Assessment of TRACE 5.0 Against ROSA Test 3-2, High Power Natural Circulation (NUREG/IA-0412)
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Manuscript Completed: March 2012
Date Published: March 2012
S. Gallardo, V. Abella, G. Verdú and A. Querol
Universitat Politécnica de Valéncia
Camino Vera s/n
46022 Valencia, SPAIN
A. Calvo, NRC Project Manager
Prepared as part of:
The Agreement on Research Participation and Technical Exchange
Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
The purpose of this work is to provide an overview of the results obtained in the simulation of a pressurized water reactor (PWR) high-power natural circulation due to failure of scram following a Loss-Of-Feed Water (LOFW) transient under the assumption of total failure of High Pressure Injection System (HPIS), but actuation of Auxiliary Feed Water (AFW).
Simulation of the experiment conducted in the Large Scale Test Facility (LSTF) is performed via the thermal-hydraulic code TRACE5. This work is developed in the frame of OECD/NEA ROSA Project Test 3-2 (TR-LF-13 in JAEA). AFW was actuated when the steam generator (SG) secondary-side collapsed liquid level decreased to a determined value, providing a continuous primary-to-secondary heat removal. The primary and secondary pressures were maintained almost constant by cycle opening of pressurizer Power-Operated Relief Valve (PORV) and SG relief valves till the end of the test.
A detailed model has been developed with TRACE5 following these assumptions. Results of the simulation are compared with the experimental in several graphs, observing an acceptable general behaviour in the entire transient. In conclusion, this work represents a good contribution for assessment of the predictability of thermalhydraulic computer codes such as TRACE5.