Multiphysics simulations of fast transients in VVER-1000 and VVER-440 reactors

Elina Syrjälahti, Ville Valtavirta, Joonas Kättö, Henri Loukusa, Timo Ikonen, Jaakko Leppänen, Ville Tulkki

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

    Abstract

    FINIX is a recently developed fuel behaviour module that is designed to provide "simple but sufficient" descriptions of the most essential fuel behaviour phenomena in multiphysics simulations. In such simulations, it is possible to obtain significant improvement in the feedback to neutronics or thermal hydraulics modelling even with a relatively simple fuel performance model. In this work, FINIX is used as an internal fuel behaviour module both in reactor physics and in reactor dynamics codes to simulate coupled behaviour in fast transient scenarios. With the Monte Carlo reactor physics code Serpent we model a prompt transient in a VVER-1000 pin cell, and with the reactor dynamics code HEXTRAN, a control rod ejection accident in a VVER-440 reactor.
    Original languageEnglish
    Title of host publicationProceedings of the 11th International Conference on WWER Fuel Performance, Modeling and Experimental Support
    PublisherState Scientific and Technical Center for Nuclear and Radiation Safety SSTC NRS
    Number of pages10
    Publication statusPublished - 2015
    MoE publication typeB3 Non-refereed article in conference proceedings
    Event11th International Conference on WWER Fuel Performance, Modeling and Experimental Support - Varna, Bulgaria
    Duration: 28 Sep 20152 Oct 2015
    Conference number: 11

    Conference

    Conference11th International Conference on WWER Fuel Performance, Modeling and Experimental Support
    CountryBulgaria
    CityVarna
    Period28/09/152/10/15

    Fingerprint

    Physics
    Control rods
    Accidents
    Hydraulics
    Feedback
    Hot Temperature

    Keywords

    • FINIX
    • multiphysics
    • fuel behaviour module

    Cite this

    Syrjälahti, E., Valtavirta, V., Kättö, J., Loukusa, H., Ikonen, T., Leppänen, J., & Tulkki, V. (2015). Multiphysics simulations of fast transients in VVER-1000 and VVER-440 reactors. In Proceedings of the 11th International Conference on WWER Fuel Performance, Modeling and Experimental Support State Scientific and Technical Center for Nuclear and Radiation Safety SSTC NRS.
    Syrjälahti, Elina ; Valtavirta, Ville ; Kättö, Joonas ; Loukusa, Henri ; Ikonen, Timo ; Leppänen, Jaakko ; Tulkki, Ville. / Multiphysics simulations of fast transients in VVER-1000 and VVER-440 reactors. Proceedings of the 11th International Conference on WWER Fuel Performance, Modeling and Experimental Support. State Scientific and Technical Center for Nuclear and Radiation Safety SSTC NRS, 2015.
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    title = "Multiphysics simulations of fast transients in VVER-1000 and VVER-440 reactors",
    abstract = "FINIX is a recently developed fuel behaviour module that is designed to provide {"}simple but sufficient{"} descriptions of the most essential fuel behaviour phenomena in multiphysics simulations. In such simulations, it is possible to obtain significant improvement in the feedback to neutronics or thermal hydraulics modelling even with a relatively simple fuel performance model. In this work, FINIX is used as an internal fuel behaviour module both in reactor physics and in reactor dynamics codes to simulate coupled behaviour in fast transient scenarios. With the Monte Carlo reactor physics code Serpent we model a prompt transient in a VVER-1000 pin cell, and with the reactor dynamics code HEXTRAN, a control rod ejection accident in a VVER-440 reactor.",
    keywords = "FINIX, multiphysics, fuel behaviour module",
    author = "Elina Syrj{\"a}lahti and Ville Valtavirta and Joonas K{\"a}tt{\"o} and Henri Loukusa and Timo Ikonen and Jaakko Lepp{\"a}nen and Ville Tulkki",
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    Syrjälahti, E, Valtavirta, V, Kättö, J, Loukusa, H, Ikonen, T, Leppänen, J & Tulkki, V 2015, Multiphysics simulations of fast transients in VVER-1000 and VVER-440 reactors. in Proceedings of the 11th International Conference on WWER Fuel Performance, Modeling and Experimental Support. State Scientific and Technical Center for Nuclear and Radiation Safety SSTC NRS, 11th International Conference on WWER Fuel Performance, Modeling and Experimental Support, Varna, Bulgaria, 28/09/15.

    Multiphysics simulations of fast transients in VVER-1000 and VVER-440 reactors. / Syrjälahti, Elina; Valtavirta, Ville; Kättö, Joonas; Loukusa, Henri; Ikonen, Timo; Leppänen, Jaakko; Tulkki, Ville.

    Proceedings of the 11th International Conference on WWER Fuel Performance, Modeling and Experimental Support. State Scientific and Technical Center for Nuclear and Radiation Safety SSTC NRS, 2015.

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

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    AU - Syrjälahti, Elina

    AU - Valtavirta, Ville

    AU - Kättö, Joonas

    AU - Loukusa, Henri

    AU - Ikonen, Timo

    AU - Leppänen, Jaakko

    AU - Tulkki, Ville

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    AB - FINIX is a recently developed fuel behaviour module that is designed to provide "simple but sufficient" descriptions of the most essential fuel behaviour phenomena in multiphysics simulations. In such simulations, it is possible to obtain significant improvement in the feedback to neutronics or thermal hydraulics modelling even with a relatively simple fuel performance model. In this work, FINIX is used as an internal fuel behaviour module both in reactor physics and in reactor dynamics codes to simulate coupled behaviour in fast transient scenarios. With the Monte Carlo reactor physics code Serpent we model a prompt transient in a VVER-1000 pin cell, and with the reactor dynamics code HEXTRAN, a control rod ejection accident in a VVER-440 reactor.

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    Syrjälahti E, Valtavirta V, Kättö J, Loukusa H, Ikonen T, Leppänen J et al. Multiphysics simulations of fast transients in VVER-1000 and VVER-440 reactors. In Proceedings of the 11th International Conference on WWER Fuel Performance, Modeling and Experimental Support. State Scientific and Technical Center for Nuclear and Radiation Safety SSTC NRS. 2015