Post-Test Calculation of the ROSA/LSTF Test 3-1 using RELAP5/mod3.3 (NUREG/IA-0409)

On this page:

• Publication Information
• Abstract

Download complete document

• NUREG/IA-0409 (PDF - 1.23 MB)

Publication Information

Manuscript Completed: January 2012
Date Published: March 2012

Prepared by:
V. Martinez, F. Reventós, C. Pretel

Institute of Energy Technologies
Technical University of Catalonia
ETSEIB, Av. Diagonal 647, Pav. C
08028 Barcelona, SPAIN

A. Calvo, NRC Project Manager

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

Abstract

The Thermalhydraulic Studies Group of Technical University of Catalonia (UPC) holds a large background in nuclear safety studies in the field of Nuclear Power Plant (NPP) code simulators. RELAP5mod3.3 has been used in this study in order to analyze the LSTF Test 3-1, which simulates an anticipated transient without scram (ATWS) as a result of a small break LOCA without rods insertion (but with scram signal) and loss of off-site power. Two local phenomena have been object of study: U-tube liquid accumulation due to CCFL at the inlet of the SG Utubes, and loop seal behavior during the transient.