Assessment of TRACE 5.0 Against ROSA Test 6-2, Vessel Lower Plenum SBLOCA (NUREG/IA-0244)
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Publication Information
Date Published: February 2011
Prepared by:
S. Gallardo, V. Abella, G. Verdú
Universidad Politécnica de Valencia
ETSII
Camί de Vera s/n
46021 Valencia, 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
Availability Notice
Abstract
The purpose of this work is to provide an overview of the results obtained in the simulation of a pressure vessel lower plenum Small Break Loss-Of-Coolant Accident (SBLOCA) under the assumption of total failure of High Pressure Injection System (HPIS) in the Large Scale Test Facility (LSTF) via the thermal-hydraulic code TRACE5.
The work is developed in the frame of OECD/NEA ROSA Project Test 6-2 (SB-PV-10 in JAEA). An asymmetrical steam generator secondary-side depressurization is produced as an accident management action at the steam generator in the loop without PZR, after the generation of the safety injection signal in order to achieve a determined depressurization rate in the primary system. 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 behavior in the entire transient. In conclusion, this work represents a small contribution for assessment of the predictability of thermal hydraulic computer codes such as TRACE5.
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