Post-Test Calculation of the ROSA/LSTF Test 3-2 using RELAP5/mod3.3 (NUREG/IA-0410)

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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

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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. This report analyzes with RELAP5mod3.3 the LSTF Test 3-2, which simulates a loss-of-feedwater transient (LOFW) without scram and with a total failure of the high pressure injection system (HPIS). The simulation of several phenomena related with the high power natural circulation has been object of study as well as the impact of the environment heat losses in the primary coolant discharge across the pressurizer power-operated relief valve (PORV).