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          NRC Library  Document Collections  NUREG-Series Publications  Publications Resulting from International Agreements  Simulation of ROSA-2 Test 3 Counterpart with TRACE5 – Application to Nuclear Power Plant (NUREG/IA-0Simulation of ROSA-2 Test 3 Counterpart with TRACE5 – Application to Nuclear Power Plant(NUREG/IA-0512, Revision 1)

On this page: Publication Information AbstractDownload complete document NUREG/IA-0512, Revision 1 (PDF – 1.51 MB)Publication Information **Manuscript Completed:** April 2018**Date Published:** April 2019 **Prepared by:** S. Gallardo, A. Querol, M. Lorduy, and G. Verdu Universitat Politecnica de Valencia Instituto Universitario de Seguridad Industrial, Radiofisica y Medioambiental Cami de Vera s/n 46022 Valencia, SPAIN 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 Availability Notice Abstract This paper presents a first approach of a hot leg Small Break Loss-Of-Coolant Accident (SBLOCA) application to a Nuclear Power Plant (NPP). For this purpose, a standard 3-loop PWR NPP model by means of the thermal-hydraulic code TRACE5 patch 2 and Symbolic Nuclear Analysis Packages (SNAP) has been used. The SBLOCA transient corresponds to the Test 3 (SB-HL-18) conducted at the Large Scale Test Facility (LSTF) of the Japan Atomic Energy Agency (JAEA) in the frame of the OECD/NEA ROSA-2 Project. LSTF is a Full-Height Full-Pressure (FHFP) facility designed to simulate the Tsuruga unit II NPP (a 4-loop W-type PWR) with volume and power scaled by a factor of 1/48. Test 3 simulates a PWR 1.5% hot leg SBLOCA with an assumption of the total failure of High Pressure Injection (HPI) system under two different pressure conditions. Considering the assumptions of this test, some modifications have been performed in the 3-loop PWR TRACE5 model. The simulation results are provided throughout several graphs where the main system variables, such as primary and secondary pressures, collapsed liquid levels and temperatures are shown. 
      
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