ATWS analyses for VVER-91 concept by the SMATRA code

Riitta Kyrki-Rajamäki, Jaakko Miettinen, Hanna Räty, Timo Vanttola, Pertti Siltanen, Nikolai Fil

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

    Abstract

    This year, 7 different offers have been handed in for the fifth nuclear power unit of Finland. One of them is the VVER-91 plant concept of VVO Atomenergoexport (AEE). In cooperation with IVO International planning work has been made in order to fulfil the strict safety criteria of the Finnish authorities. Part of the accident analyses have been made by the Technical Research Centre of Finland (VTT). In Finland there is experience of the VVER type reactors. There are two VVER-440 reactors in Loviisa. A group of analyses made in VTT includes cases that belong to the class of Anticipated Transient Without Scram (ATWS). In this paper, methods and results of some loss of feedwater ATWS analyses are discussed.
    Original languageEnglish
    Title of host publication3rd Annual Nuclear Society International (NSI) meeting
    Subtitle of host publicationNuclear technology tomorrow
    EditorsYu.A. Prokhorov, Anatoli S. Krivokhatski, Sergei V. Kryukov, R.M. Aleksakhin
    Place of PublicationMoscow
    Pages203-207
    Publication statusPublished - 1992
    MoE publication typeA4 Article in a conference publication
    Event3rd Annual Scientific Conference of the Nuclear Society International - St. Petersburg, Russian Federation
    Duration: 14 Sep 199218 Sep 1992

    Publication series

    SeriesTransactions of the American Nuclear Society
    NumberSuppl. 1
    Volume67
    ISSN0003-018X

    Conference

    Conference3rd Annual Scientific Conference of the Nuclear Society International
    CountryRussian Federation
    CitySt. Petersburg
    Period14/09/9218/09/92

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