Methodology, status and plans for development and assessment of HEXTRAN, TRAB AND APROS

Timo Vanttola, Riitta Kyrki-Rajamäki, Olli Tiihonen, Markku Hänninen, Jaakko Miettinen

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

    Abstract

    A number of transient and accident analysis codes have been developed in Finland during the past twenty years mainly for the needs of their own power plants, but some of the codes have also been utilized elsewhere. The continuous validation, simultaneous development and experiences obtained in commercial applications have considerably improved the performance and range of application of the codes. At present, the methods allow fairly covering accident analysis of the Finnish nuclear power plants.
    Original languageEnglish
    Title of host publicationProceedings of the OECD/CSNI Workshop on Transient Thermal-Hydraulic and Neutronic Codes Requirements
    EditorsD. Ebert
    Place of PublicationWashington, D.C.
    PublisherU.S. Nuclear Regulatory Commission
    Pages129-143
    Publication statusPublished - 1997
    MoE publication typeA4 Article in a conference publication
    EventOECD/CSNI Workshop on Transient Thermal-Hydraulic and Neutronic Codes Requirements - Annapolis, United States
    Duration: 5 Nov 19968 Nov 1996

    Publication series

    SeriesNUREG/CP
    Number0159
    ISSN0270-6482

    Conference

    ConferenceOECD/CSNI Workshop on Transient Thermal-Hydraulic and Neutronic Codes Requirements
    CountryUnited States
    CityAnnapolis
    Period5/11/968/11/96

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    Vanttola, T., Kyrki-Rajamäki, R., Tiihonen, O., Hänninen, M., & Miettinen, J. (1997). Methodology, status and plans for development and assessment of HEXTRAN, TRAB AND APROS. In D. Ebert (Ed.), Proceedings of the OECD/CSNI Workshop on Transient Thermal-Hydraulic and Neutronic Codes Requirements (pp. 129-143). U.S. Nuclear Regulatory Commission. NUREG/CP, No. 0159