Analysis of a small break loss-of-coolant accident of pressurized water reactor by APROS

A. Al-Falahi, Markku Hänninen, Kari Porkholm

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

    Abstract

    The purpose of this paper is to study the capability of APROS (Advanced PROcess Simulator) code to simulate the real plant thermal-hydraulic transient of a Small Break Loss-Of-Coolant Accident (SBLOCA) of Loss-Of-Fluid Test (LOFT) facility. The LOFT is a scaled model of a Pressurized Water Reactor (PWR). This work is a part of a larger validation of the APROS thermal-hydraulic models. The results of SBLOCA transient calculated by APROS showed a reasonable agreement with the measured data.
    Original languageEnglish
    Title of host publicationProceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7
    Place of PublicationWashington, D.C.
    PublisherU.S. Nuclear Regulatory Commission
    Pages2263-2279
    Volume3
    Publication statusPublished - 1995
    MoE publication typeA4 Article in a conference publication
    Event7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7 - Saratoga Springs, United States
    Duration: 10 Sep 199515 Sep 1995

    Publication series

    SeriesNUREG/CP
    Number0142
    ISSN0270-6482

    Conference

    Conference7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7
    CountryUnited States
    CitySaratoga Springs
    Period10/09/9515/09/95

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  • Cite this

    Al-Falahi, A., Hänninen, M., & Porkholm, K. (1995). Analysis of a small break loss-of-coolant accident of pressurized water reactor by APROS. In Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7 (Vol. 3, pp. 2263-2279). U.S. Nuclear Regulatory Commission. NUREG/CP, No. 0142