Recirculation suction large break LOCA analysis of the Santa Maria De Garona Nuclear Power Plant using TRAC-BF1 (G1J1)

Technical Report · Sat Aug 01 04:00:00 EDT 1992

OSTI ID:7041700

Lopez, J V; Blanco, J ^[1]; Crespo, J L ^[2]; Fernandez, R A ^[3]

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1. Universidad Politecnica de Madrid (Spain)
2. Univ. of Cantabria (Spain)
3. Nuclenor, S.A. (Spain)

This document presents a recirculation suction large break loss of coolant accident analysis of Santa Maria de Garona Nuclear Power Plant. The plant is a General Electric Boiling Water Reactor 3, containment type Mark 1. 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 agreement for developing an engineering simulator of operational transients and accidents for Santa Maria de Garona Power Plant. The analysis was performed using the frozen version of TRAC-BFI (GlJl) code and is the first of two NUCLENOR contributions to the International Code Applications and Assessment Program (ICAP).

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Universidad Politecnica de Madrid (Spain)
• Sponsoring Organization: NRC; Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 7041700
• Report Number(s): NUREG/IA-0067; ON: TI92019680
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CODES
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FLUID MECHANICS
GARONA REACTOR
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
POWER REACTORS
PUMPS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
T CODES
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS