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Heat and Mass Transfer in Severe Nuclear Reactor Accidents

ISBN:
978-1-56700-059-7 (印刷)
978-1-56700-434-2 (オンライン)

Heat and Mass Transfer in Severe Nuclear Reactor Accidents

J. T. Rogers
Dept. of Mechanical and Aerospace Engineering, Carleton University, Ottawa, Ontario, Canada

説明

Papers and lectures from an international seminar, held from May 21 to May 26, 1995 in Cesme, Turkey, on various heat and mass transfer aspects involved in severe accidents in nuclear power reactors.



708 pages, CD, © 1996

目次:

Preface
Part 1. Overview of Severe Reactor Accidents (Impacts of TM1 and Chernobyl)
TMI-2 Vessel Investigation: Results, Conclusions and Implications for Accident Management Strategies
Safety Assurance Approach to Severe Accidents and Severe Accident Management at Nuclear Power Plants with WWER
Features of RBMK During Severe Accidents and Related Assessment Issues
Canadian Involvement in RBMK Safety Improvement Programmes
Regulatory Approaches to Severe Accident Issues: An International Perspective
Part 2. Reactor Core and Primary System Behavior and Consequences in Severe Accidents
Overview:
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 FPTO Test with ICARE 2: Bundle Degradation
ICARE2 Late Phase Degradation Models: Application to TMI-2 Accident
Source Terms - Fission Product Transport:
CEC Reinforced Concerted Action on Reactor Safety: Primary Circuit Aspects of the Source Term Project
The Release and Transport of Low Volatility Fission Products Under Severe Accident Conditions
LWR Severe Accident Source Terms:
Part I: Fission Product Release, Transport and Behavior in Core and Primary System
Part II: Fission Product Release, Transport and Behavior in the Containment
A Study of Diffusiophoretic Particle Deposition in a Steam Generator Tube in PWR Primary Circuit Using the SOPHAEROS Code
Modeling of Late Phase Phenomena:
Thermalhydraulic Behavior of a Molten Core within a Structure, Simulated by the TOLBIAC Code
Molten Pool Modeling in PWR Severe Accident Scenario Codes
Fuel-Coolant Interactions:
Corium-Water Interaction Studies in France
Escalating and Propagating Melt/Coolant Interactions in the KROTOS Experiments: Status of Knowledge
Accident Mitigation:
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
Part 3. Containment Behavior in Severe Accidents
LWR Severe Accident Source Terms: Part 2: Fission Product Release, Transport and Behavior in the Containment
Insights into Severe Accident Phenomena from Level 2 PSA.
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 Recombiners for Severe Accident Hydrogen
Experiments on Vessel Hole Ablation During Severe Accidents
Validation of Hydrodynamic Models of the RASPLAV/SPREAD Code Against the CORINE Experiments
GEYSER/TONUS: A Code for Severe Accidents Containment Atmosphere Analysis
Iodine Behavior in Containment
Part 4. Computer Modeling and Research on Heat and Mass Transfer in Severe Accidents
Overview of Severe Accident Research:
U.S. NRC Severe Accident Codes - Progress, Status and Future Direction of Modeling and Supporting Experimental Activities
Severe Accident Research Activities in Japan
Severe Accident Research Activities in Russia
Development and Application of Computer Codes for Severe Accident Analysis:
TEXAS-V: A Fuel-Coolant Interaction Model
AEA Technology Calculational Support for the CORA Early Phase Melt Progression Experiments
Parallel Computing Applied to the Modeling of the Complex Interacting Phenomena in Severe Fuel Damage Experiments
VAPEX Code for Analysis of Steam Explosions Under Severe Accidents
Accident Progression and Source Term Analyses for LWR Severe Accidents-Japanese Activities and Progress
Development of the RBMK - 1500 Models Using State-of-Art Codes
Experimental Analysis of Aerosol Behaviors in Primary Piping with ART Code During Severe Accident
R & D Needs Related to the Core Catcher Concept Based on Corium Spreading
Status of the ESTER Severe Accident Code System
ESCADRE ModO and RALOC Mod2 Assessment. Major Findings and Relevance to the Safety of LWRs
Net Heat Flux Identification Using Digitized Temperature Data in Reactor Accidents with Hot Spot Formation on Thin Wall with Variable Thermal Conductivity
Status and Future Development of Computer Codes for Severe Accident Analysis:
Status and Main Uncertainties in Leading Severe Accident Analysis Codes
Development of a Set of Codes for NPP Severe Accident Analysis
Part 5. Panel Discussion and Summary
Introduction
SUMMARY OF SESSION 1 OVERVIEW OF SEVERE ACCIDENTS IN NUCLEAR POWER PLANTS (IMPACTS OF TMI AND CHERNOBYL)
SUMMARY OF SESSION 2 REACTOR CORE AND PRIMARY SYSTEM BEHAVIOUR AND CONSEQUENCES IN SEVERE ACCIDENTS
SUMMARY OF SESSION 3 CONTAINMENT BEHAVIOUR IN SEVERE ACCIDENTS
SUMMARY OF SESSION 4 COMPUTER MODELING AND RESEARCH ON HEAT AND MASS TRANSFER IN SEVERE ACCIDENTS
Comments (G.M. Frescura)
Comments (V.G. Asmolov)
Comments (T.P. Speis)
Discussion from the Floor
Subject Index