Analysis of PANDA Experiments P3 and P6 Using RELAP5/MOD3.2 (NUREG/IA-0196)
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Date Published: January 2001
L. Batet, E Reventós
Department of Physics and Nuclear Engineering
University Politecnica de Cataluna
Prepared as part of:
The Agreement on Research Participation and Technical Exchange
under the International Code Application and Maintenance Program (CAMP)
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
Between 1996 and 1998 Technical University of Catalonia (UPC) has been participating in the "Technology Enhancement for Passive Safety Systems" (TEPSS) project, in the Fourth Framework Program of the Commission of the European Communities.
One of the purposes of TEPSS has been the study of the residual heat removal by passive means after a loss of coolant accident into a simplified boiling water reactor (ESBWR) type containment. To that end, eight experiments have been performed in PANDA experimental facility of Paul Scherrer Institute in Villigen (Switzerland). PANDA represent a ESBWR scaled 1:1 in elevation and 1:40 in volume.
UPC has supplied analytical support of PANDA tests P3 and P6, using RELAP5/Mod3.2. P3 and P6 simulate Main Steam Line Break scenarios with different initial conditions and different passive safety systems available.
This report shows the results obtained in the simulation of those experiments. Discrepancies between calculated and measured parameters are identified and discussed.