Physics and chemistry of nuclear fuels (PANCHO)

    Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

    Abstract

    PANCHO has been the essential platform for the ongoing development of FINIX fuel behaviour module and its accompanying automatic validation system. FINIX has been published through the OECD/NEA Data Bank, and has been licensed by several institutions around the world. The studies on fuel behaviour in accident conditions have been framed within the international projects, where the accident simulation codes have been tested and validated. A coupling between SCANAIR and GENFLO codes has been developed in the project.
    The chemical experiments on nuclear fuel materials aimed to investigate characteristics of initial dissolution of crystalline ThO2 by adding 229Th tracer into the aqueous phase, and were conducted for total 534 days. The experimental campaign on cladding creep demonstrated that the VTT equipment is capable of performing suitable transient tests which support modelling efforts.
    Three DSc theses were finalized based on the ongoing cladding creep modelling work, the modelling of fuel behavior in design basis accidents and fuel pellet dissolution experiments. One Master’s thesis is to be finalized from the work performed in this project.
    Original languageEnglish
    Title of host publicationSAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018
    Subtitle of host publicationFinal Report
    EditorsJari Hämäläinen, Vesa Suolanen
    PublisherVTT Technical Research Centre of Finland
    Pages252-268
    ISBN (Electronic)978-951-38-8682-0
    Publication statusPublished - 2019
    MoE publication typeD2 Article in professional manuals or guides or professional information systems or text book material

    Publication series

    SeriesVTT Technology
    Number349
    ISSN2242-1211

    Fingerprint

    Nuclear fuels
    Accidents
    Physics
    Creep
    Dissolution
    Experiments
    Crystalline materials

    Cite this

    Arkoma, A., Heikinheimo, J., Ikonen, T., Kättö, J., Loukusa, H., Myllykylä, E., ... Valtavirta, V. (2019). Physics and chemistry of nuclear fuels (PANCHO). In J. Hämäläinen, & V. Suolanen (Eds.), SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Final Report (pp. 252-268). VTT Technical Research Centre of Finland. VTT Technology, No. 349
    Arkoma, Asko ; Heikinheimo, Janne ; Ikonen, Timo ; Kättö, Joonas ; Loukusa, Henri ; Myllykylä, Emmi ; Peltonen, Jussi ; Pohja, Rami ; Tulkki, Ville ; Valtavirta, Ville. / Physics and chemistry of nuclear fuels (PANCHO). SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Final Report. editor / Jari Hämäläinen ; Vesa Suolanen. VTT Technical Research Centre of Finland, 2019. pp. 252-268 (VTT Technology; No. 349).
    @inbook{67359735ac2744d8945710b02fd27363,
    title = "Physics and chemistry of nuclear fuels (PANCHO)",
    abstract = "PANCHO has been the essential platform for the ongoing development of FINIX fuel behaviour module and its accompanying automatic validation system. FINIX has been published through the OECD/NEA Data Bank, and has been licensed by several institutions around the world. The studies on fuel behaviour in accident conditions have been framed within the international projects, where the accident simulation codes have been tested and validated. A coupling between SCANAIR and GENFLO codes has been developed in the project.The chemical experiments on nuclear fuel materials aimed to investigate characteristics of initial dissolution of crystalline ThO2 by adding 229Th tracer into the aqueous phase, and were conducted for total 534 days. The experimental campaign on cladding creep demonstrated that the VTT equipment is capable of performing suitable transient tests which support modelling efforts.Three DSc theses were finalized based on the ongoing cladding creep modelling work, the modelling of fuel behavior in design basis accidents and fuel pellet dissolution experiments. One Master’s thesis is to be finalized from the work performed in this project.",
    author = "Asko Arkoma and Janne Heikinheimo and Timo Ikonen and Joonas K{\"a}tt{\"o} and Henri Loukusa and Emmi Myllykyl{\"a} and Jussi Peltonen and Rami Pohja and Ville Tulkki and Ville Valtavirta",
    year = "2019",
    language = "English",
    series = "VTT Technology",
    publisher = "VTT Technical Research Centre of Finland",
    number = "349",
    pages = "252--268",
    editor = "Jari H{\"a}m{\"a}l{\"a}inen and Vesa Suolanen",
    booktitle = "SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018",
    address = "Finland",

    }

    Arkoma, A, Heikinheimo, J, Ikonen, T, Kättö, J, Loukusa, H, Myllykylä, E, Peltonen, J, Pohja, R, Tulkki, V & Valtavirta, V 2019, Physics and chemistry of nuclear fuels (PANCHO). in J Hämäläinen & V Suolanen (eds), SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Final Report. VTT Technical Research Centre of Finland, VTT Technology, no. 349, pp. 252-268.

