olkiluoto 1 nuclear power plant in 1998 in connection with the power uprating project. The fact that there is local power measurement data available from this test makes it a suitable case for three-dimensional core model validation. The agreement between the results of the TRAB-3D calculation and the measurements is very good.",
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    Daavittila, A & Räty, H 2002, Reactor physics and dynamics (READY): Validation of TRAB-3D. 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. 127-133.

    Reactor physics and dynamics (READY) : Validation of TRAB-3D. / Daavittila, Antti; Räty, Hanna.

    FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo : VTT Technical Research Centre of Finland, 2002. p. 127-133 (VTT Tiedotteita - Research Notes; No. 2164).

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

    TY - CHAP

    T1 - Reactor physics and dynamics (READY)

    T2 - Validation of TRAB-3D

    AU - Daavittila, Antti

    AU - Räty, Hanna

    PY - 2002

    Y1 - 2002

    N2 - TRAB-3D is a reactor dynamics code with three-dimensional neutronics coupled to core and circuit thermal-hydraulics. The code, entirely developed at VTT, can be used in transient and accident analyses of boiling (BWR) and pressurized water (PWR) reactors with rectangular fuel bundle geometry. The validation history of TRAB-3D includes calculation of international benchmark exercises, as well as comparisons with measured data from real plant transients. The most recent validation case is a load rejection test performed at the Olkiluoto 1 nuclear power plant in 1998 in connection with the power uprating project. The fact that there is local power measurement data available from this test makes it a suitable case for three-dimensional core model validation. The agreement between the results of the TRAB-3D calculation and the measurements is very good.

    AB - TRAB-3D is a reactor dynamics code with three-dimensional neutronics coupled to core and circuit thermal-hydraulics. The code, entirely developed at VTT, can be used in transient and accident analyses of boiling (BWR) and pressurized water (PWR) reactors with rectangular fuel bundle geometry. The validation history of TRAB-3D includes calculation of international benchmark exercises, as well as comparisons with measured data from real plant transients. The most recent validation case is a load rejection test performed at the Olkiluoto 1 nuclear power plant in 1998 in connection with the power uprating project. The fact that there is local power measurement data available from this test makes it a suitable case for three-dimensional core model validation. The agreement between the results of the TRAB-3D calculation and the measurements is very good.

    M3 - Chapter or book article

    SN - 951-38-6085-X

    T3 - VTT Tiedotteita - Research Notes

    SP - 127

    EP - 133

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

    PB - VTT Technical Research Centre of Finland

    CY - Espoo

    ER -

    Daavittila A, Räty H. Reactor physics and dynamics (READY): Validation of TRAB-3D. In FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo: VTT Technical Research Centre of Finland. 2002. p. 127-133. (VTT Tiedotteita - Research Notes; No. 2164).