United States Nuclear Regulatory Commission - Protecting People and the Environment

Post-Test Analysis of Cold Leg Small Break 4.1% at PSB-VVER Facility using TRACE V5.0 (NUREG/IA-0502)

On this page:

Download complete document

Publication Information

Manuscript Completed: April 2018
Date Published: March 2019

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

Availability Notice

Abstract

The U.S. NRC best estimate thermo-hydraulic computer code TRACE V5.0 has been assessed against the "4.1 % cold leg break (CL-4.1-03)" experiment at the large-scale test facility PSB-VVER. The PSB-VVER facility is a 1:300 volume-power scaled model of VVER-1000 NPP located in Electrogorsk, Russia. An extensive TRACE input deck of PSB-VVER facility was developed. The model includes all important components of the PSB-VVER facility: reactor, 4 separated loops, pressurizer, HPIS and LPIS ECCS, several 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). The TRACE code is 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 the TRACE code 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 presented analysis is the latest in series of TRACE and RELAP5 assessment calculations evaluated at the company TES. The purpose of performed analyses is to extend the validation of the TRACE code focused on VVER type of NPPs and to support applicability of the TRACE code in the Czech Republic.

Page Last Reviewed/Updated Friday, March 15, 2019