The European project FLOMIX-R: Fluid mixing and flow distribution inthe reactor circuit - Final summary report

Autor: Hemström, B., Mühlbauer, P., Lycklama a. Nijeholt, J.-A., Farkas, I., Boros, I., Aszodi, A., Scheuerer, M., Dury, T., Rohde, U., Höhne, T., Kliem, S., Vyskocil, L., Toppila, T., Klepac, J., Remis, J.

Publikováno v: Wissenschaftlich-Technische Berichte / Forschungszentrum Rossendorf; FZR-432 2005

The project was aimed at describing the mixing phenomena relevant for both safety analysis, particularly in steam line break and boron dilution scenarios, and mixing phenomena of interest for economical operation and the structural integrity. Measure

Externí odkaz: https://hzdr.qucosa.de/id/qucosa%3A21688
https://hzdr.qucosa.de/api/qucosa%3A21688/attachment/ATT-0/

CFD simulation of the Vattenfall 1/5th-scale PWR model for boron dilution studies

Autor: Dury, T.V., Hemström, B., Shepel, S.V.

Publikováno v: In Nuclear Engineering and Design 2008 238(3):577-589

Fluid mixing and flow distribution in the reactor circuit, measurement data base

Autor: Rohde, U. ^*, Kliem, S., Höhne, T., Karlsson, R., Hemström, B., Lillington, J., Toppila, T., Elter, J., Bezrukov, Y.

Publikováno v: In Nuclear Engineering and Design 2005 235(2):421-443

Fluid mixing and flow distribution ín a primary circuit of a nuclear pressurized water reactor – Validation of CFD codes

Autor: Rohde, U., Höhne, T., Kliem, S., Hemström, B., Scheuerer, M., Toppila, T., Aszodi, A., Boros, I., Farkas, I., Muehlbauer, P., Vyskocil, V., Klepac, J., Remis, J., Dury, T.

Publikováno v: Nuclear Engineering and Design 237(2007)15-17, 1639-1655

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 scenarios, and mixing phenomena of interest for economical operation and the structural integr

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=od______4577::9e6d8ab53fd3e427463e76f5e31ca0bb
https://www.hzdr.de/publications/Publ-8606-1

Measurement data base on fluid mixing and flow distribution in the reactor circuit

Autor: Rohde, U., Kliem, S., Höhne, T., Prasser, H.-M., Hemström, B., Toppila, T., Elter, J., Bezrukov, Y., Scheuerer, M.

Publikováno v: The 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11), 02.-06.10.2005, Avignon, France
11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 02.-06.10.2005, Avignon, France, 2-9516195-0-2

Experimental investigations on coolant mixing in Pressurised Water Reactors (PWR) have been performed within the EC project FLOMIX-R. The project was aimed at describing the mixing phenomena relevant for both safety analysis, particularly in steam li

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::1447062e00a1eb51a292850712d69985
https://www.hzdr.de/publications/Publ-7261-1