United States Nuclear Regulatory Commission - Protecting People and the Environment

Assessment of TRACE 5.0 Against ROSA-2 Test 3 Counterpart Test to PKL (NUREG/IA-0504)

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Publication Information

Manuscript Completed: April 2018
Date Published: March 2019

Prepared by:
S. Gallardo, A. Querol, M. Lorduy, and G. Verdu

Universitat Politècnica de València
Instituto Universitario de Seguridad Industrial, Radiofísica y Medioambiental
Camí de Vera s/n
46022 Valencia, SPAIN

Kirk Tien, NRC Project Manager

Division of Systems Analysis
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

Published by:
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

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Abstract

The purpose of this work is to overview the results obtained by the simulation of the Counterpart Test 3 PKL-ROSA (SB-HL-18 in JAEA) in the Large Scale Test Facility (LSTF) using the thermal-hydraulic code TRACE5 patch 2. This experiment simulates a PWR hot leg Small Break Loss-Of-Coolant Accident (SBLOCA).

One of the main objectives of this test is to establish a relationship between the Core Exit Temperature (CET) measured by the thermocouples and the fuel rod surface temperature (Peak Cladding Temperature, PCT). The core exit thermocouples are used as an important indicator to start an accident management (AM) operator action by detecting core temperature excursion during reactor accidents. Test 3 provides experimental data to study the relation between CET and PCT and the time delay existing between them.

A detailed model of the LSTF and the control logic of the Test 3 have been simulated using TRACE5 patch 2. The main thermal hydraulic variables obtained with TRACE5 have been compared with experimental data. In general, the simulation results are able to reproduce the experimental behavior.

Page Last Reviewed/Updated Friday, March 15, 2019