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Konstrukční návrh části zařízení pro studijní účely krize varu / Design concept of the facility part for the educational objectives of the boiling crisis

Graduation these deals with investigation of critical heat flux in pressurized water nuclear reactors. Theoretical part covers fundamental terms from area hydrodynamics of two-phase flow and critical heat flux. Here are also mentioned the individual approaches to description of physical process of heat transfer crisis. Practical part is devoted to systems design of measuring stand for critical heat flux in vertical canal allowing visualization of two-phase flow.

Identiferoai:union.ndltd.org:nusl.cz/oai:invenio.nusl.cz:230091
Date January 2012
CreatorsSuk, Ladislav
ContributorsBaláš, Marek, Martinec, Jiří
PublisherVysoké učení technické v Brně. Fakulta strojního inženýrství
Source SetsCzech ETDs
LanguageCzech
Detected LanguageEnglish
Typeinfo:eu-repo/semantics/masterThesis
Rightsinfo:eu-repo/semantics/restrictedAccess

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