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Borek-Kruszewska, E.; Bykowski, W.
Institute of Atomic Energy, Otwock-Swierk (Poland)2003
Institute of Atomic Energy, Otwock-Swierk (Poland)2003
AbstractAbstract
[en] The results of experimental research aimed to determine the maximum admissible thermal load on the inner surface of the compensation rod, flow conditions, recording the thermal-hydraulic parameters and visualization of the occurring phenomena which have been accomplished in the water test facility WIW-300, are presented in the paper. The flow parameters preceding the CHF occurrence in a vertical channel of annular geometry with 23/20 mm O/I diameters and of 1000 mm length under transient conditions were analysed. Based on the experimental investigations it was obtained an empirical correlation for the DNB and CHF occurrence in down-flow forced convection in uniformly heated tube depend on initial flow parameters. (author)
Original Title
Eksperymentalne badanie parametrow procesu wrzenia w kanalach rownoleglych w warunkach przeplywu przejsciowego
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Secondary Subject
Source
2003; 43 p; ISSN 1232-5317;
; 14 refs., 22 figs., 3 tabs.

Record Type
Report
Report Number
Country of publication
BERYLLIUM MODERATED REACTORS, BOILING, COMPUTER CODES, CONVECTION, ENERGY TRANSFER, ENRICHED URANIUM REACTORS, FLUID MECHANICS, HEAT FLUX, HEAT TRANSFER, HYDRAULICS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, MASS TRANSFER, MECHANICS, METAL MODERATED REACTORS, NUCLEATE BOILING, PHASE TRANSFORMATIONS, POOL TYPE REACTORS, REACTIVITY COEFFICIENTS, REACTORS, RESEARCH AND TEST REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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