Analysis with TRACE Code of PKL III Tests G1.2. Study on Heat Transfer Mechanisms in the SG in Presence of Nitrogen, Steam and Water as a Function of the Primary Coolant Inventory in Double Loop Operation (NUREG/IA-0521)

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Publication Information

Manuscript Completed: August 2019
Date Published: November 2020

Prepared by:
A. Julbe, C. Berna, A. Escrivá & J.L. Muñoz-Cobo

Instituto de Ingeniería Energética
Universitat Politècnica de València
Camino de Vera 14, 46022 València.
Spain.

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 goal of this report is to explain the main results obtained in the simulations performed with the consolidated thermal-hydraulic code TRACE regarding tests PKL III G1.2. The G1 test series are composed of G1.1, G1.1a and G1.2 tests, all of them are focused on the occurrence of boron dilution processes following the loss of Residual Heat Removal System (RHRS) during ¾-loop operation (primary circuit still closed). Main objective was to provide a data basis for thermal-hydraulics codes for a better understanding of the heat transfer mechanisms in the Steam Generator in presence of Nitrogen, steam and water in the U-tubes and of the coolant transport phenomena observed inside the U-tubes. The differences among G1.1/G1.1a and G1.2 test series are the coolant drain-injections sequences and the loop configuration, 1 loop or 2 loops in operation respectively. The main goal of this report is to analyse the capacity of TRACE V5.0p2 code to precisely simulate thermal stratification and natural circulation of both single and two-phase fluxes inside the whole primary circuit, as well as accurately predicting boron concentration variations.