|Author||Riikonen, V. ♦ Puustinen, M. ♦ Kouhia, J.|
|Source||United States Department of Energy Office of Scientific and Technical Information|
|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.|
|Learning Resource Type||Article|
|Publisher Place||United States|
|Journal||Transactions of the American Nuclear Society|
|Technical Publication No.||CONF-951006-|
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