890 Pages
by
CRC Press
890 Pages
by
CRC Press
Also available as eBook on:
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.
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
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
Biography
J. T. Rogers (Author) , N. Afgan (Edited by)
