TRACE Nodalization Performance in PSB-VVER SB-LOCA Benchmark (NUREG/IA-0557)

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Publication Information

Manuscript Completed: May 2025
Date Published: July 2025

Prepared by:
R. Orosz, T. Varju, B. Biró & A. Aszódi

Budapest University of Technology and Economics
Institute of Nuclear Techniques
Műegyetem rkp. 3.
1111 Budapest, Hungary

A. Hsieh, 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

In the recent decades computer code calculations have become invaluable in nuclear engineering. With the modern tools, the experts are able to predict the different processes with high accuracy, which has numerous advantages, such as improved reactor safety, enhanced design optimization and cost-effectiveness. It is however essential that the user possesses adequate knowledge and experience about the given code, including its principles and limitations.

In the current report the focus is on the nodalization of the thermal-hydraulic models built for the PSB-VVER integral test facility. Altogether three models have been constructed in TRACE, where the main differences are in the used components and their nodalization of the RPV section. To assess the behavior of the models, a cold leg small break loss of coolant accident benchmark was chosen. In the report we present both the qualitative and quantitative comparison of the calculations and the measurements performed on the facility. For the quantitative evaluation, two methods, namely FFTBM-SM and SARBM, have been used. Finally, a summary of the notable observations and recommendations is included.