1st Edition

Fission Product Processes In Reactor Accidents

By J. T. Rogers Copyright 1990

    The Three Mile Island and Chernobyl nuclear incidents emphasized the need for the world-wide nuclear community to cooperate further and exchange the results of research in this field in the most open and effective manner. Recognizing the roles of heat and mass transfer in all aspects of fission-product behavior in sever reactor accidents, the Executive Committee of the International Centre for Heat and Mass Transfer organized a Seminar on Fission Product Transport Processes in Reactor Accidents. This book contains the eleven of the lectures and all the papers presented at the seminar along with four invited papers that were not presented and a summary of the closing session.

    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

    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

    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

    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 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

    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


    J. T. Rogers (Author) , N. Afgan (Edited by)