SESSION 1: Overview of Severe Accidents in Nuclear Power Plants (Impacts of TMI and Chernobyl)

• LECTURE: TMI-2 Vessel Investigation: Results, Conclusions and Implications for Accident Management Strategies
• LECTURE: Safety Assurance Approach to Severe Accidents and Severe Accident Management at the NPP with WWER
• LECTURE: Features of RBMK Reactors During Severe Accidents and Related Assessment Techniques
• LECTURE: Canadian Involvement in RBMK Safety Improvement Programmes
• LECTURE: Regulatory Approaches to Severe Accident Issues: An International Prospective

SESSION 2: Reactor Core and Primary System Behaviour and Consequences in Severe Accidents

• Estimation of Coremelt Event Trees
• Core Melt Progression: Status of Current Understanding and Principal Uncertainties

  CODE VERIFICATION AGAINST EXPERIMENTS

• Status of ATHLET-CD Development Shown by the LOFT-FP-2 Analysis as an Example
• Verification of Modified Version of SFD Integral Code ICARE2 Against CORA-W2 (ISP-36) Experimental Data
• Status of the Interpretation of the PHEBUS FPT0 Test with ICARE2: Bundle Degradation
• ICARE2 Late Phase Degradation Model: Application to TMI-2 Accident

  SOURCE TERMS - FISSION PRODUCT TRANSPORT

• LECTURE: CEC Reinforced Concerted Action on Reactor Safety; Source Term Project
• The Release and Transport of Low Volatility Fission Products under Severe Accident Conditions
• LWR Severe Accident Source Term, Part 1: Fission Product Release, Transport and Behaviour in Core and Primary Systems
• A Study of Diffusiophoretic Particle Deposition in a Steam Generator Tube in PWR Primary Circuit with the SOPHAEROS Code

  MODELLING OF LATE-PHASE PHENOMENA

• Thermalhydraulic Behaviour of a Molten Core within a Structure, Simulated by the TOLBIAC Code
• Molten Pool Modelling in PWR Severe Accident Scenario Codes
• Review of Models and Codes Describing WWER and RBMK Reactors. First Outline Systems Behaviour under Heavy Accidents
• Numerical Decision of Steady and Unsteady Problems of Thermal Conductivity and Thermal Elasticity for Reactor Pressure Vessel

  FUEL-COOLANT INTERACTIONS

• Corium-Water Interaction Studies in France
• Escalating and Propagating Melt/Coolant Interactions in the KROTOS Experiments: Status of Knowledge

  ACCIDENT MITIGATION

• LECTURE: Severe Accident Mitigation Concept for the EPR and R&D-Support
• Effectiveness of the Moderator as a Heat Sink During a Loss-of-Coolant Accident in a CANDU-PHW Reactor
• Coolability of Severely Degraded CANDU Cores

SESSION 3: Containment Behaviour in Severe Accidents

• LECTURE: LWR Severe Accident Source Term, Part 2: Fission Product Release, Transport and Behaviour in the Containment
• LECTURE: Insights into Severe Accident Phenomena from Level 2 PSA
• Prediction of the Thermal-Hydraulics of Model Containments
• Thermalhydraulics Testing of the Phebus-FP Containment
• Experimental Investigation and Analysis of Hydrogen Combustion
• Criteria for Transition from Deflagration to Detonation in H₂/Air/Steam Mixtures
• Catalytic Hydrogen Mitigation in Post-Accident Containments
• Experiments on Vessel Hole Ablation During Severe Accidents
• Passive Containment Cooling after a Core Melt Accident
• Validation of RASPLAV/SPREAD Code against CORINE Experiments
• GEYSER/TONUS: A Code for Severe Accidents Containment Atmosphere Analysis
• Ad-hoc Filtration for Severe Accidents
• Iodine Behaviour in Containment

SESSION 4: Computer Modelling and Research on Heat and Mass Transfer in Severe Accidents

OVERVIEW OF SEVERE ACCIDENT RESEARCH
• US NRC Severe Accident Research Program - Progress, Status and Future Direction of Modelling and Supporting Experimental Activities
• Severe Accident Research Activities at JAERI
• Severe Accident Research in Russia

  DEVELOPMENT AND APPLICATION OF COMPUTER CODES FOR SEVERE ACCIDENT ANALYSIS

• TEXAS-V - A Model for Simulation of the Vapor Explosion Process
• AEA Calculational Support for the CORA Early Phase Melt Progression Experiment
• Parallel Computing Applied to the Modelling of the Complex Interacting Phenomena in Severe Fuel Damage Experiments
• VAPEX Code for and Analysis of Steam Explosions Under Severe Accidents
• Accident Progression and Source Term Analysis for LWR Severe Accident - Japanese Activities and Progress
• Development of the New Fast Running French/German Integral Code ASTEC
• Development of RBMK-1500 Models Using State-of-the-art Codes
• Experimental Analysis of FP Aerosol Behaviours in Primary Piping with ART Code During Severe Accident
• Development of Models for OECD RASPLAV Project
• R&D Needs Related to the Core Cathcer Concept Based on Corium Spreading
• Status of the ESTER Severe Accident Code System
• ESCADRE mod0 and RALOC mod2 Assessment, Major Findings and Relevance to the Safety of PWRs

  STATUS AND FUTURE DEVELOPMENT OF COMPUTER CODES FOR SEVERE ACCIDENT ANALYSIS

• LECTURE: Status and Main Uncertainities in Leading Severe Accident Analysis Codes
• LECTURE: Severe Accident Codes Status and Future Development
• LECTURE: The Concept of Advanced Simulators for Nuclear Reactor Severe Accidents

SESSION 5: Summary and Panel Discussion

Poster Session Papers

List of Participants