MODEL OF THE COOLING OF A NUCLEAR REACTOR FUEL ROD
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23640%2F13%3A43924247" target="_blank" >RIV/49777513:23640/13:43924247 - isvavai.cz</a>
Result on the web
<a href="http://dx.doi.org/10.1615/MultScienTechn.v25.i2-4.90" target="_blank" >http://dx.doi.org/10.1615/MultScienTechn.v25.i2-4.90</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1615/MultScienTechn.v25.i2-4.90" target="_blank" >10.1615/MultScienTechn.v25.i2-4.90</a>
Alternative languages
Result language
angličtina
Original language name
MODEL OF THE COOLING OF A NUCLEAR REACTOR FUEL ROD
Original language description
The paper presents an experimental setup showing some typical phenomena associated the cooling of a fuel rod inside a nuclear reactor. The fuel rod model allows the general public to observe phenomena related to fluid mechanics and heat transfer. Safetyand operational reasons usually prevent these phenomena from being observed in real-life equipment. The most interesting and important phenomena are "boiling crisis" and transient heat transfer in two-phase flow.
Czech name
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Czech description
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Classification
Type
J<sub>x</sub> - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)
CEP classification
JF - Nuclear energy
OECD FORD branch
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Result continuities
Project
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Continuities
S - Specificky vyzkum na vysokych skolach
Others
Publication year
2013
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Multiphase Science and Technology
ISSN
0276-1459
e-ISSN
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Volume of the periodical
25
Issue of the periodical within the volume
2-4
Country of publishing house
US - UNITED STATES
Number of pages
12
Pages from-to
237-248
UT code for WoS article
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EID of the result in the Scopus database
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