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


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
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


Conference3rd Annual Scientific Conference of the Nuclear Society International
CountryRussian Federation
CitySt. Petersburg

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