Assessment of RELAP5/MOD3.3 and TRACE V5.0 Computer Codes against LOCA Test Data from PSB-VVER Test Facility (NUREG/IA-0435)

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Publication Information

Manuscript Completed: July 2013
Date Published: December 2013

Prepared by:
M. Kynčl, R. Pernica

Research Centre Řež,TSO
Hlavní 130
250 68 Husinec-Řež, Czech Republic

K. 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:
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

Availability Notice

Abstract

This report documents the USNRC system thermal-hydraulic codes assessment performed at Research Centre Rez. RELAP5/MOD3.3 and TRACE V5.0 computer codes were assessed against the experimental data from two LOCA tests carried out at PSB-VVER test facility built and operated at Electrogorsk Research and Engineering Center on NPPs Safety in Russia. Experimental data and all necessary information for developing the facility database and facility model notebook were available through the OECD/NEA/CSNI/WGAMA PSB Project.

In the RELAP5/MOD3.3 case, in addition to the best estimate post test analysis of LB LOCA experiment denoted as CL-2x100-01 by EREC and as Test-5a as part of the OECD PSB project, the uncertainty and sensitivity analysis was performed, and the results are presented here. Double ended cold leg guillotine break with initial power scaled further down to 15% was simulated in Test-5a.

In the TRACE V5.0 case, the best estimate post test analysis of SB LOCA experiment denoted as CL-4.1-03 by EREC and as Test-3 as part of the OECD PSB project was carried out, and the results are presented here. A 4.1% cold leg break was simulated in Test-3. The test scenario applied was very close to the scenario realized in LOBI test BL-34.

The RELAP5/MOD3.3 thermal-hydraulic model of PSB-VVER test facility was developed without using the SNAP Model Editor. The development of the TRACE V5.0 thermal-hydraulic model of the PSB-VVER test facility started from RELAP5/MOD3.3 model in SNAP environment. Firstly, the reference case input deck from RELAP5/MOD3.3 study was imported to SNAP and secondly, the thermal-hydraulic model was converted to TRACE V5.0. The resulting TRACE V5.0 thermal-hydraulic model was systematically verified using the Test-5a experimental data. After that, only few computer runs were needed to properly define the initial and boundary conditions of Test-3 in order to validate the TRACE V5.0 thermal-hydraulic model of the PSB-VVER test facility for analysis of SB LOCA.

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