摘要
INTRODUCTORY SESSION. OVERVIEW LECTURES A Generic Overview of Severe Accident Phenomena, H.J. Teague and D.F. Torgerson Thermalhydraulics and Activity Transport, B.H. McDonald and D.J. Wren Fission Product Transport in the Primary System, Important Phenomena, and Code Status, J.A. Gieseke, H. Jordan, and M.R. Kuhlman An Overview of Containment Fission Product Behavior and Transport Codes, W.O. Schikarski and W. Schock FUEL BEHAVIOR AND FISSION PRODUCT RELEASE Chemical Processes in Fission Product Release and Transport, D.A. Powers The Chemistry of Water Reactor Fuel, P.E. Potter Rare Earth and Actinide Release Characteristics from Solid and Molten Fuels, C.A. Alexander, J.S. Ogden, L. Chan, and S.B. Burson Matrix Isolation-Infrared Spectroscopic and Mass Spectrometric Studies of High Temperature Simulant Fission Products, A.K. Brisdon, J.S. Ogden, B.R. Bowser, and S. Dickinson Fuel Behavior and Fission Product Release under Realistic Hydrogen Conditions with Comparisons between Heva 06 Test Results and Vulcain Computations, J.M. Dumas, G. Lhiaubert, G. LeMarois, and G. Ducros Measured Release Kinetics of Iodine and Cesium from UO2 at High Temperatures under Reactor Accident Conditions, C.E.L. Hunt, F.C. Iglesias, and D.S. Cox Fission Product Release During the Air Oxidation of Irradiated Uranium Dioxide, R. Williamson and S.A. Beetham Ruthenium Release Kinetics from Uranium Oxides, F.C. Iglesias, C.E.L. Hunt, F. Garisto, and D.S. Cox Fuel Behavior and Fission Product Release under HTGR Accident Conditions, K. Fukuda, K. Hayashi, and K. Shiba Experiments on In-Vessel Core-Melt Progression, R.W. Wright Fission Product Release from Fuel Elements under Stationary and Accident Conditions, A.L. Strupzewski Source Team of Iodine and Nobel Gas Fission Products in the Fuel-to-Sheath Gap of Intact Operating Nuclear Fuel Elements, B.J. Lewis, C.E.L. Hunt, F.C. Iglesias, L.D. Macdonald, and C. Che Correlation of Recent Fission Product Release Data, T.S. Kress, R.A. Lorenz, T. Nakamura, and M.F. Osborne A Thermodynamic/Mass-Transport Model for the Release of Ruthenium from Irradiated Fuel, F. Garisto, F.C. Iglesias, and C.E.L. Hunt Influence of VVER-1000 Reactor Failure Model on Kinetics of Fission Product Release in Severe Accidents, B.E. Volkov, G.A. Volkov, N.S. Fill, A.S. Sidorov, and V.P. Spasskov TRANSPORT PHENOMENA IN THE REACTOR COOLANT SYSTEM Phenomena Occurring in the Reactor Coolant System during Severe Core Damage Accidents, A.P. Malinauskas The Effects of Phenomena not Modeled by STCP on Fission Product Transport in a PWR System Accident, P.P. Bieniarz Thermalydraulic Processes in the Reactor Coolant System of a BWR under Severe Accident Conditions, S.A. Hodge Fission Product Transport during In-Vessel Progression of PWR Severe Accidents, B.R Sehgal, A.T. Wasel, D.C. Bugby, and R.L. Ritzman SOPHIE: A Computer Code for the Prediction of Transport and Deposition of Fission Product Vapors in a PWR Primary Circuit during a Severe Core Damage Accident, C. Leuthrot Fission Product Transport in the Reactor Coolant System for a Spectrum of Interfacing System LOCA Scenarios, E.A. Warman, J. Metcalf, R. Hessian, Jr., and M. Donahue Review of the Major Predicted Phenomena during FP Transport and Deposition in the RCS and Containment Building under Severe Accident Conditions, A. Markovina, P. Fasoli-Stella, and A. Mailliat Representation of the Fission Products Behavior during Severe Accidents into a Global Experiment: Dimensioning of