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TRANSACTIONSof the 5th International Conference on STRUCTURAL MECHANICS IN REACTUR TECHNOLOGY International Congress Center Berlin Berlin, Germany" 13­17 August 1979 Transaction General Editors: Thomas A. JAEGER ■ Bruno A. BOLEY Vol. A . Introduction General Contents Authors Index Conference organization by: International Association for Structural Mechanics in Reactor Technology Commission of the European Communities, Brussels ¡n cooperation with: Bundesanstalt für M aterialprüfung ( B A M ) , Berlin United States Nuclear Regulatory Commission, Washington, D. C. NORTH­HOLLAND PUBLISH ING COMPANY for THE COMMISSION OF TH E EUROPEAN COMMUNITIES PATRONAGE The 5th SMiRT Conference and its associated Pre- and PostConference Seminars are under the patronage of Dr. Guido BRUNNER Member of the Commission of the European Communities CONFERENCE ORGANISATION BY: International Association for Structural Mechanics in Reactor Technology e. V., and Commission of the European Communities, Brussels Bundesanstalt für Materialprüfung (BAM), Berlin United States Nuclear Regulatory Commission, Washington, D.C. in cooperation with: Bechtel Power Corp.. San Francisco/Los Angeles. Cal., U.S.A. Electric Power Research Institute (EPRI). Palo Alto. Cal.. U.S.A. Franklin Research Center (FRO, Philadelphia, Pa., U.S.A. Massachusetts Institute of Technology (MIT), Cambridge, U.S.A. Northwestern University, Evanston, Illinois, U.S.A. MacNeal-Schwendler Corporation, Los Angeles, Cal., U.S.A. Associated Nuclear Services. Epsom, Surrey, United Kingdom CO-SPONSORING INSTITUTIONS AND SOCIETIES American Academy of Mechanics American Nuclear Society (ANS) American Society of Civil Engineers (ASCE) American Society of Mechanical Engineers (ASME) Argonne National Laboratory, Argonne, Illinois, U.S.A. Brookhaven National Laboratory. Upton, New York, U.S.A. Canadian Nuclear Association Gesellschaft für Reaktorsicherheit mbH. Köln. Fed. Rep. Germany Lawrence Livermore Laboratory, Livermore, California. U.S.A. Office of Naval Research (ONR) Society of Engineering Science GENERAL SUPPORT Senate of the City of Berlin STRUCTURAL IN REAGTUR TECHNOLOGY Vol. A. Introduction General Contents Authors Index Lawrence C. SHAO. BOLEY. Franklin E. SMiRT-6 General Chairman Chef Département des Études Mécaniques et Thermiques. Representative Director. XII) Commission of the European Communities. Division of Reactor Safety Research. Northwestern University Evanston. Scientific Chairman and Organization Chairman Direktor und Professor. Belgium John M.S.R. D. Belgium Robert AVERY Director. Raymond K.C. Centre d'Études Nucléaires de Saclay. Department for Dissemination of Research Results. Luxembourg . Commission of the European Communities. Science and Education' (D. General Chairman. Research. Bundesanstalt für Materialprüfung D-1000 Berlin (West) 45. United States Nuclear Regulatory Commission.A. 20555. Representative Director. Directorate-General 'Scientific and Technical Information and Information Management' (DG. Washington. STALPAERT. COFFMAN Acting Director. Germany Bruno A.G. Illinois 60439. CACCIA-DOMINIONI. Directorate-General 'Scientific and Technical Information and Information Management' (D. U. Development and Nuclear Policy Directorate. Secretary of Executive Committee Head. U. Argonne.C. Argonne National Laboratory. Luxembourg.G. Belgium F. XIII) Commission of the European Communities. Reactor Analysis and Safety Division.C.E.N.C. U S A . D C . Commissariat à l'Énergie Atomique. XIII) Commission of the European Communities. Gif-sur-Yvette. Scientific Chairman and Deputy General Chairman Dean. APPLEYARD. J.S.EXECUTIVE COMMITTEE Thomas A. C. Washington. XIII) Department for Dissemination of Research Results.G. Brussels. United States Department of Energy. Brussels. Office of Fusion Energy. C. U S A . Brussels.S. 20545. Directorate-General 'Scientific and Technical Information and Information Management' (O. Illinois 60201. Jean RASTOIN. France PUBLICATION MANAGEMENT Mme. The Technological Institute. JAEGER. GIBB. U. Representative Director General.A. Directorate-General 'Research.E. Division of Development and Technology. Thomas A. BOLEY Scientific Chairmen: Tilomas A. Chairman: Bruno A. BOLEY Conference organization b y : International Association for Structural Mechanics in Reactor Technology Commission of the European Communities.TRANSACTIONS of the 5th International Conference on STRUCTURAL MECHANICS IN REACTUR TECHNOLOGY International Congress Center Berlin Berlin. Germany" 13­17 August 1979 Transaction General Editors: Thomas A. Washington. D. JAEGER Bundesanstalt für Material­ prüfung. Berlin.SA NORTH­HOLLAND PUBLISH ING COMPANY for THE COMMISSION OF TH E EUROPEAN COMMUNITIES . JAEGER Organization Chairman: Thomas A. U. JAEGER Bruno A. Brussels ¡n cooperation with: Bundesanstalt für M aterialprüfung (BAM ). Illinois. General Chairman: Dep. Germany Gen. BOLEY Northwestern University. JAEGER ■ Bruno A. Evanston. C. Berlin United States Nuclear Regulatory Commission. 1979 All rights reserved.Published by NORTH-HOLLAND PUBLISHING COMPANY — AMSTERDAM NORTH-HOLLAND PUBLISHING COMPANY — OXFORD for THE COMMISSION OF THE EUROPEAN COMMUNITIES. CEE. photocopying. 10017 North-Holland ISBN for this volume: 0 4 4 4 8 5 3 5 7 χ North-Holland ISBN for the set: 0 4 4 4 8 5 3 5 6 1 LEGAL NOTICE The Commission of the European Communities is not responsible for the use which could be made of the following information. 52 Vanderbilt Avenue New York. © Copyright CECA. recording or otherwise. or transmitted.Y. CEEA Luxembourg. No part of this publication may be reproduced. electronic. N. stored in a retrieval system. without the prior permission of the copyright owner. mechanical. .SA and Canada: ELSEVIER NORTH-HOLLAND INC. DIRECTORATE GENERAL SCIENTIFIC AND TECHNICAL INFORMATION AND INFORMATION MANAGEMENT Sole distributors for the U. in any form or by any means. JAEGER — General Chairman Bruno Α. BOLEY — S cientific Chairman 11 Topical S cope of the Conference 15 Topical Grouping of the Conference S essions 17 Table of Contents 21 Authors Index 103 .CONTENTS Foreword 7 Guido BRUNNER — Member of the Commission of the European Communities Welcome Address Dietrich STOBBE — Regierender Bürgermeister von Berlin 9 Preface Thomas A. . it is a sign of the determination of a world dependent on energy for its economic and social development to free itself from the menace of shortage which goes with reliance on conventional sources. with SMiRT­5 the series is as it were. SMiRT­5 will include in its program for the first time a division on the structural mechanics problems of fusion reactor plants. This is a reflection of the world­wide significance of the problems on which they have focussed. in a world which relies more and more on the optimal application of hardly­won knowledge it is conferences like SMiRT­5 which foster the exchange of many diverse experiences. and I should like to thank the Senate of the City of Berlin for acting as host once more. This is a sign of the times. they are also of direct relevance to nuclear safety. I am particularly glad that such issues are being discussed both thoroughly and openly. Quite generally. many of these problems are not just technological. The Conferences have throughout been truly international bringing togeth­ er participants from some 30 countries. Thus. coming home again. H^-ctô^ {_^Τ\ΑΛΛΛΛ&^~ Guido Brunner Member of the Commission of the European Communities . they are not only themselves large clubs but give rise to more and more specialized informal groups as can be seen from the present draft program.FOREWORD This International Conference on Structural Mechanics in Reactor Tech­ nology is the fifth of a series which started in 1971 in Berlin. . and I hope that your papers and seminars and discussions will provide a great deal of inspiration and impetus. I also hope that beside of your work some time will remain for you to get to know our city. consequently. concerned with problems which are of particular interest to the industrialised countries and which. The 5th International Conference on Structural Mechanics in Reactor Technology taking place here is a convention whose goals are to contribute both towards the further development of nuclear energy and towards ensuring the maximum degree of safety. From production of energy to the economic essentials of our well-being — I wish the Conference every success. Our efforts are also aimed to make Berlin even more a focus of research. It is.WELCOME ADDRESS Berlin is increasingly consolidating and extending its position as an international convention city — the International Congress Center is our contribution to this top rank. But we do not merely want to strengthen further Berlin's world-wide reputation as a place of meeting and contact. Dietrich Stobbe Regierender Bürgermeister von Berlin . affect all of us. moreover. As Governing Mayor of the City of Berlin I extend a cordial welcome to the participants of the 5th SMiRT Conference who come to Berlin from all over the world. JAEGER General Chairman .Bruno A. BOLEY Scientific Chairman 10 and Thomas A. The major problems in building today's reactors and developing tomorrow's are mechanical and structural. in the Foreword to the Proceedings of the First SMiRT Conference. but severe problems still lie ahead. We have already noted that the answer to many considerations of reactor safety undoubtedly lies within the realm of structural mechanics. not only in the area of analysis coupled with complex laws of materials. The ability to solve the structural mechanics problems encountered is of vital importance for achieving economic. Great advances have been made during the past decade. Since the basic concept of the SMiRT-Conferences did prove its vitality and adaptability to the changing needs of the field." Purpose and Scope of the Conference The biennial International Conferences on Structural Mechanics in Reactor Technology aim at bringing together engineers and scientists who are actively engaged in solving structural mechanics problems in the field of reactor technology with fundamentalists in the general field of engineering mechanics. are valid today with undiminished force: "Structural mechanics are at the very centre of nuclear technology. we should like to restate it 11 . problems which arise from a diversity of new materials used for the different reactor system components operating under severe environmental conditions and postulated loading. reliable structure that counts. of the Commission of the European Communities. because it is the safe. The rapid development of reactor technology has given rise to a multitude of problems in the area of structural mechanics. The solution of special problems of reactor technology provides one of today's most important influxes of basic enrichment and inspiration in the general field of structural mechanics. Further impetus for improved technology stems from the great emphasis that must be placed on considerations of reactor safety. Altiero Spinelli. Structural mechanics has thus been forced to develop rapidly. both applied and fundamental papers on structural mechanics problems in reactor technology are presented and discussed for the benefit of both reactor technology and of structural mechanics science.PREFACE Reactor Technology and Structural Mechanics Reactor Technology requires a synthesis of many skills. reliable and safe exploitation of nuclear power. The unprecedented combination of mechanical and structural requirements posed by reactor technology represent at one and the same time a great challenge and a great stimulus to the field of structural mechanics. Thus. here again the role of structural mechanics is paramount. but also in the related disciplines of computer methods and quality control. The words of Dr. as in the previous SMiRT Conferences. This is the usual linear dimension of topical meetings. Acknowledgements Many persons who have worked so hard in the planning and organization to make this Conference a success would deserve acknowledgement. The second dimension of this meeting extends across the boundaries of the technical fields and should initiate a cross-fertilizing of the different technological disciplines involved. The Transactions of the Conference have once again been produced by the Directorate-General for Scientific and Technical Information and Information 12 . held in London in 1975. The broad field of structural mechanics in reactor technology has been subdivided. There are. held in Berlin in 1971 and 1973. First of all. Part A): The SMiRT-Conferences have been designed for a type of multi-dimensional communication. whose individual and collective efforts have played an essential part in the shaping of the Conference programs. the 3rd SMiRT Conference. and engineering mechanics scientists from all over the world. mechanical and civil structural engineers. the specialist can communicate with experts in his own field. highlighting the present state of the field and pointing the way to possible future developments. But it is not possible here to mention all of these persons by name. Due to the truly international character of this meeting there is also a fourth dimension of communication across the boundaries of countries. SMiRT-5 includes a new division dealing with foreseeable thermal. however.from the Opening Address of the 1st SMiRT Conference (Proceedings of the 1st SMiRT-Conference. The third dimension of the Conference results from its bringing together mechanical and structural engineers with fundamental research workers in the general field of engineering mechanics. Each Division contains a Principal Lecture. held in San Francisco in 1977. 