Assessment of the one feedwater pump trip transient'' in Cofrentes nuclear power plant with TRAC-BF1

Technical Report · Wed Apr 01 04:00:00 EST 1992

OSTI ID:5346884

Castrillo, F ^[1]; Navarro, A G; Gallego, I ^[2]

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1. Hidroelectrica Espanola, Madrid (Spain)
2. Union Iberoamericana de Tecnologia Electrica, Madrid (Spain)

This report presents the results of the assessment of TRAC-BF1 (GiJ1) code with the model of the C.N. Cofrentes for simulation of the transient originated by the manual trip of one pump.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Hidroelectrica Espanola, Madrid (Spain)
• Sponsoring Organization: NRC; Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 5346884
• Report Number(s): NUREG/IA-0068; ON: TI92014447
• Country of Publication: United States
• Language: English

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99 GENERAL AND MISCELLANEOUS
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BWR TYPE REACTORS
COFRENTES REACTOR
COMPUTER CODES
COMPUTERIZED SIMULATION
COOPERATION
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EVALUATION
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INTERNATIONAL COOPERATION
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POWER REACTORS
PUMPS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
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SIMULATION
T CODES
THERMAL REACTORS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS