United States Nuclear Regulatory Commission - Protecting People and the Environment

International Agreement Report: Simulation of LSTF Hot Leg Break (OECD/NEA ROSA-2 Test 1) with TRACE Code: Application to a PWR NPP Model (NUREG/IA-0444)

On this page:

Download complete document

Publication Information

Manuscript Completed: March 2014
Date Published: April 2014

Prepared by:
Juan Gonzalez-Cadelo1, César Queral1,
J. Montero-Mayorga1, J. C. Martinez Murillo2

1Universidad Politécnica de Madrid
Alenza 4. 28003 Madrid.
Spain.

2Almaraz-Trillo AIE
Avda. de Manoteras, 46, 28050 Madrid.
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:
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

Availability Notice

Abstract

An analysis of LSTF Surge Line Break experiment (OECD/NEA ROSA-2 test 1) has been performed with TRACE code. This test, included within the OECD/NEA ROSA-2 project and performed in Large Scale Test Facility (LSTF), it is attempted to analyze the phenomenology and different accident management actions after the occurrence of a surge line (SL) break with failure of High Pressure Safety Injection (HPSI). The comparison between experimental data and the results obtained with TRACE code shows that, in general, the main phenomena are well reproduced.

Additionally, a broad analysis of Surge Line Medium Break Loss of Coolant Accident with HPSI failed in a Westinghouse PWR has been performed taking into account different accident management actions and conditions in order to check their suitability.

These works has been performed in the framework of OECD/NEA ROSA-2 and CAMP projects.

Page Last Reviewed/Updated Monday, May 05, 2014