Transient and fuel performance analysis with VTT's coupled code system

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    Abstract

    VTT maintains and further developes a comprehensive safety analysis code system ranging from the basic neutronic libraries to 3D transient analysis and fuel behaviour analysis codes. Some of the computer codes have been developed at VTT, others have been acquired from internationally recognized sources. The code system is based on various types of couplings between the relevant physival phenomena.

    The main tools for analyses of reactor transients are presently the 3D reactor dynamics code HEXTRAN for cores with a hexagonal fuel assembly geometry and TRAB-3D for cores with a quadratic fuel assembly geometry. HEXTRAN has been applied to safety analyses of VVER-type reactors since early 1990’s. TRAB-3D is the latest addition to the code system, and has been applied to BWR and PWR analyses in recent years.

    The results from the 3D analysis can be used as boundary conditions for more detailed fuel rod analysis. For this purpose a general flow model GENFLO, developed at VTT, has been coupled with USNRC’s FRAPTRAN fuel accident behaviour model. FRAPTRAN/GENFLO is quite a promising tool that can handle flow situations that are far too complicated for the models that are usually seen with fuel codes.
    Original languageEnglish
    Title of host publicationMathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications
    PublisherAmerican Nuclear Society ANS
    Number of pages12
    Publication statusPublished - 2005
    MoE publication typeNot Eligible
    EventMathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications Meeting, M&C 2005: 21st biennial topical meeting of the Mathematics and Computation Division of the American Nuclear Society (ANS) - Avignon, France
    Duration: 12 Sep 200515 Sep 2005

    Conference

    ConferenceMathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications Meeting, M&C 2005
    CountryFrance
    CityAvignon
    Period12/09/0515/09/05

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    Cite this

    Daavittila, A., Hämäläinen, A., & Räty, H. (2005). Transient and fuel performance analysis with VTT's coupled code system. In Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications American Nuclear Society ANS. http://www.vtt.fi/inf/julkaisut/muut/2005/091.pdf