Original title: Návrh programu pro výpočet výkonu a průtoku aktivní zónou z parametrů sekundárního okruhu pro JE s reaktorem VVER 440
Translated title: Evaluation of power and coolant flow in reactor core
Authors: Tvrdý, Miloslav ; Šen, Hugo (referee) ; Nerud, Pavel (advisor)
Document type: Master’s theses
Year: 2010
Language: cze
Publisher: Vysoké učení technické v Brně. Fakulta strojního inženýrství
Abstract: [cze] [eng]

Keywords: Coolant flow in reactor core; nuclear energy; nuclear power plant; power of reactor; Visual Basic for Applications (VBA); VVER 440.; Jaderná elektrárna; jaderná energetika; průtok aktivní zónou; Visual Basic for Applications (VBA); VVER 440; výkon reaktoru.

Institution: Brno University of Technology (web)
Document availability information: Fulltext is available in the Brno University of Technology Digital Library.
Original record: http://hdl.handle.net/11012/13502

Permalink: http://www.nusl.cz/ntk/nusl-228896


The record appears in these collections:
Universities and colleges > Public universities > Brno University of Technology
Academic theses (ETDs) > Master’s theses
 Record created 2016-06-03, last modified 2022-09-04


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