    Physics and chemistry of nuclear fuels (PANCHO). / Arkoma, Asko; Heikinheimo, Janne; Ikonen, Timo; Kättö, Joonas; Loukusa, Henri; Myllykylä, Emmi; Peltonen, Jussi; Pohja, Rami; Tulkki, Ville; Valtavirta, Ville.

    SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Final Report. ed. / Jari Hämäläinen; Vesa Suolanen. VTT Technical Research Centre of Finland, 2019. p. 252-268 (VTT Technology; No. 349).

    Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

    TY - CHAP

    T1 - Physics and chemistry of nuclear fuels (PANCHO)

    AU - Arkoma, Asko

    AU - Heikinheimo, Janne

    AU - Ikonen, Timo

    AU - Kättö, Joonas

    AU - Loukusa, Henri

    AU - Myllykylä, Emmi

    AU - Peltonen, Jussi

    AU - Pohja, Rami

    AU - Tulkki, Ville

    AU - Valtavirta, Ville

    PY - 2019

    Y1 - 2019

    N2 - PANCHO has been the essential platform for the ongoing development of FINIX fuel behaviour module and its accompanying automatic validation system. FINIX has been published through the OECD/NEA Data Bank, and has been licensed by several institutions around the world. The studies on fuel behaviour in accident conditions have been framed within the international projects, where the accident simulation codes have been tested and validated. A coupling between SCANAIR and GENFLO codes has been developed in the project.The chemical experiments on nuclear fuel materials aimed to investigate characteristics of initial dissolution of crystalline ThO2 by adding 229Th tracer into the aqueous phase, and were conducted for total 534 days. The experimental campaign on cladding creep demonstrated that the VTT equipment is capable of performing suitable transient tests which support modelling efforts.Three DSc theses were finalized based on the ongoing cladding creep modelling work, the modelling of fuel behavior in design basis accidents and fuel pellet dissolution experiments. One Master’s thesis is to be finalized from the work performed in this project.

    AB - PANCHO has been the essential platform for the ongoing development of FINIX fuel behaviour module and its accompanying automatic validation system. FINIX has been published through the OECD/NEA Data Bank, and has been licensed by several institutions around the world. The studies on fuel behaviour in accident conditions have been framed within the international projects, where the accident simulation codes have been tested and validated. A coupling between SCANAIR and GENFLO codes has been developed in the project.The chemical experiments on nuclear fuel materials aimed to investigate characteristics of initial dissolution of crystalline ThO2 by adding 229Th tracer into the aqueous phase, and were conducted for total 534 days. The experimental campaign on cladding creep demonstrated that the VTT equipment is capable of performing suitable transient tests which support modelling efforts.Three DSc theses were finalized based on the ongoing cladding creep modelling work, the modelling of fuel behavior in design basis accidents and fuel pellet dissolution experiments. One Master’s thesis is to be finalized from the work performed in this project.

    M3 - Chapter or book article

    T3 - VTT Technology

    SP - 252

    EP - 268

    BT - SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018

    A2 - Hämäläinen, Jari

    A2 - Suolanen, Vesa

    PB - VTT Technical Research Centre of Finland

    ER -

    Arkoma A, Heikinheimo J, Ikonen T, Kättö J, Loukusa H, Myllykylä E et al. Physics and chemistry of nuclear fuels (PANCHO). In Hämäläinen J, Suolanen V, editors, SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Final Report. VTT Technical Research Centre of Finland. 2019. p. 252-268. (VTT Technology; No. 349).