Comprehensive uncertainty and sensitivity analysis for coupled code calculations of VVER plant transients

S. Langenbuch (Corresponding Author), B. Krzykacz-Hausmann, K.-D. Schmidt, G. Hegyi, A. Keresztúri, S. Kliem, J. Hadek, S. Danilin, S. Nikonov, A. Kuchin, V. Khalimanchuk, Anitta Hämäläinen

    Research output: Contribution to journalArticleScientificpeer-review

    18 Citations (Scopus)


    The development of coupled codes, combining thermal-hydraulic system codes and 3D neutron kinetics codes, is an important step to perform best-estimate calculations for plant transients of nuclear power plants. For applications in safety analysis, these coupled codes should be validated by benchmark calculations and, preferably, by comparison with plant transient data from operating plants. In addition, the results should be supplemented by applying uncertainty and sensitivity analysis methods, which allow to identify relevant parameters of models and solution procedures affecting the results and to quantify their relative importance. Both objectives were part of the VALCO project. The aspect of validation is presented in [S. Mittag, et al., 2004. Neutron-Kinetic Code Validation against Measurements in the Moscow V-1000 Zero-Power Facility, in press; T. Vanttola et al., 2004. Validation of coupled codes using VVER plant measurements, in press], the aspect of a comprehensive uncertainty and sensitivity analysis for coupled code calculations is the topic of this contribution. The results and experiences obtained by the analysis for two plant transients in a VVER-440 and a VVER-1000, respectively, are presented and discussed.
    Original languageEnglish
    Pages (from-to)521 - 540
    Number of pages20
    JournalNuclear Engineering and Design
    Issue number2-4
    Publication statusPublished - 2005
    MoE publication typeA1 Journal article-refereed


    • nuclear power plants
    • code validation
    • pressurized water reactors


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