Kraken: An upcoming Finnish reactor analysis framework

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

    Abstract

    This article gives an overview of the development plans and goals for the upcoming Finnish reactor analysis framework Kraken, developed at VTT Technical Research Centre of Finland Ltd. We describe the motivation behind this new code development project, the currently available in-house solver modules used in the framework as well as the coupling approach used for multi-physics simulations. After touching briefly on the development goals, we offer a simple demonstration of a multi-physics problem solved using either continuous energy Monte Carlo neutronics or nodal diffusion neutronics, while keeping
    the modules providing thermal hydraulic and fuel behavior feedback same in each case. In the demonstration case, we show how the continuous energy neutron transport solution can serve as an initial computational verification for the reduced order neutronics and how some of the sources of discrepancy between the two can be identified.
    Original languageEnglish
    Title of host publicationInternational Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019
    PublisherAmerican Nuclear Society (ANS)
    Pages786-795
    Number of pages10
    ISBN (Electronic)978-0-89448-769-9
    Publication statusPublished - 2019
    MoE publication typeA4 Article in a conference publication
    EventInternational Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering - Portland, United States
    Duration: 25 Aug 201929 Aug 2019

    Conference

    ConferenceInternational Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering
    CountryUnited States
    CityPortland
    Period25/08/1929/08/19

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