the Phebus F.P. Experimental Set-Up, E. Scott De Martinville and C. Hueber Modeling Aerosol Behavior in Reactor Cooling Systems, B.H. McDonald Limitations of Current Primary Circuit Aerosol Transport Codes, D.A. Williams The Suspension of Fine Particles in a Reactor Coolant System, M.W. Reeks Chemical Interactions with Primary Circuit Surfaces under Severe Reactor Accidents, C.G. Benson, B.R. Bowsher, and A.L. Nichols Metal Oxides and Hydroxides: Their Relevance to Vapor Transport in Severe Reactor Accidents, I.R. Beattie, P.J. Jones, B.R. Bowsher, A.L. Nichols, P.E. Potter, and M.H. Rand Radiation and Fission Product Transport in the RCS, D.J. Wren Experimental Studies of Degraded Core Coolability, I. Catton and N. Afgan TRANSPORT INTO CONTAINMENT Direct Containment Heating, M.L. Corradini Ex-Vessel Melt/Water Interaction, H.E. Under, M. Burger, and E.F. Hicken Resuspension of Fission Product Aerosols from the Boiling Sump, W. Schock and M. Wagner-Ambs Failure Modes of the Primary System of PWR, H. Schultz, P. Gruner, and E. Hicken BWR Reactor Vessel Bottom Head Failure Modes, S.A. Hodge CONTAINMENT TRANSPORT PHENOMENA Containment Transport Behavior: Status and Needs, T.S. Kress, E.C. Beahm, and A.L. Wright The Interface between Containment Thermal Hydraulics and Fission Product Transport, I.H. Dunbar Validation of core Debris/Concrete Interactions and Source Term Models, D.A. Powers, D.R. Bradley, J.E. Brockman, E.R. Copus, G.A. Greene, and S.B. Burson Core Debris/Concrete Interaction during a Severe Reactor Accident, H. Alsmeyer Heat Transfer in Reactor Cavity during Core-Concrete Interaction, B.Adroguer and G. Cenerino Theoretical and Experimental Investigation on Large-Scale, Long-Term Thermohydraulics Relevant to Sever Accident Conditions in Containment, L. Wolf, L. Valencia, and T. Kanzleiter The Influence of the Sensible heat Removal on the Condensation onto Aerosols inside a Light Water Reactor Containment, H.M. van Rij and V. Vonke TRENDS: A Code for Modeling Iodine Behavior in Containment during Sever Accidents, C.F. Weber, E.C. Beahm, T.S. Kress, S.R. Daish, and W.E. Shockley Effect of Radiation of Iodine Transport and Chemistry, K. Ishigure and H. Shiraishi Influence of Minor Materials on Iodine Behavior, J.-O. Liljenzin and O. Lindqvist Large-Scale Experiments on Hydrogen Distribution, T. Kanzleiter, G. Langer, and L. Valencia Heat and Mass Transfer from Bubbles Rising through Pools, F. Abbey and S.A. Ramsdale THE ACCIDENTS AT THREE MILE ISLAND AND CHERNOBYL Radioactive Releases Due to the Chernobyl Accident, S.N. Begichev, A.A. Borovoj, A.J. Gagarinsky, V.F. Demin, A.A. Khrulev, and I.L. Khodakovsky Effect of the Annealing Temperature on Escape of Metal Fission Products from Different Media (Features of Experimental Data Analysis), N.N. Ponomarev-Stepnoi and A.A. Khrulev Filtering Cooling Model for the Pile-Up in the ChAPP Accident Block, V.P. Maslov, V.P. Myanikov, and V.G. Danilov Method and Results of Aerosol Particle Size Definitions in 30-km Zone of Chernobyl Nuclear Power Plant in 1986-1987, V.I. Skitovich, A.K. Budyka, B.I. Ogorodnikov, and I.V. Petrayanov Theoretical Analysis and Numerical Modeling of Heat Transfer and Fuel Migration in Underlying Soils and Constructive Elements of Nuclear Plants during an Accident Release from the Core, R.V. Arutunjan, L.A. Bolshov, V.V. Vitukov, V.M. Goloviznin, A.M. Dykhne, V.P. Kiselev, S.V. Klementrova, I.E. Krayushkin, A.V. Chudanov, O.V. Khorushii, and A.I. Yudin