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Experiments critical heat flux

By Petr Štaffa

Abstract

The Bachelor’s thesis deals with phenomenon of critical heat flux in a core of nuclear reactor. The first part is dedicated to describe physical nature of critical heat flux and basic thermo mechanical and hydrodynamics terms. The second part is dedicated to summarize experimental investigations on critical heat flux and their process

Topics: dvoufázové proudění; heat transfer; Critical heat flux; přenos tepla; two-phase flow; krize varu; the boiling crisis; Kritický tepelný tok
Publisher: Vysoké učení technické v Brně. Fakulta strojního inženýrství
Year: 2014
OAI identifier: oai:invenio.nusl.cz:214402
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