Laguna Verde closure of all MSIV transient analyses with TRAC-BF1
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:6932259
This paper shows the work performed to analyze the behavior of the Laguna Verde Nuclear Power Station (LVNPS) in the event of the total closure of the main steam isolation valves (MSIVs). This analysis was based on results derived by the TRAC-BF1 code, a well-known best-estimate code used for transient analyses of boiling water reactors (BWRs). The work undertook an evaluation of several safety parameters, such as dome pressure rise, maximum temperature in the fuel, maximum reactor power, and others. The LVNPS is a 1931-MW(thermal) BWR/5 General Electric plant. A TRAC-BF1 model of LVNPS was developed in this work and proved to work quite well when compared with other theoretical results. A comparison of the TRAC-BF1 calculations with those of the start-up tests is in process that will validate the LVNPS model.
- OSTI ID:
- 6932259
- Report Number(s):
- CONF-901101--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 62
- Country of Publication:
- United States
- Language:
- English
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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
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTROL
CONTROL ELEMENTS
CONTROL EQUIPMENT
COOLING SYSTEMS
CORE SPRAY SYSTEMS
DRYERS
ECCS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
EQUIPMENT
FEEDWATER
FLOW REGULATORS
FUEL ELEMENTS
HIGH PRESSURE COOLANT INJECTION
HYDROGEN COMPOUNDS
LAGUNA VERDE-1 REACTOR
LEVELS
LOW PRESSURE COOLANT INJECTION
OXYGEN COMPOUNDS
POSITIONING
POWER DENSITY
POWER REACTORS
PRESSURIZATION
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
RELIEF VALVES
SAFETY
SCRAM
SECONDARY COOLANT CIRCUITS
SEPARATION EQUIPMENT
SHUTDOWN
SIMULATION
STEADY-STATE CONDITIONS
STEAM SEPARATORS
STEAM SYSTEMS
T CODES
TEMPERATURE CONTROL
THERMAL REACTORS
TRANSIENTS
VALVES
VAPOR SEPARATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTROL
CONTROL ELEMENTS
CONTROL EQUIPMENT
COOLING SYSTEMS
CORE SPRAY SYSTEMS
DRYERS
ECCS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
EQUIPMENT
FEEDWATER
FLOW REGULATORS
FUEL ELEMENTS
HIGH PRESSURE COOLANT INJECTION
HYDROGEN COMPOUNDS
LAGUNA VERDE-1 REACTOR
LEVELS
LOW PRESSURE COOLANT INJECTION
OXYGEN COMPOUNDS
POSITIONING
POWER DENSITY
POWER REACTORS
PRESSURIZATION
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
RELIEF VALVES
SAFETY
SCRAM
SECONDARY COOLANT CIRCUITS
SEPARATION EQUIPMENT
SHUTDOWN
SIMULATION
STEADY-STATE CONDITIONS
STEAM SEPARATORS
STEAM SYSTEMS
T CODES
TEMPERATURE CONTROL
THERMAL REACTORS
TRANSIENTS
VALVES
VAPOR SEPARATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS