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:10146667

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: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 10146667
• Report Number(s): NUREG/IA--0068; ON: TI92014447; IN: ICSP-CO-TURFW-T
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
99 GENERAL AND MISCELLANEOUS
990200
COFRENTES REACTOR
COMPUTERIZED SIMULATION
EVALUATION
HEAT TRANSFER
HYDRAULICS
INTERNATIONAL COOPERATION
MATHEMATICS AND COMPUTERS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
PUMPS
REACTOR SAFETY
RESEARCH PROGRAMS
T CODES
TRANSIENTS