Evaluation of reflooding effects on an overheated BWR core in a small steam line break accident using MAAP, MELCOR and SCDAP/RELAP5 computer codes

Ilona Lindholm, Esko Pekkarinen, Heikki Sjövall

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

    Original languageEnglish
    Title of host publicationInternational Conference on New Trends in Nuclear System Thermohydraulics
    Subtitle of host publicationThermohydraulics of Containment and Severe Accidents
    EditorsFrancesco Oriolo, Piero Vigni
    Place of PublicationPisa
    Pages233-243
    Volume2
    Publication statusPublished - 1994
    MoE publication typeA4 Article in a conference publication
    EventInternational Conference on New Trends in Nuclear System Thermohydraulics - Pisa, Italy
    Duration: 30 May 19942 Jun 1994

    Conference

    ConferenceInternational Conference on New Trends in Nuclear System Thermohydraulics
    CountryItaly
    CityPisa
    Period30/05/942/06/94

    Cite this

    Lindholm, I., Pekkarinen, E., & Sjövall, H. (1994). Evaluation of reflooding effects on an overheated BWR core in a small steam line break accident using MAAP, MELCOR and SCDAP/RELAP5 computer codes. In F. Oriolo, & P. Vigni (Eds.), International Conference on New Trends in Nuclear System Thermohydraulics: Thermohydraulics of Containment and Severe Accidents (Vol. 2, pp. 233-243).