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Transient two-phase flow

Conference ·
OSTI ID:5201991
; ;

This book presents the papers given at a conference which examined two-phase flow in relation to reactor safety. Topics considered at the conference included reactor monitoring systems, blowdown, wave propagation, critical heat flux, film boiling, reflooding, void fraction, rod bundles, dryout, flow models, loss of coolant, heat transfer, transients, computer codes, thermodynamics, and hydraulics.

OSTI ID:
5201991
Report Number(s):
CONF-810307-
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
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ABSTRACTS
ACCIDENTS
BLOWDOWN
BOILING
COMPUTER CODES
CRITICAL HEAT FLUX
DOCUMENT TYPES
DRYOUT
ENERGY TRANSFER
FILM BOILING
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
LEADING ABSTRACT
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
MEETINGS
PHASE TRANSFORMATIONS
QUENCHING
REACTOR ACCIDENTS
REACTOR MONITORING SYSTEMS
REACTOR SAFETY
ROD BUNDLES
SAFETY
THERMODYNAMICS
TRANSIENTS
TWO-PHASE FLOW
VOID FRACTION
WAVE PROPAGATION