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Multiphase Science and Technology
SJR: 0.183 SNIP: 0.483 CiteScore™: 0.5

ISSN Imprimer: 0276-1459
ISSN En ligne: 1943-6181

Multiphase Science and Technology

DOI: 10.1615/MultScienTechn.v25.i2-4.90
pages 237-248

MODEL OF THE COOLING OF A NUCLEAR REACTOR FUEL ROD

David Lavicka
New Technology Research Center (NTC), University of West Bohemia, Univerzitni 8, 306 14 Plzen, Czech Republic
Jiri Polansky
New Technology Research Center (NTC), University of West Bohemia, Univerzitni 8, 306 14 Plzen, Czech Republic

RÉSUMÉ

This paper presents an experimental setup showing some typical phenomena associated with 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. 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 transient heat transfer in two-phase flow.


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