HEXTRAN-SMABRE calculation of the VVER-1000 coolant transient-1 benchmark

Elina Syrjälahti (Corresponding Author), Anitta Hämäläinen

    Research output: Contribution to journalArticleScientificpeer-review

    Abstract

    The VVER-1000 coolant transient benchmark is intended for validation of couplings of the thermal hydraulic codes and three-dimensional neutron kinetic core models. It concerns switching on a main coolant pump when the other three main coolant pumps are in operation. The problem is based on an experiment performed in Kozloduy NPP in Bulgaria. In addition to the real plant transient, an extreme scenario concerning a control rod ejection after switching on a main coolant pump was calculated. At VTT the three-dimensional advanced nodal code HEXTRAN is used for the core dynamics, and the system code SMABRE as a thermal hydraulic model for the primary and secondary loop. The parallelly coupled HEXTRAN–SMABRE code has been in production use since early 1990s, and it has been extensively used for analyses of VVER NPPs. The SMABRE input model is based on the standard VVER-1000 input used at VTT. The whole core calculation is performed with HEXTRAN. Also the core model is based on earlier VVER-1000 models. Nuclear data for the calculation were specified in the benchmark. The paper outlines the input models used for both codes. Calculated results are introduced both for the coupled core system with inlet and outlet boundary conditions and for the whole plant model. Parametric studies have been performed for selected parameters.
    Original languageEnglish
    Pages (from-to)849-864
    Number of pages16
    JournalProgress in Nuclear Energy
    Volume48
    Issue number8
    DOIs
    Publication statusPublished - 2006
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Coolants
    Pumps
    pump
    Control rods
    Hydraulic models
    hydraulics
    calculation
    Neutrons
    Hydraulics
    Boundary conditions
    boundary condition
    code
    Kinetics
    kinetics
    Experiments
    experiment
    Hot Temperature

    Keywords

    • reactor dynamics
    • coupled codes
    • coolants
    • light water reactor coolant
    • light water reactors

    Cite this

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    title = "HEXTRAN-SMABRE calculation of the VVER-1000 coolant transient-1 benchmark",
    abstract = "The VVER-1000 coolant transient benchmark is intended for validation of couplings of the thermal hydraulic codes and three-dimensional neutron kinetic core models. It concerns switching on a main coolant pump when the other three main coolant pumps are in operation. The problem is based on an experiment performed in Kozloduy NPP in Bulgaria. In addition to the real plant transient, an extreme scenario concerning a control rod ejection after switching on a main coolant pump was calculated. At VTT the three-dimensional advanced nodal code HEXTRAN is used for the core dynamics, and the system code SMABRE as a thermal hydraulic model for the primary and secondary loop. The parallelly coupled HEXTRAN–SMABRE code has been in production use since early 1990s, and it has been extensively used for analyses of VVER NPPs. The SMABRE input model is based on the standard VVER-1000 input used at VTT. The whole core calculation is performed with HEXTRAN. Also the core model is based on earlier VVER-1000 models. Nuclear data for the calculation were specified in the benchmark. The paper outlines the input models used for both codes. Calculated results are introduced both for the coupled core system with inlet and outlet boundary conditions and for the whole plant model. Parametric studies have been performed for selected parameters.",
    keywords = "reactor dynamics, coupled codes, coolants, light water reactor coolant, light water reactors",
    author = "Elina Syrj{\"a}lahti and Anitta H{\"a}m{\"a}l{\"a}inen",
    year = "2006",
    doi = "10.1016/j.pnucene.2006.06.007",
    language = "English",
    volume = "48",
    pages = "849--864",
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    }

    HEXTRAN-SMABRE calculation of the VVER-1000 coolant transient-1 benchmark. / Syrjälahti, Elina (Corresponding Author); Hämäläinen, Anitta.

    In: Progress in Nuclear Energy, Vol. 48, No. 8, 2006, p. 849-864.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

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    AU - Hämäläinen, Anitta

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    N2 - The VVER-1000 coolant transient benchmark is intended for validation of couplings of the thermal hydraulic codes and three-dimensional neutron kinetic core models. It concerns switching on a main coolant pump when the other three main coolant pumps are in operation. The problem is based on an experiment performed in Kozloduy NPP in Bulgaria. In addition to the real plant transient, an extreme scenario concerning a control rod ejection after switching on a main coolant pump was calculated. At VTT the three-dimensional advanced nodal code HEXTRAN is used for the core dynamics, and the system code SMABRE as a thermal hydraulic model for the primary and secondary loop. The parallelly coupled HEXTRAN–SMABRE code has been in production use since early 1990s, and it has been extensively used for analyses of VVER NPPs. The SMABRE input model is based on the standard VVER-1000 input used at VTT. The whole core calculation is performed with HEXTRAN. Also the core model is based on earlier VVER-1000 models. Nuclear data for the calculation were specified in the benchmark. The paper outlines the input models used for both codes. Calculated results are introduced both for the coupled core system with inlet and outlet boundary conditions and for the whole plant model. Parametric studies have been performed for selected parameters.

    AB - The VVER-1000 coolant transient benchmark is intended for validation of couplings of the thermal hydraulic codes and three-dimensional neutron kinetic core models. It concerns switching on a main coolant pump when the other three main coolant pumps are in operation. The problem is based on an experiment performed in Kozloduy NPP in Bulgaria. In addition to the real plant transient, an extreme scenario concerning a control rod ejection after switching on a main coolant pump was calculated. At VTT the three-dimensional advanced nodal code HEXTRAN is used for the core dynamics, and the system code SMABRE as a thermal hydraulic model for the primary and secondary loop. The parallelly coupled HEXTRAN–SMABRE code has been in production use since early 1990s, and it has been extensively used for analyses of VVER NPPs. The SMABRE input model is based on the standard VVER-1000 input used at VTT. The whole core calculation is performed with HEXTRAN. Also the core model is based on earlier VVER-1000 models. Nuclear data for the calculation were specified in the benchmark. The paper outlines the input models used for both codes. Calculated results are introduced both for the coupled core system with inlet and outlet boundary conditions and for the whole plant model. Parametric studies have been performed for selected parameters.

    KW - reactor dynamics

    KW - coupled codes

    KW - coolants

    KW - light water reactor coolant

    KW - light water reactors

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    DO - 10.1016/j.pnucene.2006.06.007

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