Study of Unusual Occurrence of a Partial Core Uncovery in an SBLOCA Scenario (NUREG/IA-0174)
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Date Published: February 2000
*Universidad Politecnica De Catalunya
ETSEIB, Av. Diagonal, N° 647
08028 Barcelona, SPAIN
**Asociación Nuclear Ascó
08004 Barcelona, SPAIN
Prepared as part of:
The Agreement on Research Participation and Technical Exchange
under the International Code Application and Maintenance Program (CAMP)
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
The Polytechnical University of Catalonia (UPC) has been cooperating since 1992 with the Asociación Nuclear Ascó (ANA) improving its plant model.
Ascó NPP is a two unit, three loop Pressurized Water Reactor (PWR) plant of Westinghouse design operated by ANA. Its model, developed for RELAP5/MOD3.2, includes thermal-hydraulics, kinetics and protection and control systems and has been qualified in previous calculations of several actual plant transients.
This report shows the results obtained with the Ascó NPP model for a 5 inch Loss of Coolant Accident using RELAP5/MOD3.2.
It also includes two different sensitivity studies performed to show the singularity of the phenomenology identified in the base case: the first study analyzes the influence of Main Coolant Pumps (MCPs) coast-down start; the second, the influence of the code itself (of its flow regime prediction).