The modeling of emergency core cooling systems in a degraded BWR core
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6503548
None
- Research Organization:
- Rensselaer Polytechnic Institute, Troy, NY 12181
- OSTI ID:
- 6503548
- Report Number(s):
- CONF-840614-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 46
- 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
ACCIDENTS
ALGORITHMS
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EQUATIONS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
M CODES
MATHEMATICAL LOGIC
MECHANICS
MELTDOWN
QUENCHING
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTOR PROTECTION SYSTEMS
REACTORS
SIMULATION
THERMODYNAMICS
TWO-DIMENSIONAL CALCULATIONS
TWO-PHASE FLOW
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
ACCIDENTS
ALGORITHMS
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EQUATIONS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
M CODES
MATHEMATICAL LOGIC
MECHANICS
MELTDOWN
QUENCHING
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTOR PROTECTION SYSTEMS
REACTORS
SIMULATION
THERMODYNAMICS
TWO-DIMENSIONAL CALCULATIONS
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS