Heat and Mass Transfer in Severe Nuclear Reactor Accidents. Proceedings of the International Symposium
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc
ISBN Print: 978-1-56700-059-7
Inhaltsverzeichnis
Author Index
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.10
Preface
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.20
TMI-2 VESSEL INVESTIGATION: RESULTS, CONCLUSIONS AND IMPLICATIONS FOR ACCIDENT MANAGEMENT STRATEGIES
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.30
SAFETY ASSURANCE APPROACH TO SEVERE ACCIDENTS AND SEVERE ACCIDENT MANAGEMENT AT NUCLEAR POWER PLANTS WITH WWER
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.40
FEATURES OF RBMK REACTORS DURING SEVERE ACCIDENTS AND RELATED ASSESSMENT TECHNIQUES
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.50
CANADIAN INVOLVEMENT IN RBMK SAFETY IMPROVEMENT PROGRAMMES
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.60
REGULATORY APPROACHES TO SEVERE ACCIDENT ISSUES: AN lNTERNATIONAL PERSPECTIVE
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.70
ESTIMATION OF COREMELT EVENT TREES
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.80
CORE MELT PROGRESSION: STATUS OF CURRENT UNDERSTANDING AND PRINCIPAL UNCERTAINTIES
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.90
STATUS OF ATHLET-CD DEVELOPMENT SHOWN BY THE LOFT-FP-2-ANALYSIS AS AN EXAMPLE
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.100
VERIFICATION OF MODIFIED VERSION OF SFD INTEGRAL CODE ICARE2 AGAINST C0RA-W2 (ISP-36) EXPERIMENTAL DATA
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.110
STATUS OF THE INTERPRETATION OF THE PHEBUS FPTO TEST WITH ICARE 2: BUNDLE DEGRADATION
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.120
ICARE2 LATE PHASE DEGRADATION MODELS APPLICATION TO TMI-2 ACCIDENT
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.130
CEC REINFORCED CONCERTED ACTION ON REACTOR SAFETY: PRIMARY CIRCUIT ASPECTS OF THE SOURCE TERM PROJECT
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.140
THE RELEASE AND TRANSPORT OF LOW VOLATILITY FISSION PRODUCTS UNDER SEVERE ACCIDENT CONDITIONS
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.150
LWR SEVERE ACCIDENT SOURCE TERMS:
Part 1: Fission product release, transport and behavior in core and primary system;
Part 2: Fission product release, transport and behavior in the containment
Part 1: Fission product release, transport and behavior in core and primary system;
Part 2: Fission product release, transport and behavior in the containment
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.160
A STUDY OF DIFFUSIOPHORETIC PARTICLE DEPOSITION IN A STEAM GENERATOR TUBE IN PWR PRIMARY CIRCUIT USING THE SOPHAEROS CODE
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.170
THERMALHYDRAULIC BEHAVIOR OF A MOLTEN CORE WITHIN A STRUCTURE, SIMULATED BY THE TOLBIAC CODE
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.180
MOLTEN POOL MODELLING IN PWR SEVERE ACCIDENT SCENARIO CODES
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.190
CORIUM-WATER INTERACTION STUDIES IN FRANCE
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.200
ESCALATING AND PROPAGATING MELT/COOLANT INTERACTIONS IN THE KROTOS EXPERIMENTS: STATUS OF KNOWLEDGE
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.210
SEVERE ACCIDENT MITIGATION CONCEPT FOR THE EPR AND R&D-SUPPORT
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.220
EFFECTIVENESS OF THE MODERATOR AS A HEAT SINK DURING A LOSS-OF-COOLANT ACCIDENT IN A CANDU-PHW REACTOR
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.230
COOLABILITY OF SEVERELY DEGRADED CANDU CORES
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.240
LWR SEVERE ACCIDENT SOURCE TERMS: Part 2: Fission product release, transport and behavior in the containment
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.250
INSIGHTS INTO SEVERE ACCIDENT PHENOMENA FROM LEVEL 2 PSA
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.260
THERMALHYDRAULICS TESTING OF THE PHEBUS-FP CONTAINMENT
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.270
EXPERIMENTAL INVESTIGATION AND ANALYSIS OF HYDROGEN COMBUSTION
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.280
CRITERIA FOR TRANSITION FROM DEFLAGRATION TO DETONATION IN H2-AIR-STEAM MIXTURES
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.290
CATALYTIC RECOMBINERS FOR SEVERE ACCIDENT HYDROGEN
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.300
Experiments on Vessel Hole Ablation During Severe Accidents
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.310
VALIDATION OF HYDRODYNAMIC MODELS OF THE RASPLAV/SPREAD CODE AGAINST THE CORINE EXPERIMENTS
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.320
GEYSER/TONUS : A CODE FOR SEVERE ACCIDENTS CONTAINMENT ATMOSPHERE ANALYSIS
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.330
IODINE BEHAVIOUR IN CONTAINMENT
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.340
U.S. NRC SEVERE ACCIDENT CODES - PROGRESS, STATUS AND FUTURE DIRECTION OF MODELING AND SUPPORTING EXPERIMENTAL ACTIVITIES
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.350
SEVERE ACCIDENT RESEARCH ACTIVITIES IN JAPAN
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.360
SEVERE ACCIDENT RESEARCH IN RUSSIA
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.370
TEXAS-V: A FUEL-COOLANT INTERACTION MODEL
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.380
AEA TECHNOLOGY CALCULATIONAL SUPPORT FOR THE CORA EARLY PHASE MELT PROGRESSION EXPERIMENTS
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.390
PARALLEL COMPUTING APPLIED TO THE MODELLING OF THE COMPLEX INTERACTING PHENOMENA IN SEVERE FUEL DAMAGE EXPERIMENTS
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.400
VAPEX CODE FOR ANALYSIS OF STEAM EXPLOSIONS UNDER SEVERE ACCIDENTS
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.410
Accident Progression and Source Term Analyses for LWR Severe Accidents - Japanese Activities and Progress -
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.420
DEVELOPMENT OF THE RBMK-1500 MODELS USING STATE-OF-ART CODES
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.430
EXPERIMENTAL ANALYSIS OF AEROSOL BEHAVIORS IN PRIMARY PIPING WITH ART CODE DURING SEVERE ACCIDENT
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.440
R&D NEEDS RELATED TO THE CORE CATCHER CONCEPT BASED ON CORIUM SPREADING
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.450
STATUS OF THE ESTER SEVERE ACCIDENT CODE SYSTEM
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.460
ESCADRE MODO AND RALOC MOD2 ASSESSMENT MAJOR FINDINGS AND RELEVANCE TO THE SAFETY OF LWRS
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.470
NET HEAT FLUX IDENTIFICATION USING DIGITIZED TEMPERATURE DATA IN REACTOR ACCIDENTS WITH HOT SPOT FORMATION ON THIN WALL WITH VARIABLE THERMAL CONDUCTIVITY
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.480
STATUS AND MAIN UNCERTAINTIES IN LEADING SEVERE ACCIDENT ANALYSIS CODES
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.490
DEVELOPMENT OF A SET OF CODES FOR NPP SEVERE ACCIDENT ANALYSIS
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.500
SUMMARY AND PANEL DISCUSSION
DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.510