Two-phase flows and heat transfer with application to nuclear reactor design problems
Book
·
OSTI ID:6589787
- ed.
Nineteen chapters are included under the following headings: introduction to two-phase flow, simple momentum and energy balances and their related empirical correlations, bubble and slug flow, annular two-phase flow, two-phase heat transfer, nucleate boiling heat transfer, heat transfer in high-quality two-phase flow, burnout, constitutive equations for two-phase flow, critical two-phase flow, oscillatory two-phase flow, steady-state void fraction and pressure drop in water-cooled reactors, steam-water separation, steady-state subchannel analysis, measuring techniques, steady-state critical heat flux in water-cooled fuel assemblies, subcooled boiling, blowdown, and ECCS refilling.
- OSTI ID:
- 6589787
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
BOILING
BURNOUT
CRITICAL FLOW
CRITICAL HEAT FLUX
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
HEAT FLUX
HEAT TRANSFER
MATHEMATICAL MODELS
NUCLEATE BOILING
PHASE TRANSFORMATIONS
PRESSURE DROP
REACTOR PROTECTION SYSTEMS
REACTORS
SUBCOOLED BOILING
TWO-PHASE FLOW
VOID FRACTION
WATER COOLED REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
BOILING
BURNOUT
CRITICAL FLOW
CRITICAL HEAT FLUX
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
HEAT FLUX
HEAT TRANSFER
MATHEMATICAL MODELS
NUCLEATE BOILING
PHASE TRANSFORMATIONS
PRESSURE DROP
REACTOR PROTECTION SYSTEMS
REACTORS
SUBCOOLED BOILING
TWO-PHASE FLOW
VOID FRACTION
WATER COOLED REACTORS