Thermal hydraulics of nuclear reactors
Conference
·
OSTI ID:5290777
This book presents the papers given at a conference on reactor thermohydraulics. Topics considered at the conference included two-phase hydrodynamics, heat transfer, mathematical models, simulators for the analysis of reactor transients, loss of coolant accidents, fluid-structure interactions, the thermal hydraulics of degraded cores, natural circulation, the behavior of plant components and systems, the behavior of containment systems, hydrogen behavior in containment, and reactor instrumentation.
- OSTI ID:
- 5290777
- Report Number(s):
- CONF-830103-
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ABSTRACTS
ACCIDENTS
ANALOG SYSTEMS
CONTAINMENT
CONTAINMENT SYSTEMS
CONVECTION
DOCUMENT TYPES
ELEMENTS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FLUID MECHANICS
FLUID-STRUCTURE INTERACTIONS
FUNCTIONAL MODELS
HEAT TRANSFER
HYDRAULICS
HYDROGEN
LEADING ABSTRACT
LOSS OF COOLANT
MASS TRANSFER
MATHEMATICAL MODELS
MECHANICS
MEETINGS
NATURAL CONVECTION
NONMETALS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR INSTRUMENTATION
REACTORS
SIMULATORS
THERMAL POWER PLANTS
THERMODYNAMICS
TRANSIENTS
TWO-PHASE FLOW
220900* -- Nuclear Reactor Technology-- Reactor Safety
ABSTRACTS
ACCIDENTS
ANALOG SYSTEMS
CONTAINMENT
CONTAINMENT SYSTEMS
CONVECTION
DOCUMENT TYPES
ELEMENTS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FLUID MECHANICS
FLUID-STRUCTURE INTERACTIONS
FUNCTIONAL MODELS
HEAT TRANSFER
HYDRAULICS
HYDROGEN
LEADING ABSTRACT
LOSS OF COOLANT
MASS TRANSFER
MATHEMATICAL MODELS
MECHANICS
MEETINGS
NATURAL CONVECTION
NONMETALS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR INSTRUMENTATION
REACTORS
SIMULATORS
THERMAL POWER PLANTS
THERMODYNAMICS
TRANSIENTS
TWO-PHASE FLOW