Recirculation Suction Large Break LOCA Analysis of the Santa Maria De Garoña Nuclear Power Plant Using TRAC–BF1 (G1J1) (NUREG/IA-0067, ICSP–GA–LOCA–T)
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Date Published: August 1992
J. V. López, J. Blanco, Polytechnical University of Madrid
J. L. Crespo, University of Cantabria
R. A. Fernández, Nuclenor, S. A.
Polytechnical University of Madrid
c/José Abascal, 2
Prepared as part of:
The Agreement on Research Participation and Technical Exchange
under the International Thermal-Hydraulic Code Assessment
and Application Program (ICAP)
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
This document presents a recirculation suction large break loss of coolant accident analysis of Santa Maria de Garoña Nuclear Power Plant.
The plant is a General Electric Boiling Water Reactor 3, containment type Mark I. It Is operated by NUCLENOR, S.A. and was connected to the grid in 1971.
The analysis has been performed by the Chair of Nuclear Technology from the Polytechnical University of Madrid, the Applied Physics Department from the University of Cantabria and the Analysis and Operation Section from NUCLENOR, S.A. as a part of an agreedment for developing an engineering simulator of operational transients and accidents for Santa Maria de Garoña Power Plant.
The analysis was performed using the frozen version of TRAC-BF1 (G1J1) code and is the first of two NUCLENOR contributions to the International Code Applications and Assessment Program (ICAP).
The code was run in a CDC Cyber 830 with operating system NOS 2.6, property of NUCLENOR, S.A. Additionally the code was updated into a CDC Cyber 932 operating system NOS VE, in order to solve the problems related to central memory limitations found at early stages of the work. A programming effort was carried out in order to provide suitable graphics capabilities to the code.
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