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Author Banerjee, S. S. ♦ Hassan, Y. A.
Source United States Department of Energy Office of Scientific and Technical Information
Content type Text
Language English
Subject Keyword NUCLEAR REACTOR TECHNOLOGY ♦ NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS ♦ WATER COOLED REACTORS ♦ R CODES ♦ HYDRAULICS ♦ COOLING SYSTEMS ♦ HEAT TRANSFER ♦ CONTAINMENT ♦ REACTOR SAFETY
Abstract Degradation of the condensation heat transfer coefficient in the presence of noncondensable gases was studied using the RELAP5/MOD3 thermal-hydraulic code. The purpose was to evaluate the condensation model in the code. This will help in the analysis of the various passive containment cooling systems for the next generation of nuclear reactors. The experiment chosen for this study was the Hitachi steam condensation experiment.
ISSN 0003018X
Educational Use Research
Learning Resource Type Article
Publisher Date 1995-12-31
Publisher Place United States
Journal Transactions of the American Nuclear Society
Volume Number 73
Technical Publication No. CONF-951006-


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