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AbstractAbstract
[en] Importance of the reactor pressure vessel for safety of nuclear power plants is great, while the possibilities for ita analysis are very limited. As classical methods of analysis are not adequate for this case, the paper gives a short description, obtained characteristic results, a comparison and criteria of use for two identified and applied methods: the statistical-comparative one and the probabilistic-structural one. (author)
Original Title
Analiza mogucnosti procene pouzdanosti suda nuklearnog reactora
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Source
1983; 8 p; Society for Electronics,Telecommunications, Automation, and Nuclear Engineering; Belgrade (Yugoslavia); ETAN '83 - 27. Conference of the Society for Electronics, Telecommunications, Computers, Automation, and Nuclear Engineering; 27. Konferencija za ETAN; Struga (Yugoslavia); 6-11 Jun 1983; Also available from the Institute of Nuclear Sciences VINCA; 17 refs., 2 figs, 2 tabs.
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