Experimental and analytical studies of the thermal stratification phenomenon in the outlet plenum of fast breeder reactors

Water and sodium experiments were conducted with scaled models to study the in-vessel thermal stratification. The models simulate the outlet plenum in a loop-type LMFBR with an inner barrel and a closed-type UIS (upper instrumentation structure). An examination of the threshold for thermal stratific...

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Bibliographic Details
Published inNuclear engineering and design Vol. 120; no. 2; pp. 403 - 414
Main Authors Ieda, Y., Maekawa, I., Muramatsu, T., Nakanishi, S.
Format Journal Article
LanguageEnglish
Published Amsterdam Elsevier B.V 01.06.1990
Elsevier
Subjects
Applied sciences
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fission nuclear power plants
Installations for energy generation and conversion: thermal and electrical energy
Calculation code
Temperature
Flow rate
Breeder
Small scale
Experimental study
Thermal stratification
Nuclear reactor
Flow regime
Sodium
Test facility
Fast reactor
Numerical simulation
Thermohydraulics
Interface
Reactor core
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Summary:Water and sodium experiments were conducted with scaled models to study the in-vessel thermal stratification. The models simulate the outlet plenum in a loop-type LMFBR with an inner barrel and a closed-type UIS (upper instrumentation structure). An examination of the threshold for thermal stratification, the rising rate of the stratification interface, and the flow regime above the interface has been conducted and is reported in the present paper. In parallel, the phenomenon in the experiments has been evaluated with the multi-dimensional analysis.
ISSN:0029-5493
1872-759X
DOI:10.1016/0029-5493(90)90390-J