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          NRC Library  Document Collections  NUREG-Series Publications  Publications Resulting from International AgreementsPost-Test Calculation of the ROSA/LSTF Test 3-1 using RELAP5/mod3.3 (NUREG/IA-0409)

On this page: Publication Information AbstractDownload complete document NUREG/IA-0409 (PDF - 1.23 MB)Publication Information **Manuscript Completed:** January 2012**Date Published:** March 2012 **Prepared by:** V. Martinez, F. Reventós, C. Pretel Institute of Energy Technologies Technical University of Catalonia ETSEIB, Av. Diagonal 647, Pav. C 08028 Barcelona, SPAIN A. Calvo, NRC Project Manager Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 **Prepared as part of:** The Agreement on Research Participation and Technical Exchange Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP) **Published by:** U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Availability Notice Abstract The Thermalhydraulic Studies Group of Technical University of Catalonia (UPC) holds a large background in nuclear safety studies in the field of Nuclear Power Plant (NPP) code simulators. RELAP5mod3.3 has been used in this study in order to analyze the LSTF Test 3-1, which simulates an anticipated transient without scram (ATWS) as a result of a small break LOCA without rods insertion (but with scram signal) and loss of off-site power. Two local phenomena have been object of study: U-tube liquid accumulation due to CCFL at the inlet of the SG Utubes, and loop seal behavior during the transient. 
      
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