United States Nuclear Regulatory Commission - Protecting People and the Environment

Simulation of ROSA-2 Test-2 Experiment: Application to Nuclear Power Plant (NUREG/IA-0511)

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Publication Information

Manuscript Completed: April 2018
Date Published: March 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

Kirk 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

The purpose of this work is to overview the results provided by a first approach to the simulation of an Intermediate Break Loss-Of-Coolant Accident (IBLOCA) in a 3-loop PWR Nuclear Power Plant (NPP) using the thermal-hydraulic code TRACE5 patch 2 and the Symbolic Nuclear Analysis Packages software (SNAP) version 2.1.2.

The IBLOCA transient applied to the standard PWR TRACE5 model is the Test 2 (IB-CL-03) handled at the Large Scale Test Facility (LSTF) in the frame of the OECD/NEA ROSA-2 Project. Test 2 simulates a 17% cold leg IBLOCA under the assumption of the single-failure of High Pressure Injection and Low Pressure Injection systems and total failure of the Auxiliary Feedwater.

The LSTF is a Full Height Full Pressure (FHFP) facility designed to simulate a 4-loop W-type PWR (Tsuruga unit II NPP). The volumetric scaling factor is 1/48. The four primary loops of the reference PWR are scaled in LSTF by two equal-volume loops. The core power used to simulate the decay power is 10 MW, corresponding to 14% of the 1/48 volumetrically scaled reference PWR rated power.

The simulation results are provided throughout several graphs, where the main system variables, such as pressures, pressure vessel liquid levels and temperatures are shown. These results represent a contribution to assess the predictability of computer codes such as TRACE5.

Page Last Reviewed/Updated Thursday, March 14, 2019