Report a Safety Concern
Search

The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Home NRC Library Document Collections NUREG-Series Publications Publications Resulting from International Agreements

Post-Test Calculation of the ROSA/LSTF Test 3-2 using RELAP5/mod3.3 (NUREG/IA-0410)

On this page:

Download complete document

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. This report analyzes with RELAP5mod3.3 the LSTF Test 3-2, which simulates a loss-of-feedwater transient (LOFW) without scram and with a total failure of the high pressure injection system (HPIS). The simulation of several phenomena related with the high power natural circulation has been object of study as well as the impact of the environment heat losses in the primary coolant discharge across the pressurizer power-operated relief valve (PORV).

Page Last Reviewed/Updated Tuesday, March 09, 2021