Validation of the APROS thermal-hydraulics against the PACTEL test facility

Herkko Plitt, Kari Porkholm, Markku Hänninen

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

    Abstract

    APROS - Advanced PROcess Simulator - has been developed since 1986 together with the Technical Research Centre of Finland (VTT) and IVO Power Engineering Ltd (IVO PE) for process and automation design, safety analysis and training simulator applications. Up to now the APROS development has required more than 150 man years. APROS applications include nuclear and fossil power plant models, but also chemical as well as pulp and paper processes can be modeled. PACTEL - PArallel Channel TEst Loop - is an experimental integral test facility for VVER-440 nuclear power plants. VVER nuclear power plants have some special features like hexagonal fuel assemblies and horizontal steam generators. Therefore PACTEL experiments provide for VVER-purposes unique information which can not be obtained with normal PWR integral test facilities. PACTEL experiments are also very important for computer codes, like APROS, for VVER validation.
    Original languageEnglish
    Title of host publication8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8)
    Subtitle of host publicationNew horizons in nuclear reactor thermal-hydraulics
    Place of PublicationTokyo
    PublisherAtomic Energy Society of Japan
    Pages1187-1194
    Publication statusPublished - 1997
    MoE publication typeB3 Non-refereed article in conference proceedings
    Event8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics - Kyoto, Japan
    Duration: 30 Sep 19974 Oct 1997

    Publication series

    SeriesNUREG/CP
    Number0142
    ISSN0270-6482

    Conference

    Conference8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics
    CountryJapan
    CityKyoto
    Period30/09/974/10/97

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