1. and is instrumental in increasing the interaction among fundamental and applied workers in this vital field. each of these has been organized by two Division Coordinators. The 5th SMiRT Conference maintains the high level of contribution from engineers and researchers from all over the world. materials engineering and structural mechanics problems of future fusion reactor power plants. and the 4th SMiRT Conference. into topical divisions. The 1st and 2nd SMiRT Conferences. Vol. In this Conference. a few people who should be mentioned individually for their outstanding work. provided a most useful meeting ground for reactor technologists. printing and distributing in time the SMiRT­5 Transactions. and to all those who have helped so much in the long months of planning. Warren Secretary to the Deputy General Chairman and to Mrs. for their unflagging support and assistance. h Thomas A. Gill of the Bundesanstalt für Materialprüfung. Berlin. the Conference organizers are grateful to Mrs. In addition. to Mrs. Kleversaat of the Department of Organization and Operation. JAEGER General Chairman S¿J\tuu> *Γ Bruno A.Management of the Commission of the European Communities. for their capable and devoted efforts at all stages of the Conference organization. and wish to extend our thanks to all authors and participants. We are sure that the present Conference will form a memorable link in the chain of SMiRT Conferences. who acted in the capacity of Publication Manager and has accomplished the monumental task of assembling. E. BOLEY Scientific Chairman 13 . Stalpaert of this Directorate­General. E. J. G. We are grateful to the several co­sponsoring and cooperating organizations and societies for their extremely important cooperation. Special thanks go to Mme. International Congress Center Berlin. who served as Secretary to the General Chairman and Scientific Chairman. Bellows.REACTOR TECHNOLOGY I REACTOR COMPONENTS Solutions for Special Problems M A T H E M A T I C A L MODELS OF M A T E R I A L S BEH AVIOR GEOMETRICAL IDEALIZATION ¡ REACTOR M A T E R I A L S IECHANICAL/THERMAL B O U N D A R Y & SOURCE CONDITIONS REACTOR CORE: NUCLEAR COMPONENTS Basic Components of Fui ■¡os REACTOR CORE: S T R U C T U R A L COMPONENTS Fuel Element Assemblies. STRUCTURAL M A T E R I A L S Metals Ceramics Concrete 8 PRACTICAL EXPERIENCE . Junctions. NUCLEAR M A T E R I A L S Metals Ceram ί α Cermeti PRIMARY COOLANT CIRCUIT STRUCTURES Piping. deformation. • for the analysis of the influence of structural characteristics on the performance and selection of major dynamic components in reactors. neutron pulses. and limit load. reactor fuel elements. design. stability. More particularly. the following topics will be covered in detail: Structural Analysis of Fission Reactor and Fusion Reactor Components The main topics of the Conference are theoretical developments and combined experimental theoretical studies: • for the analysis of stress.g.. reactor containment shells) on the basis of the theories of (thermotelasticity. • • for the analysis of stress and strain under mechanical and thermal cycling conditions (shake down and low-cycle fatigue).TOPICAL SCOPE OF THE CONFERENCE The topical scope of the Conference is outlined in the following and a graphical display of the topical scope is given on page 14. • for the dynamic structural analysis of vibrational and shock response behavior of fuel element assemblies and other reactor structures. for the analysis of crack propagation and fracture in reactor fuel elements and reactor pressure vessels. 15 . (thermo)plasticity. and limit load of all kinds of nuclear reactor components and associated equipment (e. or a combination of these indeed. The papers may be theoretical or experimental. pressure pulses. one of the aims of the Conference is to bring together results of investigations of various types towards an improved integration of technical state of the field. reactor vessels and piping. The Conference contains presentations on all aspects of engineering mechanics and nuclear (fission and fusion) reactor engineering having direct bearing on the analysis. solid moderators. induced by internal conditions (hydraulic flow. thermal shock) and general loads encountered in accident conditions. (thermo)visco-elasticity. • Mathematical-Physical Characterization of Materials Consolidation of available experimental knowledge of the behavior of reactor fuel materials by solid mechanics hypotheses related to their microstructures. reactor core support structures. for the structural mechanics analysis of first wall structures and magnet structures for future fusion reactor power plants. applied or fundamental in scope. and by external conditions such as seismic forces and ship motion. reliability and generally on the safety of power reactor mechanical and structural components and systems. • for the analysis of interactions of thermodynamic and fluid dynamics phenomena with mechanical behavior of reactor components. and engineered safeguards including containment. and fluid dynamics phenomena with interactive coupling with mechanical behavior of reactor components. and fracture mechanics of pressure vessel steels. Special topics are (e. Reliability of Mechanical Systems Probabilistic methods and statistics as applied to structural analysis and safety assessment of mechanical and structural reactor components and systems. Analysis of the interrelationship of thermal and structural design factors will be directed towards materials selection criteria concerning high-temperature materials technology in nuclear applications.Studies on influences of the micro-structure and of micromechanical changes under environmental conditions and time upon the macroscopic behavior under mechanical and thermal loading.) Design Conditions. 16 . This includes reactor internals. Computer Methods in Solid and Structural Mechanics Besides the application of analytic and numerical techniques to special problems of structural analysis of reactor components. rheological behavior laws of structural metals at high temperatures. Interaction Between Structural Mechanics Science and Practical Engineering Particular emphasis will be placed on investigations which show (1) how various theoretical analyses are actually incorporated into existing design procedures and (2) how the predictions from the various design procedures correlate with actual reactor experience. Boundary Fields Tangential areas rendering the mechanical/thermal boundary and source conditions are within the scope of the Conference: Radiation induced heat generation and heat conduction in solid bodies. Within-the scope of the topic is the specification of reasonable ways of defining. continuum models for nuclear fuel materials.g. consideration will also be given to those fundamental theoretical treatments of modern topics in engineering mechanics which are of basic potential interest for solving complex problems arising in nuclear reactor design. (This is closely related to the topic of reliability analysis of mechanical reactor components and systems. reactor vessels and primary circuit.): microstructure and mechanical properties. arriving at. Special emphasis will be on modern computer methods in solid and structural mechanics. and specifying design load conditions (operational and failure) on mechanical and structural reactor components. Β 7. Β 2. D 3. D 2. E 4. Β 8. E 6. Β 4. Structural Analysis of Reactor Fuel Elements and Assemblies Fuel Performance Analysis Pellet-Clad Interaction Effects on Clad Behavior Methods for Analysis for Pellet-Clad Interaction Thermal Reactor Subassembly Analysis Fast Reactor Subassembly Analysis Accident and Overpower Transient Analysis of Thermal Reactors Accident and Overpower Transient Analysis of Fast Reactors Energetics and Structural Dynamics in Fast Reactor Accident Analysis HCDA Containment Upper Core Structures and Coper Response Coolant Systems and Materials Response Experiments and Code Verification I Experiments and Code Verification II Core Components Response 17 . D 5. C 2. E 5. Division E. C4„. E 3. C3|. D 4. Analysis of Reactor Fuel and Cladding Materials Fuel and Fission Product Behavior I Fuel and Fission Product Behavior II Graphite Fuels Analysis Cladding Materials Behavior I Cladding Materials Behavior II Failure Criteria I Failure Criteria II C1|. Β 5. Β 3.. C3||. C1||. E 1. D 6. Division D. E 2. Β1. D 7. Β 6. D1. Thermal and Fluid/Structure Dynamics Analysis Computational Methods I Computational Methods II Computational Methods III Acoustic Methods Flow Induced Vibrations PWR Problems BWR Problems I BWR Problems II Division C.SMiRT-5 SCIENTIFIC PROGRAM TOPICAL GROUPING OF THE CONFERENCE SESSIONS Division Β. C 4. G 4. H 3. F 8. H1. F1. G 10 Division H. H 4. F 6. G 2. H 2. G 8. G 5. H 5. F 3. Division G. 18 Structural Analysis of Reactor Core and Coolant Circuit Structures Reactor Core Structures Special Problems Piping: Structural Analysi s Piping: Dynami c Analysi s Fracture Mechani cs Pipe Rupture Pipe Rupture: Methodology Components and Support Systems Heat Exchangers Structural An alysis of Steel Reactor Pressure Vessels Overviews of Integri ty Assessment Fracture Toughness Measurements Fracture Mechani cs: "Èlasto-Plastic Fracture Mechani cs: Speci al Aspects Fracture Mechani cs: Stable Crack Growth Fracture Mechani cs: Materi als Modeli ng Fracture Mechani cs: Computati on Fatigue Fracture Mechani cs: Thermal Effects Stress Analysi s Structural Engineering of Prestressed Reactor Pressure Vessels Materials Behavi or ι Materials Behavi or II Design. Research and Survei llance of PCVs Structural Analysi s of PCVs and Components Liner and Thermal Barri er Systems Concept and Research for a PCV with Hot Li ner Concept and Research for a PCIV Concept and Research for a PCV for the LMFBR . F 7. F 9. H 6. G 3. F 4. G 6.Division F. F 5. H 7. G 7. F 2. H 8. G 9. G 1. Soil-Structure Interaction II K 7. L 8. Response of Piping and Equipment I K 11. General Design Criteria and Containment Selection J 2. Ground Motion K 2. Reactor Core and Fluid Related Structures I K 12||. Loading Conditions and Structural Analysis of Reactor Containment J 1. Response of Structures K 9. Design Concepts K 5. L 2. L 12. Reactor Core and Fluid Related Structures II K 13|. Concrete Containment: Testing Behavior J 5. L 10. Seismic Response Analysis of Nuclear Power Plant Systems K 1. BWR Containment Design J 3. L 7. L4. Floor Response Analysis K 10. Risk Analysis I K 3. Structural and Leak Testing and Design of Containment Components J 7. Design and Analysis of Slabs and Structures J 6. Response of Piping and Equipment II K 12|. L 6. L 3. Dynamic Testing and Qualification I K 13ii. L 1. L 13. Underground Structures K 8. L 9. Soil-Structure Interaction K 6. Aircraft Impact Load J 10. Concrete Containment Design and Analysis J 4. Impact Load Analysis and Desiqn II J 9.Division J. Impact Load Analysis and Design I J 8. Risk Analysis II K 4. Impulsive Load Analysis and Design Division K. Status of Research in Structural and Mechanical Engineering for Nuclear Power Plants Materials Modeling and Inelastic Analysis of Metal Structures Advanced Theories I Advanced Theories II Methods I Methods II Fracture. L 5. Dynamic Testing and Qualification II Panel Session JK-P Division L. Rupture Codes and Criteria Materials Behavior Applications I Applications II Simplified Methods Damage Experiments I Experiments II . L11. Thermal. Numerical Implementation of Inelastic Material Models M 3.1 N 2.5 20 Structural Analysis of Magnets Magnet Technology First Wall Performance in Fusion Reactors Fusion Blanket Structural Analysis Materials and Plasma-Fluid Wall Interaction . Methods for Structural Analysis M 1.4 N 2. Dynamic Modeling in Seismic Analysis M 11.3 N 2.2 Engineering Concepts of Inertial Confinement and Hybrid Fusion Reactor Systems and Safety Considerations N 1. Numerical Procedures for Fracture Mechanics M 10. Computational Techniques for Plate and Shell Analysis I M 5.Division M. Computational Techniques within Finite Element Analysis II M 8. Computational Techniques within Finite Element Analysis I M 7. Probabilistic Methods in Structural Analysis M 9. Computational Techniques for Plate and Shell Analysis II M 6. Part2.Engineering Concepts and Thermo-FluidDynamics of Future Fusion Reactor Power Plants N 1. Part I.3 Thermal-Fluid Dynamics of Fusion Power Reactor Systems N. Integrated Methods of Structural Analysis M 2. Design and Simplified Methods of Analysis M 4. Materials Engineering.Structural Mechanics Problems of Fusion Power Reactors N 2.2 N 2. and Structural Mechanics Problems of Future Fusion Reactor Power Plants N.1 Engineering Concepts of Magnetic Confinement Fusion Reactor Systems N 1. Advances in Linear Boundary and Initial Value Problems Division N. Zimmermann.S. Illinois.C. Italy Β 1/4 Quasi-Eulerian Finite Element Formulation for Fluid-Structure T. P.M.B. Illinois.Y. THERMAL AND FLUID/STRUCTURE DYNAMICS ANALYSIS Session Β 1. Wang. Illinois J.. Livermore.R. Argonne National Laboratory. Illinois.M. Giuliani. Computational Methods I Β 1/1* Evaluation of Lagrangian.J. Wang. H. USA. Notes: — The sign {*) designates Invited Lectures. Lawrence Liver­ more Laboratory.SA.Y. Illinois D. Califcrnia. Chang. Donea. Argonne National Laboratory. Paul-lez-Durance. Norris. 21 . Fasoli-Stella. J. Argonne.S. U. California Institute of Technology.E. Chicago. — A title mentioned on the Table of Contents but not followed by a summary or a paper means that the paper was not available at the time of finishing of the book.R.TABLE OF CONTENTS Division Β. J.K. Hancock. Eulerian. U. San Leandro.SA. Argonne.P. S. Northwestern University.L. Arbitrary Lagrangian-Eulerian Methods for Fluid-Structure Interaction Problems in HCDA Analy­ sis Y. Liu. D.S. Hughes.K. Schoeberle. Pasadena. Physics International Company. California. U. Β 1/2 Arbitrary Lagrangian-Eulerian Finite-Element Descriptions with Particular Reference to Incompressible Viscous Flows T.A. St. P.F. U. G. Cowler. Β 1/3 An Arbitrary Lagrangian Eulerian Finite Element Procedure for Transient Dynamic Fluid-Structure Interaction Problems J. Belytschko. Graveleau.H. Argonne National La­ boratory. Jr. J.V.S. Goudreau. France An Eulerian Formulation of Fluid-Structure Interaction in Reactor Containment System C. University of Illinois at Chicago Circle. S. U. Argonne. — A paper number missing in the numeral order means that the paper was cancelled or withdrawn. C. Commission of the European Communities.A.A. A.W. CISI.A. C.L.Y. Jones. Kennedy. Gvildys. California. McMaster. Calculation of Fluid-Structure Interaction for Reactor Safety with the Cassiopee Code J. Chu. T. Louvet. Β 1 /5 Β 1/6 Β 1/7 Β 1/8 Coupled Fluid-Structure Method for Pressure Suppression Anal­ ysis W. Ispra. Evanston. Halleux./DRNR-SEDC. St. Dynamic Fluid-Structure Analysis of Shells Using the PISCES 2 DELK Computer Code M. Paul-lez-Durance.L. W. Ispra Esta­ blishment. .S .T. Illinois. Rep. Ramani.Y. Lör­ rach. Quartapelle. Computational Methods III Β 3/1 * Finite Element Solution to Transient Convective­Conductive H eat Transfer Problems J. France Β 3/2a Thermal Analysis of Guarded Penetration Assemblies in a Reactor Containment and Cooling Coil Requirements D. Inc. Goldstein. Woodbury.. M. Illinois. Germany Β 2/4 Formation of LOCA Jets and Induced Flows During Water Clearing C K Chu. Gif­sur­ Yvette. H ogge. Computational M ethods II Β 2/1 * A Three­Dimensional Finite­Element Formulation for Fluid­Struc­ ture Interaction R. Lui. Argonne. S t. Université de Liège. N.A. U. Ispra Establishment.Session Β 2. University College of S wansea.S . Raheja. TT. Patel. Fed. Y.­Paul­lez­Durance. Illinois. S DK Ingenieurunternehmen GmbH. Argonne. Argonne National Laboratory. U. Liège. Rungis­S ilic. H.N.A. Β 3/4 Spectral Decomposition in Nonlinear Transient Heat Transfer Ana­ lysis M. S. Valentin. Β 3/3 Numerical Analysis of H eat Transfer in a Fluid/Solid Coupled System C. Burns S t Roe. C. L.A. Urbana.R. Dubois.EA. Sargent and Lundy Engineers. Donea.K. Chavant. University of Illinois at Urbana­Cham­ paign. Italy Β 3/2 Thermal Analysis of the Penetrations of a LMFBR S. Fautz. Columbia University. CEA/CEN­DEMT. Illinois. U. CIS I. J. J. U.A. Giuliani. Gif­sur­Yvette.A. H uber. US A. Milano.D. Taylor. H offmann. Kraftwerk Union AG. P. Β 2/5 Calculation of the Loads Induced by Pressure Wave­Flow in Branched Piping in Interaction to Valve Closing Behavior M. Y. J. A. Rep.C. France Session Β 3. A. Argonne National Laboratory. Belgium 22 . Walker.A. Kulak.W.. Phillips. Germany Β 2/6 Reflection and Transmission of Fluid Transients at an Elbow R. H ofmann. Β 2/8 PLEXUS: A General Computer Code for Explicit Lagrangian Com­ putation C.C..E. Joly. New York. Engineering S ystems International S . H . Commission of the European Communities. S aclay. Β 2/3 Thermo­Mechanical Analysis of Depressurization A.S. Vidard. Dimopoulos. S aclay. Chicago. Cadarache. Ν.­C. Politecnico di Milano.S . Lee. J. CEA/CEN­DEMT. Gif­sur­Yvette.F. Fed.. Offenbach. Swansea.. Ispra.A. J. R. Verpeaux. . Abingdon.J. U. Engelke. Berlin. Culham Laboratory. Middle East Technical University. Dubois. Swanson. Kollmann. Β 3/7 Effectiveness of Simple Computational Schemes for Transient Temperature Distributions in Structural Components K. W.J.C. S wanson Analysis S ystems Corporation. Ankara. France Finite Element Analysis of Fluid­Structure Interaction Problems B. Fed. V. Engineering S ystem International.K.A.S . NOVATOME Industries. S aclay. Gesellschaft für Reaktorsicherheit. Leimbach.­R. 23 .S . Illinois. Argonne. H. Kraftwerk Union AG. Osterie.A. Le Plessis Robinson. Descleve. Gantayat.A. J. Forkel. Livolant. Argonne National Laboratory. Jeanpierre.U.Y.K.A. New York. Muller. Germany Β 3/8 A Finite Element Model for Fluid­Structure Interaction Studies A. Liebecq.Ch. Fed. Technische Universität Berlin.Β 3/5 A General Formulation of the Isotherm Migration Method for Reac­ tor Accident Analysis B. Β 3/9 Difference Analysis for Fluid­Structure Interaction E. G.A. J. H offmann. Leonard. Gif­sur­Yvette.N. Ger­ many Β 3/10 Theoretical and Experimental Study of the Unsteady Flow Through Perforated Structures J. Akkas. Engineering Decision Analysis Company. Belgium. Columbia University. Pennsylvania. U. Yilmaz. N. Germany Analyses of the Dynamic Behavior of Nuclear Power Reactor Com­ ponents Containing Fluid F. Acoustic M ethods Β 4/1 * Β 4/2 Β 4/3 Β 4/4 Β 4/5 Β 4/6 Description of a General Method to Compute the Fluid­ Structure Interaction F. Oxon.D.H. Giencke. Turland. Illinois. CEA/CEAV­ DEMT. N. U. Illinois Institute of Technology. Holtbecker. J. Ispra. Von Karman Institute for Fluid Dynamics. Palo Alto.R. M. Ahmed. Rhode­St­Genèse. Rep.W. Bochum­Linden. Gar­ ching. Fluid Element in SAP IV C. Rep. W. H. Italy Session Β 4. U. Houston. M. France Development and Verification of Fluid Finite Elements for the Eva­ luation of Structure Fluid Interaction Effects A. California.. Offenbach. Tur­ key Application of ANSYS Fluid Elements in Fluid­Structural Inter­ action Problems J. Consultant.A. Smolderen. R. A. Nahavandi.S. Rungis­S ilic. U. Commission of the European Communities. Chicago.N.E. Ispra Establishment. Gibert. Tokyo. Kalnins. Chatou. U. University of Ottawa. Japan B 5/10 Effective Mass and Damping of Submerged Structures R. R. Gif­sur­Yvette. USA.J. ANAMET Laboratories.A.Tang. 24 . Bethlehem. Weppelink. Citerley. E. Lehigh University.L. Electric Power Research Institute. Calculation and Tests on Fluid­Elastic Interaction between a Cylin­ drical Shell and a Liquid Sheet with Parallel Flow F. Hara. France withdrawn Flow­Induced Vibration and Instability of an Elastic Pipe Structure E.H . Session Β 5. van der H oogt. Ottawa. Pennsylvania. U. NASA Ames Research Center. Electricité de France. Β 4/9 A New Method for Analyzing Fluid­Structure Interaction Using MSC/NASTRAN R.S. Purdue University. Canada Three­Dimensional Calculation of the Coupled Vibrations of a Group of Circular Tubes in an Unconfined Liquid H.A. Montreal. Koninklijke Machinefabriek S tork B. California.A. S aclay.N. U. Moffett Field. Direction des Etudes et Recher­ ches. Canada Fluid­Structure Interaction of Submerged Structures H. France A Theoretical Analysis of Two­Phase Flow/Fuel Pin Structural Dynamical Interactions F. M.C. CEA/CEN­DEMT.B.G. University of Texas at Austin.H. Flow Induced Vibrations Β 5/1 Β 5/2 Β 5/3 Β 5/4 Β 5/5 Β 5/6 B 5/7 B 5/9 A Comprehensive Analytical Approach to the Free and Forced Vi­ bration Analysis of Large Steam Generator U­Tubes D. Paidoussis.V. Quebec. Axisa. Gorman. Becker. Hengelo (O). The MacNeal­Schwendler Corporation. Tokyo University of S cience. MacNeal. California. Los Ange­ les. D.. Palo Alto.Β 4/8 Vibration of Liquid­Filled Thin Shells A. Gibert. Känning. Te­ xas.S.S. Enschede. The Netherlands Dynamics of Fuel­Element Bundles in Axial Flow MP. California. Taylor. L. Ting. Chargin.M.T.S. Twente University of Technolo­ gy. R.J. McGill University. S an Carlos. P. Austin. California. Vibration Study of a Tube Bank in Liquid Cross Flow F. J. California. In­ diana. West­Lafayette. Lawrence Livermore Laboratory. van Campen. Remy. Dong.J.M. Livermore.A. U. Commission of the European Communities. Fed. F. Italy Β 6/4 Analysis of the RS16B Experiment on Fluid­Structure Interactions During PWR Blowdown U. E. Germany Β 6/6 Β 6/7 Coupled Fluid­Structure Analysis of the Core Barrel Behaviour Dur­ ing Blowdown F. Katz. Kernforschungszentrum Karlsruhe. Verbiese. Babcock & Wilcox Co. Rep.G. U. G. Krieg.F. Fed. Los Ala­ mos S cientific Laboratory.S. PWR Problems Β 6/1* Fluid­Structure Interactions in PWR Vessels during Blowdown ­ Code Development at Karlsruhe and Results U. Kernforschungszentrum Karlsruhe.Β 5/11 Experimental Investigation of Pressure Field Characteristics Ar­ ound Rods and Pipes in Parallel Flow R.G. J.D. Fed. B. Jiyavan.C. U. R. Enderle. van Goethem. C. Ram. Mösinger. Kernforschungszentrum Karlsruhe. India Β 5/13 An Experimental Vibration Study of In­Air and Fluid Coupled Co­ Axial Cylinders M. Ludwig. M. Karlsruhe. Analytical Integration of the Cylindrical Shell Equations A. E.A. Β 6/3 MEL Finite Element Analysis of Water­Shell Interactions in the Context of a PWR­LOCA S.W. Ohio. Ohio.R. Kanpur.S. Akron. Brown. Ispra Establishment. Schlechtendahl. Rep. Fed.C. Barberton. Schlechtendahl. Kernforschungszentrum Karlsruhe. Germany Calculations on the H DR Core Barrel Response During Snap­ back Tests A. New Mexico. Belgium. Schumann. Dienes. Nuclear Equipment Division. Germany Β 6/5 Dynamic Behavior of a PWR­Core Barrel.S. Brussels University. G. Schumann. Hirt. Rep. Rivard. H . Los Alamos. Indian Institute of Technology. L. Α. Germany Β 6/2 H ydroelastic Effects of a Loss of Coolant in a Pressurized Water Reactor J. Stein. Ispra.K. Torrey. S.. K. Ludwig. U. J. Ludwig. W. University of Akron. Sahay. Chu. Karlsruhe. Brussels. Karlsruhe. Fed. Karlsruhe.A. Katz. Kernforschungszentrum Karlsruhe. Rep. Lestingi. Rep. Germany 25 .R. Schumann. Session Β 6.J. Karlsruhe. 26 . Germany Β 7/2 H ydroelastic Phenomena in Boiling Water Reactor Suppression Pools B. New Mexico.D. Antony­Spies.. Los Ala­ mos. Woodbury.Session Β 7. J. Berlin. Kraftwerk Union AG. C. US A. Giencke. Inc. U. Rep.M. Offenbach. Technische Universität Berlin. Los Alamos Scientific Laboratory.W. Ray mont. Ger­ many Β 7/4 Suppression Pool Transients in BWRs Under LOCA and SRV Con­ ditions C K Chu. Hirt. Fed. Β 7/3 Fluid Structure Interaction in the Pool of Pressure Suppression Systems Containing Oscillating Bubbles P.S. Burns & Roe. BWR Problems I Β 7/1* Pressure Distribution due to Steam Bubble Collapse in a BWR Suppression Chamber E. New York.A. Nichols. Edwards. Shah.A. U. Karls­ ruhe. Applicability of Flat Plate Methods in Determining Fluid/Struc­ ture Interaction Effects in BWR Pressure Suppression Sys­ tems G. San Jose. Michail.S . US A. Germany Unconventional Dynamic Behaviour of Thin Spherical Contain­ ment Shells. E. Rep. California. BWR Problems li Β 8/1 * Analytical and Experimental Mark I Boiling Water Reactor Containment Safety Research at the Lawrence Livermore Labo­ ratory E. Lu. Holman. Gol 1er. Fed. Karlsruhe. Helsinki.W. S. Arros. U. A Semi­analytical Description B. S an Francisco. Inc.Session Β 8. Germany Coupled Vibrations of a Structure and Fluid Excited by Pressure Shocks J. withdrawn Practical Application of Current Fluid/Structure Interaction Technology to the Design and Analysis to BWR Containment Vessels N. Göller. McCauley. Finland Structural Analysis Study of Fluid­Structure Interaction Effects in BWR Mark II Reinforced Concrete Containment M.S . Technical Research Centre of Finland.W. Rep. Livermore. Fed. G. Cali­ fornia.S. G.H. 27 . NUTECH. California. Bechtel Power Corporation.A. H ailfinger. Krieg. Krieg. California. Lawrence Livermore La­ boratory. Fed. Livermore. McCauley.C.S . Karlsruhe.A.W. Hailfinger. U. Rep. Lawrence Livermore Laboratory. G. Kernforschungszentrum Karls­ ruhe. Β 8/2* Β 8/3 Β 8/4 Β 8/5 Β 8/6 Β 8/7 Β 8/8 Description of Internal Flow Problems by a Boundary Integral Me­ thod with Dipole Panels R. Germany Coupled Fluid Structural Analysis for a Spherical BWR Contain­ ment with Pressure Suppression System R. Kernforschungszentrum Karlsruhe. Β.. Kernforschungszentrum Karlsruhe. U.P. University of California. Y. Electricité de France.M. Los Angeles. Fuel and Fission Product Behavior I C 1 /1 * Behaviour of Fission Products in PWR Primary Coolant and Defected Fuel Rods Evaluation P. Japan Session C 1„. Takeuti. Belgonucléaire.A. A.. Sakai.N. University of California.A. Rest. Atomic Energy of Canada Ltd.Ghoniem.J.M. University of Osaka Prefecture. Los Angeles. Brussels. Unsteady Thermal Stresses in an Orthotropic Composite Disk Due to Asymmetrical Heating Y. California. Sakai. Karlsruhe.R. Hamamatsu Y.Okrent. Chalk River Nuclear Laboratories. Billaux. University of Osaka Prefecture. Argonne National Laboratory. Bourgeois. Fed.F.M. Stora. Hastings. Ontario.. J. Okrent.Griesmeyer. Osaka. Germany M. ANALYSIS OF REACTOR FUEL AND CLADDING MATERIALS Session C 1. Fuel and Fission Product Behavior II C 1/6 C Ml C 1 /8 The Mechanistic Prediction of Fission-Gas Behavior During Inceli Transient Heating Tests on LWR Fuel Using the Grass-SST and Fastgrass Computer Codes J. Rep. — A title. 28 . Gehl. Kuczera. Canada C 1/4 Intragranular Fission Gas Behavior During a Slow Thermal Transient W. Shizuoka University. Osaka. Notley. — A pc per number missing in the numeral order means that the paper was cancelled or withdrawn. mentioned on the Table of Contents but not followed by a summary or a paper means that the oaper was not available at the time of finishing of the book.S. C 1/3 Prediction of Fission Gas Release from High Burnup Oxide Fuel I.S. S. C 1/5 Three-Dimensional Unsteady Thermal Stresses in a Finite Circular Cylinder N. Illinois. Paris. Argonne. Wazzan. Kernforschungszentrum Karlsruhe. D. Japan Modelling of Transient Pre-Failure Fuel Relocation for LMFBR Accident Analysis B. Steele. U. Tour EDF-GDF. M. California. Belgium Notes: — The sign (·) designates Invited Lectures. Noda.TABLE OF CONTENTS Division C.D. Tanigawa. Chalk River. France C 1/2 A Model for the Dynamic Intragranular Fission Gas Swelling and Release J. Takeuti.J. Commission of the European Communities.-L. Rep. INJERATOM. C 1/10 Prediction of Thermal. Willaschek. France Session C 2. Fed. Rep. O'Connor. Wazzan.. Germany Residual Stress. Gehr. U. Graphite Fuels Analysis C 2/1* C 2/2 C 2/3 C 2/4 C 2/5 C 2/6 Experimental Verification of Stress Model Calculations for HTR Fuel Particles M. and Fission Gas Behavior of Carbide Fuel Element During Fast Thermal Transients Using the UNCLE-TUBE Code Y. Research Center Petten. Ting. Rep. Hanau. G.. Fed. EG. M.A. D. Saurwein. Idaho. Germany Session C 3. University of California. Germany Stress Performance Calculations as a Guide for Layout and Testing of Coated Fuel Particles for HTRs K. Los Angeles. J. Millet. Jülich.D.S. Rep.R. Irradiation Experiment with a Large Graphite Block H. Fed. Senski. California.S^ Olsen. Bergisch Gladbach. Okrent. Cords. Kernforschungsanlage Jülich. A. C. Germany 29 . California. Rep. U. Petten. A. Germany P. Krautwasser. Kraftwerk Union AG. Bongartz. Robert.-W. Kleist. Mechanical. and Strength Measurements in Peach Bottom Fuel Test Elements CF. J. Inc. Kunick. Rep. Languille.M. Jülich. Wallroth. Jülich. Jülich. Idaho Falls. Bergisch Gladbach. HOBEG mbH.J. Erlangen. Strain. P. Fed. P. INTERATOM. Kernforschungsanlage Jülich. The Netherlands A 3-D Inelastic Analysis of HTR Graphite Structures and a Comparison with a 2-D Approach J. A. A. Kernforschungsanlage Jülich. Cladding Materials Behavior I C 3/3 A Phenomenological Thermal and Irradiation Creep Model for Zircaloy G. Saint-Paul-lez-Durance.S. Miller. U.C 1/9 UO5 Pore Migration and Grain Growth Kinetics C. Idaho. San Diego. Kernforschungsanlage Jülich. Herren. C 1/11 Behaviour of Fast Fuel Bundles under Irradiation G.S. K.&G. Fed. Mehner. CEA/CEN-Cadarache.A. Bongartz. Marbach. Zeisser. General Atomic Company.A. Germany Statistical Methods for Predicting Failure Probability of Coated Particles H. Fed. . Trombay. Kraftwerk Union AG. University of Florida. Bombay.K. Kim. G. S pringfields Nuclear Power Development Laboratories. Leridon. Gittus. Geesthacht­Tesperhude. Session C 4. G. Springfields. Α.A. Η. U.S.J.D. Trombay. S. Lynchburg. A.S. U.H.S.A. Gaines­ ville.S. Anantharaman.S. Anand. University of Manitoba.F. Bhabha Atomic Research Centre.A. Sawhney. Canada Tensile Properties of Zircaloy­4 and 304 Stainless Steel at Constant True Strain­Rates OS. Lee. France A Cumulative Damage Fraction Design Approach for LMFBR Me­ tallic Fuel Elements D. India COMTA­A Computer Code for Fuel Mechanical and Thermal Ana­ lysis S. Hanford Engineering Development Laboratory.K. Bates. D. Rich­ land. A. H su. Reymann. Sa/wick. Washington. J. India On Slow Crack Growth in Fuel Cladding by Finite Element Analysis T. S aint­Paul­lez­Dur­ ance. CEA­CEN Cadarache. Babcock & Wilcox Company. Murty. Sawhney. Idaho. Senski. Illinois R.E.A. Mehta. Yoon. H artley. .K.L.K. Gartner. Argonne. Bombay. Jenkins. Winnipeg. Manitoba.K. Argonne National Laboratory. K. S. Einziger. S. Anand.C 3/5 C 3/6 First Results of Cladding Tube Creep Experiments in FRG­2 M. Kaspar.A. UK. U. Preston.R. Basu. Florida. Hudman. G. Erlangen. Wilhelm. Session C 3„. UKAEA. CDA­A Computer Code for Analysis of BWR Fuel Channel Deflec­ tion S. Basu. U. Gesellschaft für Kernenergieverwertung in Schiffbau und Schiffahrt. Bhabha Atomic Research Centre. Virginia. Idaho Falls. Fed. Mehta. Johnson. K. A Relationship Between Swelling and the Shear Modulus of Irra­ diated Metal J.L. Germany Prediction of Creep Transients in Zircaloy Fuel Cladding Using Anelastic Strain Model K.J. Cladding M aterials Behavior II C 3/8 C 3/9 C 3/10 C 3/11 C 3/12 C 3/13 Analysis of Reactor Fuel: Failure Criteria J. S. O Pauwels. Y.S. Argonne National Laboratory. Rep. Failure Criteria I C 4/2 C 4/3 30 Plastic Instability of Zircaloy Cladding Submitted to LOCA Condi­ tions A. F.K. Marchwood. Rolstad. J.S. A. Pinawa. Denmark Crack Propagation in a Fuel Cladding with a Local Bulging Caused by Internal Pressure A. CEGB. Risø National Laboratory. Atomic Energy of Canada Ltd.M. Too. Misfeldt. Joint Manchester University/UMIST Metallurgy Department. Canada 31 .J. Manitoba.J. Seattle. U. Whiteshell Nuclear Research Establishment. Washington. Marchwood Engineering Laboratories. University of Washington. Roskilde. withdrawn C 4/12 Modelling the Thermal Mechanical Behaviour of a Fuel Pin due to Oxidation Effects J. Williams. Kobayashi.C 4/4 C 4/5 C 4/7 C 4/8 The Stress for the Formation of a Cladding Crack During a Power Ramp E. U. Manchester.K.C.. Scandpower.S. V. Southampton. Failure Criteria II C 4/11 The Effects of Defects on the Failure of Tubes M. Emery. Coleman. Love. Norway Failure Criteria for the Probabilistic Fuel Performance Code FRP lb. W. Session C 4„.A.J. U. Smith. PCI Optimized Reactor Operation by Application of the Fuel Failure Code POSHO E. Luthra.A. Halden. Rigby.P.R. Kraftwerk Union AG. Karlsruhe. Kernforschungszentrum Karlsruhe. Roskilde. Savino. Fuel Performance Analysis D 1 /1 * Interaction between Thermal and Structural Behavior in FBR Fuel Pins B. Stephen. Japan D 1/5 WAFER-3. Saint-Paul-lez-Durance. Saint-Paul-lez-Durance.TABLE OF CONTENTS Division D.. Omiya. Rep. Y. Fed. Fuchs.L.Fuel Pin Mechanical and Thermal Behaviour Code C. — A title mentioned on the Table of Contents but not followed by a summary or a paper means that the paper was not available at lhe time of finishing of the book. E. — A paper number missing in the numeral order means that the paper was cancelled or withdrawn. Brzoska. Courtois. Comisión Nacional de Energia Atòmica. Rep. Buenos Aires. Argentina D 1/4 The FROST Code for Predicting In-Reactor Behaviours of LWR Fuel Rod H. Schankula. Nuno.H. Coroli. J. Inc. Denmark D 1/7 Heat Transfer Analysis of an Eccentric Fuel/Sheath Geometry Using the Finite Element Method G. H. Patel. Harriague. Advanced Reactor Systems Department. California. Truffert. R. M. 32 .L. Pinawa. Manitoba. Risø National Laboratory. D 1/2 The BACO Fuel Rod Analysis Computer Program S. Saitama. France D 1/9 VERDON . F. CEA/CEN-Cadarache. G. USA. Garzarolli.. An Extended Version for High-speed Analysis of Rods with an Axial Power Profile N. Germany Notes: — The sign (·) designates Invited Lectures. Mizuta. Sunnyvale. Fed. Weimar. M. Harbourne. Pu)C-Fuel Pins Irradiated in the Thermal Flux of FR 2 P. Truffert. Germany Post Irradiation Examination and Analysis of 13 (U. H. Irisa. Pellet-Clad Interaction Effects on Clad Behavior D 2/1 D 2/2 Influence of Pellet-Clad-Gap-Size on LWR Fuel Rod Performance B. Manzel. Kjaer-Pedersen. Mitsubishi Atomic Power Industries. CEA/CEN-Cadarache. France Session D 2. STRUCTURAL ANALYSIS OF REACTOR FUEL ELEMENTS AND ASSEMBLIES Session D 1. Erlangen. J. Atomic Energy of Canada Limited. General Electric Co. Steiner.D. Canada D 1/8 Fuel Pins In-Pile Reliability and End-of-Life Failure Probability Estimate J.J. Whiteshell Nuclear Research Establishment. M. M. Heeb.S. U. U. Manchester. G. Connecticut. Darling. LaVake. Fiero. P.S. Rep.J. I. Fed. B.E. Skerget. U. Darling. Lassmann. University of Ljubljana. Peehs.K.K.S. Smith. Stanford University. Washington. Iowa State University. Toshiba Research and Development Center. U. Institut Jozef Stefan. The Fuel-Cladding Interfacial Friction Coefficient in WaterCooled Reactor Fuel Rods E. Vogl. J. Joint Manchester University/UMIST Metallurgy Department. Nuclear Engineering Department. Kanagawa. Failure Analysis Associates. Fed.. A. Ranjan. Karlsruhe. Connecticut. D 3/4 Finite Element Pellet-Clad Interaction Model A.A. Kraftwerk Union AG. Richland. University of Maribor. IB. U. USA. Hering. P. U. Connecticut. Stanford. Yugoslavia 33 .A.N. withdrawn Sensitivity of Power Ramp Induced Cladding Stress and Strain Concentrations to Modelling Assumptions W. California. Miller.B. Germany D 3/2 Theoretical and Experimental Analyses of Cladding Strain Produced by Expansion of Cracked Fuel Pellets M. Ames. Rep. Department of Nuclear Engineering. Erlangen. Germany. Scott. Germany.. Ma. Stress Distributions in Fuel Element Cladding During Pellet-Clad Interaction R. Sakuyama. Combustion Engineering.. C M . Alujevic.S.A. Maribor. Transient Pellet-Cladding Interaction of LWR Fuel Rod B. Windsor. Hering.D 2/3 D 2/4 D 2/5 D 2/6 D 2/7 D2/8 Pellet-Cladding Mechanical Operating Failure Limits and Inferred Strain Thresholds C L Mohr. RS. Methods for Analysis for Pellet-Clad Interaction D 3/1 * The Structure of Fuel Element Codes K. Kawasaki-City. Japan D 3/3 Stresses and Strains at Zircaloy Cladding Ridges G.S. Combustion Engineering Inc. Windsor. Pankaskie. Windsor. W. Toshiba Corporation. Palo Alto. M. Session D 3. Brooks. California. Batteile Pacific Northwest Laboratories. Rep. Fed. Tokyo. Inc. Kernforschungszentrum Karlsruhe. Fiero. Combustion Engineering Inc.M. Analysis of Mechanical and Chemical Pellet-Clad Interaction During Power Ramps W.A. Kraftwerk Union AG. Cernej.S.A.V. Erlangen. Nakatsuka. Iowa. T. A Model for Fuel Rod and Tie Rod Elongations in Boiling Water Reactor Fuel Bundles K. Fed.S. Rustagi. Chicago. Germany Effect of Material Properties on Pellet-Clad Interaction Pressure S.D. Colaba. Liu.T. S.Tang. India An Assessment of Loading Effects on Magnox Fuel Elements in Transport Accidents H.A. R.B. Berkeley.K. Ramani.E. Palo Alto. Sargent & Lundy Engineers. Combustion Engineering. Chhatre. Argonne. Whitehead. withdrawn . Calif. Argonne National Laboratory.G. Müller-Lyda..R.R. Kalpakkam. Washington. Grover. Kernforschungszentrum Karlsruhe. Cambridge. India Fracture Mechanics Method of Evaluating Failures in PelletCladding Interaction Analysis D.T. U.S. Das. Argonne. Illinois. A Model for the Description of the Fuel-Cladding Mechanical Interaction in Fast Breeder Reactor Fuel Pins I.S. S. Meyer. Fisher. A. Windsor. Merckx.D 3/5 D 3/6 D 3/7 D 3/8 A Formulation for the Analysis of Pellet-Cladding Mechanical Interaction Y.A. India Analysis of Colliding Vibration of Two Cylinders A. Inc. Kakodkar. CEGB Berkeley Nuclear Laboratories. S. Connecticut. Department of Atomic Energy.P. Inc. Illinois. U. Bhoje. Massachusetts Institute of Technology.S. U. U. Ghosh. Bombay. Fuel Bundle End Plate Analysis by Code SPACE A. Bhabha Atomic Research Centre. Rep. Reactor Research Centre.Y. Electric Power Research Institute. Dowler..A. Bombay.A.A. U. R. Richland. Illinois. Session D 4. Wu. Massachusetts. Karlsruhe. Argon.S.J. A. Inc.S. Effects of Gap Sizes on Stresses and Deflections of a Fuel Element T.S. Exxon Nuclear Company. Nonlinear Asymmetric Load Deflection Characteristics of a Reactor Fuel Bundle H.S. Power Projects Engineering Division. Thermal Reactor Subassembly Analysis D 4/1 D 4/3 D 4/4 D 4/5 D 4/6 D 4/7 D 4/8 34 A Model for Creep and Relaxation Consideration in a Fuel Rod Assembly H. M. Trombay. Argonne National Laboratory. U. J.S. U.K.K.. A. Gloucestershire. Paranjpe.A. Bir Singh. Bhardwaj. J. Richland. P.. Govindarajan. Belgonuc/éaire.E. Perrin.A. St.A.S. CEA/CEN-Cadarache DRNR. R. S.