FINIX: Fuel behavior model and interface for multiphysics applications

Timo Ikonen, Ville Tulkki, Elina Syrjälahti, Ville Valtavirta, Jaakko Leppänen

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

    9 Citations (Scopus)

    Abstract

    In this paper, we present a novel, lightweight fuel behavior code, FINIX. FINIX provides an advanced description of the nuclear fuel rod for non-fuel-specific codes, such as reactor physics, thermal hydraulics and system codes, allowing realistic modeling of the thermal and mechanical behavior of the fuel during transients. FINIX can be implemented within the main code on a source code level, and includes a high-level interface for accessing the fuel behavior model with minimal knowledge of its internal implementation. The interface also reduces the need for modifying the main code even when the internal FINIX models are significantly updated, allowing simultaneous code development and integration. In addition to FINIX, we are developing a method for initializing the model for accumulated burn-up. The basis of the method is described in this paper. We also present initial results calculated both with the stand-alone version of FINIX, and as an integrated part of the Monte Carlo reactor physics code Serpent
    Original languageEnglish
    Title of host publicationProceedings of LWR Fuel Performance Meeting TopFuel 2013
    PublisherAmerican Nuclear Society (ANS)
    Pages726-733
    ISBN (Print)978-0-89448-701-9
    Publication statusPublished - 2013
    MoE publication typeA4 Article in a conference publication
    EventLWR Fuel Performance Meeting, Top Fuel 2013 - Charlotte, NC, United States
    Duration: 15 Sept 201319 Sept 2013

    Conference

    ConferenceLWR Fuel Performance Meeting, Top Fuel 2013
    Country/TerritoryUnited States
    CityCharlotte, NC
    Period15/09/1319/09/13

    Keywords

    • FINIX
    • fuel behaviour modelling
    • multiphysics
    • nuclear fuel

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