United States Nuclear Regulatory Commission - Protecting People and the Environment

Post-Test Analysis of Upper Plenum 11% Break at PSB-VVER Facility using TRACE V5.0 and RELAP5/MOD3.3 Code (NUREG/IA-0449)

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Publication Information

Manuscript Completed: May 2014
Date Published: July 2014

Prepared by:
Petr Heralecky

TES Ltd.
Prazska 597
674 01 Trebic, 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:
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

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Abstract

The best estimate thermo-hydraulic computer code TRACE V5.0 and RELAP5 MOD3.3 had been assessed using Upper Plenum 11% break experiment at the large-scale test facility PSB-VVER. The PSB-VVER facility is a 1:300 volume scaled model of VVER 1000 NPP located in Electrogorsk, Russia. An extensive TRACE and RELAP5 input decks of PSB-VVER facility were developed including all important components of the PSB-VVER facility: reactor, 4 separated loops, pressurizer, break units, main circulation pumps, steam generators, and important parts of secondary circuit. The TRACE (TRAC/RELAP Advanced Computational Engine) is the latest in a series of advanced, best-estimate reactor systems codes developed by the U.S. Nuclear Regulatory Commission in frame of CAMP (Code Application and Maintenance Program) and the RELAP5 code is its predecessor. The TRACE and RELAP5 codes are a component-oriented reactor systems analysis codes designed to analyze light water reactor transients up to the point of significant fuel damage. The original validation of both codes was mainly based on experiments performed on experimental facilities of typical PWR design. There are some different features of VVER design comparing to PWR. Therefore the validation of the thermo-hydraulic codes for VVER types of reactors is often required by national regulators. The purpose of performed analysis is to extend the validation of the TRACE and RELAP5 code focused on VVER type of NPPs. The TRACE calculation was performed in the frame of R&D project co-funded by The Ministry of Industry and Trade of Czech Republic. The RELAP5 calculation was performed to support standardization of the RELAP5 code in TES Company.

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