Analytical simulation of BWR pressure suppression pool swell
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5790867
None
- Research Organization:
- General Electric Company, Nuclear Energy Division, 175 Curtner Avenue, San Jose, CA 95125
- OSTI ID:
- 5790867
- Report Number(s):
- CONF-830609-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 44
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AIR FLOW
BUBBLES
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINMENT
CONTAINMENT SPRAY SYSTEMS
CONTAINMENT SYSTEMS
CONTAINMENT SYSTEMS EXPERIMENT
DIFFERENTIAL EQUATIONS
ENGINEERED SAFETY SYSTEMS
EQUATIONS
FAILURES
FLOW MODELS
FLOW RATE
FLUID FLOW
FLUID MECHANICS
GAS FLOW
LOSS OF COOLANT
MACH NUMBER
MATHEMATICAL MODELS
MECHANICS
NAVIER-STOKES EQUATIONS
PARTIAL DIFFERENTIAL EQUATIONS
PRESSURE SUPPRESSION
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
RUPTURES
S CODES
SIMULATION
STEAM
STEAM LINES
SWELLING
TWO-DIMENSIONAL CALCULATIONS
VELOCITY
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AIR FLOW
BUBBLES
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINMENT
CONTAINMENT SPRAY SYSTEMS
CONTAINMENT SYSTEMS
CONTAINMENT SYSTEMS EXPERIMENT
DIFFERENTIAL EQUATIONS
ENGINEERED SAFETY SYSTEMS
EQUATIONS
FAILURES
FLOW MODELS
FLOW RATE
FLUID FLOW
FLUID MECHANICS
GAS FLOW
LOSS OF COOLANT
MACH NUMBER
MATHEMATICAL MODELS
MECHANICS
NAVIER-STOKES EQUATIONS
PARTIAL DIFFERENTIAL EQUATIONS
PRESSURE SUPPRESSION
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
RUPTURES
S CODES
SIMULATION
STEAM
STEAM LINES
SWELLING
TWO-DIMENSIONAL CALCULATIONS
VELOCITY
WATER COOLED REACTORS
WATER MODERATED REACTORS