Validation of the STEG Code using Experiments on Two-Phase Flow Across an In-Line Tube Bundle
Author:
Affiliation:
1. National Research University “MPEI”,Department of Nuclear Power Plants,Moscow,Russian Federation
Publisher
IEEE
Link
http://xplorestaging.ieee.org/ielx7/9731097/9731358/09731366.pdf?arnumber=9731366
Reference16 articles.
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2. Interfacial friction correlations for the two-phase flow across tube bundle
3. A theoretical basis for the Lockhart-Martinelli correlation for two-phase flow
4. Proposed Correlation of Data for Isothermal Two-Phase, Two-Component Flow in Pipes;lockhart;Chem Eng Prog,1949
5. Investigation of steam-water hydrodynamics in immersed heating surfaces for improvement of steam generators of NPP with VVER;kolbasnikov;Power Technol Eng,1991
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