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          NRC Library  Document Collections  NUREG-Series Publications  Publications Resulting from International AgreementsRELAP5 and TRACE Calculations of LOCA in PWR (NUREG/IA-0479)

On this page: Publication Information AbstractDownload complete document NUREG/IA-0479 (PDF – 17.28 MB)Publication Information **Manuscript Completed:** November 2016**Date Published:** June 2017 **Prepared by:** Andrej Prošek Jožef Stefan Institute Jamova cesta 39 Sl-1000 Ljubljana,  Slovenia Kirk Tien, NRC Project Manager Division of Systems Analysis 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 Abstract Availability Notice The accident at the Fukushima Dai-ichi nuclear power plant in 2011 demonstrated that external events could cause loss of all safety systems. In the Europe stress tests were performed and the need was identified to further improve the safety of the existing operating reactors. Therefore the safety upgrade programs were started. The objective of this study was to demonstrate that developed input model of two-loop pressurized water reactor (PWR) for TRACE thermal-hydraulic systems code can be used for independent calculations to be compared with RELAP5 computer code calculations. For demonstration the response of PWR to loss-of-coolant accident (LOCA) break spectrum from 10.16 cm (4 inch) to 30.48 cm (12 inch) was simulated. Only passive accumulators were assumed available. For calculations the latest TRACE Version 5.0 Patch 4 and RELAP5/MOD3.3 Patch 4 using both break flow models were used. The results showed that RELAP5 calculations using different break flow models are rather similar, therefore also other parameters are similar. The accumulators discharge was faster in TRACE calculation than in RELAP5 calculations. It can be concluded that different accumulator discharge influencing the break flow seems to be the largest contributor to the differences in the results between RELAP5 and TRACE. 
      
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