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Author Riikonen, V. ♦ Puustinen, M. ♦ Kouhia, J.
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 ♦ MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS ♦ LOSS OF COOLANT ♦ R CODES ♦ A CODES ♦ PWR TYPE REACTORS ♦ COMPUTER CODES ♦ FLOW RATE ♦ SIMULATION ♦ TWO-PHASE FLOW ♦ STEAM GENERATORS
Abstract A cold-leg small-break loss-of-coolant accident (SBLOCA) experiment was performed on the PACTEL facility to study the behavior of natural circulation in a VVER-440 reactor geometry. The facility is a volumetrically scaled (1:305) integral test loop simulating the VVER-440 reactors used in Finland. The test results were used to assess the computer codes RELAP5/MOD3.1 and APROS 3.0 for VVER reactors. The behavior of the horizontal steam generator and the effect of the hot-leg loop seal were of particular interest. The specific parameters to be compared included the primary pressure and the downcomer mass flow rate.
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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