United States Nuclear Regulatory Commission - Protecting People and the Environment

Post-Test Analysis of ROSA-2 Test 2 (IBLOCA) with TRACE (NUREG/IA-0503)

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Publication Information

Manuscript Completed: April 2018
Date Published: February 2019

Prepared by:

S. Gallardo, A. Querol, M. Lorduy and G. Verdú
Universitat Politècnica de València
Instituto Universitario de Seguridad Industrial, Radiofísica y Medioambiental
Camí de Vera s/n 46022 Valencia, 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 Radiation Protection Computer Code Analysis and Maintenance Program (RAMP)

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 simulating a 17% cold leg Intermediate Break Loss-Of-Coolant Accident (IBLOCA) in the Large Scale Test Facility (LSTF) using the thermal-hydraulic code TRACE5 patch 2. This IBLOCA transient corresponds to the Test 2 (IB-CL-03 in JAEA) and it is performed in the frame of the OECD/NEA ROSA-2 Project. During this transient, the single-failure of the High and the Low Pressure Injection systems (HPI and LPI, respectively) in the broken loop and the total failure of Auxiliary Feedwater (AFW) are assumed.

A detailed model of the LSTF and the chronology of events following these assumptions have been developed with TRACE5 patch 2. A comparison between the simulation and the experimental results is provided throughout different graphs. Acceptable general behavior is observed in the entire transient.

Page Last Reviewed/Updated Thursday, March 14, 2019