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AbstractAbstract
[en] The two-phase flow model in the RELAP4 thermal-hydraulic computer program has been compared with steady-state, boiling two-phase flow experimental data. The experimental data were obtained for steady, vertical upflow of water in heated round tubes and annuli. The calculated results show good agreement with the experimental data, and the RELAP4 numerical scheme rapidly attained a very stable steady-state condition. All aspects of the RELAP4 model equations have been specialized to cover the two-phase flows of interest
Primary Subject
Source
Anon; p. 529-548; 1977; p. 529-548; American Nuclear Society; La Grange Park, IL; Thermal reactor safety meeting; Sun Valley, ID, USA; 31 Jul - 5 Aug 1977
Record Type
Book
Literature Type
Conference
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