Development of a Vandellòs II NPP Model using the TRACE Code:Application to an Actual Transient of Main Coolant Pumps Trip and Start-up (NUREG/IA-0243)

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Publication Information

Manuscript Completed: April 2009
Date Published: February 2011

Prepared by:
O. Lozano, C-P. Chiang, C. Llopis,
L. Batet, F. Reventόs

Department of Physics and Nuclear Engineering
Technical University of Catalonia
ETSEIB, Av. Diagonal 647, Pav. C
08028 Barcelona
Spain

A. Calvo, NRC Project Manager

Prepared for:
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 International Code Assessment and Maintenance Program (CAMP)

Published by:
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

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Abstract

The Thermal-Hydraulics Studies Group (GET) of the Technical University of Catalonia (UPC) has developed a model of Vandellòs II NPP (CNV II) for TRACE using as a previous RELAP5 model of the plant. The model simulates the components of the primary and secondary circuits, along with the main heat structures (nuclear fuel, SG tubes and pressurizer heaters). Passive heat structures and neutron kinetics are not simulated in the model. The model includes some of the plant control systems.

The main predicted steady state nominal parameters successfully match plant and design values. A real loss of off-site power with the subsequent Reactor Coolant Pumps start-up sequence (occurred in August 24th of 1993) has been simulated. The asymmetric behaviour of the flows in the vessel has been useful in qualifying the 3D capabilities of the TRACE VESSEL component.

Mass flows of primary loops are among the most important parameters in the analyzed transient. The simulation results are very similar to the data recorded at the plant. The similarity of calculated and measured values is a guarantee of the validity of the model.