Plant Application with TRACE Code of the PKL III G1 Test Series. Study on Heat Transfer Mechanisms in the SG in Presence of Nitrogen, Steam and Water as a Function of the Primary Coolant Inventory in Single & Double Loop Operation (NUREG/IA-0537)

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Publication Information

Manuscript Completed: December 2021
Date Published: February 2023

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

CoboInstituto de Ingeniería Energética
Universitat Politècnica de València
Camino de Vera 14, 46022 València

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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The main goal of this report is to explain a PWR plant application of the G1 tests series carried out in the PKL III facility through a TRACE model. With this purpose, the experimental data and TRACE V5.0p2 simulation results of PKL III G1.1 and G1.2 tests are used. Then, two TRACE simulations have been carried out, one for a commercial NPP model and the other for an own PKL facility model. The PKL III G1 test series are focused on the occurrence of boron dilution processes following the loss of RHRS during ¾-loop operation. Test G1.1 features a systematic study on heat transfer in SG U-tubes in presence of nitrogen, steam and water with variable Primary Coolant Inventory (PCI) in the PKL III test facility with a single loop configuration. While G1.2 test as the same purpose than G1.1 but with two loops in operation. A 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 flow inside the whole primary circuit of PKL facility.

Page Last Reviewed/Updated Thursday, March 02, 2023