Model of cooling fuel rod in the nuclear reactor
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23210%2F10%3A00503635" target="_blank" >RIV/49777513:23210/10:00503635 - isvavai.cz</a>
Alternative codes found
RIV/49777513:23640/10:00503635
Result on the web
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DOI - Digital Object Identifier
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Alternative languages
Result language
angličtina
Original language name
Model of cooling fuel rod in the nuclear reactor
Original language description
The paper presents the erected experimental apparatus ?Model of fuel rod cooling inside a nuclear reactor?. The fuel rod model allows the general public to observe phenomena of fluid mechanics and thermomechanics. Safety and operational reasons usually prevent these phenomena from being observed in real-life equipment. The most interesting and important phenomena are ?boiling crisis? and related nonstationary heat transfer in multi-phase flow.
Czech name
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Czech description
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Classification
Type
O - Miscellaneous
CEP classification
BJ - Thermodynamics
OECD FORD branch
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Result continuities
Project
<a href="/en/project/GP101%2F09%2FP056" target="_blank" >GP101/09/P056: Experimental and teoretical research unsteady heat transfer by the multiphase flow</a><br>
Continuities
S - Specificky vyzkum na vysokych skolach
Others
Publication year
2010
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů