Fission Product Processes In Reactor Accidents: 1st Edition (Hardback) book cover

Fission Product Processes In Reactor Accidents

1st Edition

By J. T. Rogers

CRC Press

890 pages

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Hardback: 9780891168768
pub: 1990-08-01

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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.

Table of Contents


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

Subject Categories

BISAC Subject Codes/Headings:
SCIENCE / Chemistry / Industrial & Technical
SCIENCE / Energy