Reactor physics and dynamics (READY): READY summary report

Hanna Räty, Antti Daavittila

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

    Abstract

    As a result of upgrading, adapting, developing and validating several reactor physics and dynamics codes of VTT's code system more accurate calculations and predictions of physical phenomena can now be performed. Three-dimensional reactor physics codes have been introduced and validated for various applications, especially for out-of-core flux, criticality safety, and dose rate calculations. A multi-temperature MCNP cross section and scattering law library has been created. Most recently Monte Carlo technique has been applied in burnup calculations. Development of a new advanced nodal model has resulted in a highly promising new BWR simulator code, ensuring independent calculational capabilities for steady state and safety analyses. Validation of VTT's three-dimensional BWR dynamics code has been completed, and analyses with three-dimensional core models can be carried out for PWR, BWR and VVER type reactors. Until now, the transient analyses for BWRs have been done with one-dimensional models. Fuel models of the dynamics codes have been improved, and USNRC's fuel behaviour code has been coupled with VTT's advanced hydraulics model. The coupled code has been delivered to USA in agreement with USNRC. Development and application of a sophisticated hydraulics solver in reactor dynamics has resulted in a BWR circuit model that has been tested in steady state calculations.
    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
    Pages113-126
    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

    reactor physics
    hydraulics
    safety
    reactors
    upgrading
    simulators
    dosage

    Cite this

    Räty, H., & Daavittila, A. (2002). Reactor physics and dynamics (READY): READY summary report. In FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report (pp. 113-126). Espoo: VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2164
    Räty, Hanna ; Daavittila, Antti. / Reactor physics and dynamics (READY) : READY summary report. FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo : VTT Technical Research Centre of Finland, 2002. pp. 113-126 (VTT Tiedotteita - Research Notes; No. 2164).
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    Räty, H & Daavittila, A 2002, Reactor physics and dynamics (READY): READY summary report. 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. 113-126.

    Reactor physics and dynamics (READY) : READY summary report. / Räty, Hanna; Daavittila, Antti.

    FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo : VTT Technical Research Centre of Finland, 2002. p. 113-126 (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 - READY summary report

    AU - Räty, Hanna

    AU - Daavittila, Antti

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    N2 - As a result of upgrading, adapting, developing and validating several reactor physics and dynamics codes of VTT's code system more accurate calculations and predictions of physical phenomena can now be performed. Three-dimensional reactor physics codes have been introduced and validated for various applications, especially for out-of-core flux, criticality safety, and dose rate calculations. A multi-temperature MCNP cross section and scattering law library has been created. Most recently Monte Carlo technique has been applied in burnup calculations. Development of a new advanced nodal model has resulted in a highly promising new BWR simulator code, ensuring independent calculational capabilities for steady state and safety analyses. Validation of VTT's three-dimensional BWR dynamics code has been completed, and analyses with three-dimensional core models can be carried out for PWR, BWR and VVER type reactors. Until now, the transient analyses for BWRs have been done with one-dimensional models. Fuel models of the dynamics codes have been improved, and USNRC's fuel behaviour code has been coupled with VTT's advanced hydraulics model. The coupled code has been delivered to USA in agreement with USNRC. Development and application of a sophisticated hydraulics solver in reactor dynamics has resulted in a BWR circuit model that has been tested in steady state calculations.

    AB - As a result of upgrading, adapting, developing and validating several reactor physics and dynamics codes of VTT's code system more accurate calculations and predictions of physical phenomena can now be performed. Three-dimensional reactor physics codes have been introduced and validated for various applications, especially for out-of-core flux, criticality safety, and dose rate calculations. A multi-temperature MCNP cross section and scattering law library has been created. Most recently Monte Carlo technique has been applied in burnup calculations. Development of a new advanced nodal model has resulted in a highly promising new BWR simulator code, ensuring independent calculational capabilities for steady state and safety analyses. Validation of VTT's three-dimensional BWR dynamics code has been completed, and analyses with three-dimensional core models can be carried out for PWR, BWR and VVER type reactors. Until now, the transient analyses for BWRs have been done with one-dimensional models. Fuel models of the dynamics codes have been improved, and USNRC's fuel behaviour code has been coupled with VTT's advanced hydraulics model. The coupled code has been delivered to USA in agreement with USNRC. Development and application of a sophisticated hydraulics solver in reactor dynamics has resulted in a BWR circuit model that has been tested in steady state calculations.

    M3 - Chapter or book article

    SN - 951-38-6085-X

    T3 - VTT Tiedotteita - Research Notes

    SP - 113

    EP - 126

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

    PB - VTT Technical Research Centre of Finland

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    ER -

    Räty H, Daavittila A. Reactor physics and dynamics (READY): READY summary report. In FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo: VTT Technical Research Centre of Finland. 2002. p. 113-126. (VTT Tiedotteita - Research Notes; No. 2164).