Search Results - "Toppila, T."

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  1. 1

    Validation of ice condenser model for CFD analysis of VVER-440 type containment by Rämä, T., Toppila, T., Visser, D.C., Siccama, N.B.

    Published in Nuclear engineering and design (01-10-2019)
    “…•An ice condenser model is developed in the ANSYS Fluent CFD code.•The developed ice condenser model is validated against two integral tests.•The CFD model is…”
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    Journal Article
  2. 2

    Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor—Validation of CFD codes by Rohde, U., Höhne, T., Kliem, S., Hemström, B., Scheuerer, M., Toppila, T., Aszodi, A., Boros, I., Farkas, I., Mühlbauer, P., Vyskocil, L., Klepac, J., Remis, J., Dury, T.

    Published in Nuclear engineering and design (01-09-2007)
    “…The EU project FLOMIX-R was aimed at describing the mixing phenomena relevant for both safety analysis, particularly in steam line break and boron dilution…”
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    Journal Article Conference Proceeding
  3. 3

    Fluid mixing and flow distribution in the reactor circuit, measurement data base by Rohde, U., Kliem, S., Höhne, T., Karlsson, R., Hemström, B., Lillington, J., Toppila, T., Elter, J., Bezrukov, Y.

    Published in Nuclear engineering and design (01-02-2005)
    “…Experimental investigations and computational fluid dynamics (CFD) calculations on coolant mixing in pressurised water reactors (PWR) have been performed…”
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    Journal Article
  4. 4

    CFD simulation of Fortum PTS experiment by Toppila, Timo

    Published in Nuclear engineering and design (01-03-2008)
    “…Detailed simulation of the thermal stresses of the reactor pressure vessel (RPV) wall in case of pressurized thermal shock (PTS) requires the simulation of the…”
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    Journal Article
  5. 5
  6. 6

    Validation of fluid-structure interaction simulation environment in analysis of large-break loss of coolant accident by Brandt, T., Lestinen, V., Toppila, T., Kahkonen, J., Timperi, A., Pattikangas, T., Karppinen, I.

    “…In this article, we study a large-break loss of coolant accident (LBLOCA) where a guillotine break of one of the main coolant pipes occurs near the reactor…”
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    Conference Proceeding