Validation of coupled codes for VVERs by analysis of plant transients

R. Mittag, S. Kliem, F.P. Weiss, Riitta Kyrki-Rajamäki, Anitta Hämäläinen, S. Langenbuch, S. Danilin, J. Hadek, G. Hegyi, A. Kuchin, D. Panayotov

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsProfessional

    Original languageEnglish
    Title of host publicationAdvanced Thermal-hydraulic and Neutronic Codes: Current and Future Applications
    Subtitle of host publicationWorkshop Proceedings
    PublisherOECD NEA Nuclear Energy Agency
    Pages309-324
    Publication statusPublished - 2001
    MoE publication typeD3 Professional conference proceedings
    EventOECD/CSNI Workshop on Advanced Thermal-Hydraulic and Neutronic Codes: Current and Future Applications - Barcelona, Spain
    Duration: 10 Apr 200013 Apr 2000

    Publication series

    SeriesNEA Committee on the Safety of Nuclear Installations. Report
    NumberNEA/CSNI/R(2001)2/VOL1

    Workshop

    WorkshopOECD/CSNI Workshop on Advanced Thermal-Hydraulic and Neutronic Codes
    CountrySpain
    CityBarcelona
    Period10/04/0013/04/00

    Cite this

    Mittag, R., Kliem, S., Weiss, F. P., Kyrki-Rajamäki, R., Hämäläinen, A., Langenbuch, S., Danilin, S., Hadek, J., Hegyi, G., Kuchin, A., & Panayotov, D. (2001). Validation of coupled codes for VVERs by analysis of plant transients. In Advanced Thermal-hydraulic and Neutronic Codes: Current and Future Applications: Workshop Proceedings (pp. 309-324). OECD NEA Nuclear Energy Agency. NEA Committee on the Safety of Nuclear Installations. Report, No. NEA/CSNI/R(2001)2/VOL1 https://www.oecd-nea.org/nsd/docs/2001/csni-r2001-2-vol1.pdf