Validation of coupled codes using VVER plant measurements

Timo Vanttola (Corresponding Author), Anitta Hämäläinen, S. Kliem, Y. Kozmenkov, F.-P. Weiss, A. Keresztúri, J. Hádek, C. Strmensky, S. Stefanova, A. Kuchin, P. Hlbocky, D. Siko, S. Danilin

    Research output: Contribution to journalArticleScientificpeer-review

    25 Citations (Scopus)


    A data set of five transients at different VVER type nuclear power plants was collected in order to validate neutron kinetics/thermal hydraulics codes. Two of these transients ‘drop of control rod at nominal power at Bohunice-3’ of VVER-440 type and ‘coast-down of 1 from 3 working MCPs at Kozloduy-6’ of VVER-1000 type, were then utilised for code validation. Eight institutes contributed to the validation with 10 calculations using 5 different combinations of coupled codes. The thermal hydraulic codes were ATHLET, SMABRE and RELAP5 and the neutron kinetic codes DYN3D, HEXTRAN, KIKO3D and BIPR8. The general behaviour of both the transients was quite well calculated with all the codes. Even an elementary modelling of coolant mixing in reactor pressure vessel under asymmetric transients improved correspondence to the measurements. Some differences between the calculations seem to indicate that fuel modelling and treatment of VVER-440 control rods need further consideration. The simultaneous validation interacted with the data collection effort and thus improved its quality. The complexity of data collection systems and sometimes conflicting data, however, called for compromises and interpretation guides that also taught the analysts balanced plant modelling.
    Original languageEnglish
    Pages (from-to)507 - 519
    Number of pages13
    JournalNuclear Engineering and Design
    Issue number2-4
    Publication statusPublished - 2005
    MoE publication typeA1 Journal article-refereed


    • nuclear power plants
    • nuclear reactor safety
    • nuclear safety
    • validation
    • code validation
    • pressurized water reactors


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