United States Nuclear Regulatory Commission - Protecting People and the Environment

Post-Test Calculation of the PKL-2 Test G7.1 Using RELAP5/MOD3.3 (NUREG/IA-0499)

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Publication Information

Manuscript Completed: November 2017
Date Published: February 2019

Prepared by:
V Martinez-Quiroga, F. Reventos, and C. Pretel

Institute of Energy Technologies
Technical University of Catalonia
ETSEIB, Av. Diagonal 647, Pav. C
08028 Barcelona 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

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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 G7.1 PKL Test. This experiment is part of a Counterpart Test performed in LSTF and PKL Test Facilities within the framework of the OECD/NEA ROSA-2 and PKL-2 projects. Detailed core nodalizations and Pseudo 3D modeling have been object of study as well as the capabilities of the code for reproducing the correlation between the Core Exit Temperature (CET) and the Peak Cladding Temperature (PCT).

Page Last Reviewed/Updated Thursday, February 28, 2019