-Paul-lez-Durance. Cheshire. Belgium An Analytical Study of the Dilation of Fast Reactor Fuel Assembly Ducts D.Session D 5. Mamoun. U. Illinois. Bergisch Gladbach. Risley Nuclear Power Development Establishment. External Pressure of Coolant. Sandia Laboratories. Tami/nadu. La Jolla. D 5/6 Bowing and Interaction Model for Sub-Assemblies in a Fast Reactor Core S. UK. 35 . T.K. Illinois. Miki.N. Bir Singh.G. Warrington.S. Jackson. Accident and Overpower Transient Analysis of Thermal Reactors D 6/1 * Strain-Rate Dependent Plasticity in Thermo-Mechanical Transient Analysis Y. India D 5/7 Calculation of Equilibrium Configurations of a Hexagonal Array of Deformed Subassemblies A.P. France D 5/8 Elastic Plastic Analysis of Fuel Element Assemblies-Hexagonal Claddings and Fuel Rods: Effects of Thermal Bowing of Fuel Rods. S. Argonne. USA. USA. Wu. Bernard. D 5/3 D 5/5 The Restrained Core Modelling Program CRAMP R. Chicago. New Mexico.B.S. Sharabi. INTERATOM. Risley. Pennsylvania. Bhoje. U.V. Institute of Gas Technology. Westinghouse Advanced Reactors Division. Washington.J. U.. M. Hitachi Ltd.S. Japan D 5/10 Some Fundamental Principles of Voidage Induced Bowing of Fuel Pins in Subassemblies R. Anderson. Fast Reactor Subassembly Analysis D 5/1* Structural Evaluation of Fast Reactor Core Restraint with Irradiation Creep-Swelling Opposition Effects J. Energy Research Laboratory. AERE Harwell. Bruxelles.A.. Kalinowski. Chan. D. Session D 6.R. Argonne National Laboratory. D 5/9 BEACON: A Three-Dimensional Structural Analysis Code for Bowing History of Fast Breeder Reactor Cores K. Ibaragi.K. B. D. ANATECH International Corp. Swenson. Rep.E. Fed. Germany. Kalpakkam. California. Westinghouse Hanford Company. Didcot. U. and Elevated Temperatures M. Albuquerque. Reactor Research Centre.C. Chopra. Madison.A. Többe.M. Kazimierzak. H. D 5/2 Rules for Structural Design of LMFBR Core Subassemblies H.C Rardin. Meyer zur Capeilen. Rashid. Pedersen. Washington. Eggen: DSN/SES.L. T. D 7/2 Modeling of Fast Reactor Cladding Failure for Hypothetical Accident Transient Analysis J.A. Rowe and Associates. A. Palo Alto. Bellevue. Battelle Pacific Northwest Laboratories.W. Cadarache. U. N. W. Indiana. Washington. Ariman. . U.R. Imperial College of Science and Technology.M. A Simplified Method of Computing Clad and Fuel. Hellenberg. Argonne National Laboratory. Illinois. Notre Dame. F. U. U.E. U.A.J.S. Accident and Overpower Transient Analysis of Fast Reactors D 7/1 * Bridging the Gap between Whole Core Accident and Fuel Behaviour Codes J.California. R. L.R. F-I3115 St Paul-lez-Durance.W.R. Kramer. London. Mohr. Evanston.E. Head. University of California. Richland. D 7/3 Fuel Deformation in a Loss-of-Flow Accident in the Gas-Cooled Fast Breeder Reactor T. Northwestern University. Washington.K. Rowe. W. Illinois. R. Harwell. Palo Alto. Kuzay. Frank.S.M. Deitrich. Sensitivity of Fuel Rods Material Properties to Hypothetical PWR LOCA R. Battelle Pacific Northwest Laboratories. California. U. Argonne Illinois.N. Lanning.V. Wilson. C.S. Oehlberg. Argonne.J. U. W. D.A.S. Hughes. Argonne National Laboratory.H. University of Notre Dame.E. U. Stress and Strain During an Overpower Transient M. Eggen. J. Los Alamos Scientific Laboratory.Thermal-3: A Technique for Evaluating Transient Gap Conductance and Stored Energy O L Mohr.D. current address — Wehner: Energy Division.S.H. Matthews.E. Wehner. Panisko. GAPCON . Thermohydraulic and Thermal Stress Aspects of a Porous Blockage in an LMFBR Fuel Assembly T. U.M. Session D 7.A. USA. D.S. Los Alamos. Electric Power Research Institute. Electric Power Research Institute. T. France D 7/4 D 7/6 36 87545. Didcot.D 6/2 D 6/3 D 6/4 D 6/5 D 6/6 Characterization of Transient Deformation of Zircaloy Fuel Cladding for LOCA Conditions OL.T. USA. Kastenberg.E.S. Analytical Model for Transient Gas Flow in Nuclear Fuel Rods R.R. DiMelfi. Richland.A.K.SA. D. D. Marr.E. Los Angeles. California. Oehlberg. Fuel Pin Response to an Overpower Transient in an LMFBR A. Grosberg.A. Cheshire. Argonne National Laboratory. ENERGETICS AND STRUCTURAL DYNAM ICS IN FAST REACTOR ACCIDENT ANALYSIS Session E 1. Delaval. Italy E 1 /6 Behaviour of Pressure Wavesand Fragments after Vessel Rupture Calculated with the PISCES™­2 DELK­Code H. California.K.C. Ispra Establishment. Cagliostro.J. Dorset. R. Fed. Argonne National Laboratory. E 1 /4 ALICE ­ An Arbitrary Lagrangian­Eulerian Code for Analyzing FBR Containment Response to H CDA H. Argonne. Chu. Ispra. Pottinger.K. U. V. U.Y. Ispra Establishment. E 1/5 A Comparison of Rezoning Techniques for Lagrangian LMFBR Containment Codes M. Notes: — The sign (·) designates Invited Lectures.F. A. Brown. Commission of the European Communities. AEE Winfrith. Pohl. Illinois. — A title mentiored on the Table of Contents but not followed by a summary or a paper means that the paper was not available at the time of finishing of the book.S . Warrington.E. Control Data GmbH. Italy E 1/2* Three­Dimensional Fluid­Structure Interaction Dynamics of a Pool­Reactor In­Tank Component R. U. Boverie & Cie.M.A. J. Southend­on­Sea.A. Frankfurt/Main. U. D. 37 . UKAEA. Argonne. Atomic Weapons Research Establishment. Ispra. — A paper number missing in the numeral order means that the paper was cancelled or withdrawn. Rep. Essex.. Northern Division.R. S RI International. US A. U. Schürkamp. W.TABLE OF CONTENTS Division E.S. Illinois. Yerkess. Menlo Park. Kulak. Risley.A.. Washby. Some Bounding Analyses C M . Leigh. E 1/3 Potential Missiles from LMFBR Vessels During an H CDA. Staniforth. J. Dorchester.C.K. Romander. Commission of the European Communities.R.A. HCDA Containment E 1/1* The Computer Code SEURBNUK­2: Recent Developments R. Germany E 1Π Experimental and Associated Theoretical Studies of the Response of Reactor Structures to H ypothetical Core Disruptive Accident Loadings K. MOD(PE). Mannheim. U. IB. Argonne National Laboratory. de Rouvray.T. Illinois.Y. Analysis of a Bubble Growth (HCDA) in a Fluid Inside a Primary Containment with Internals J.S. Engineering System International.A-Moneim. Upper Core Structures and Cover Response E 2/1* E 2/2 E 2/3 E 2/4 E 2/5 E 2/6 Energetics of LMFBR Core Disruptive Accidents J. Argonne National Laboratory. M.H. Argonne. Tessier.K. U. J.H.S. Zeuch. Pai. Chang. Argonne National Laboratory.F.R. Argonne National Laboratory. Evanston. Kamal. Italy Session E 3. Ispra Establishment.S. Validation of a Cavitation Model and its Appi ¡cation to Containment Loading Experiments A.A-Moneim. Morris. U.C. Argonne. Livingston. U. Chern. Argonne. Ragland.A. Illinois. Marchaterre.SA. Belytschko. Ispra Establishment. Ispra.A. Indiana. M. Montagnani. Illinois T. Albertini. Argonne. Argonne National Laboratory. Illinois. Argonne National Laboratory. J. Illinois.W. Foster Wheeler Energy Corporation.S.Session E 2.C. Belytschko. Coupled Hydrodynamic-Structural Analysis of an Integral Flowing Sodium Test Loop in the TREAT Reactor W.S. Commission of the European Communities. Kennedy.L. J.T. Notre Dame.A.A. Argonne. Illinois. USA.R. France Characterization of Dynamic Loads on the LMFBR Rotating Shield E.Wang. Illinois. Structural and Coupling Formulation for Upper Internals for LMFBR J. Y. Gregis. J. C. U. Northwestern University. Northwestern University. Italy Three-Dimensional Response of Piping Systems to Internally Propagating Pressure Pulses M. Evanston. Ariman.F. Commission of the European Communities.A. Dubois. . University of Notre Dame. Evaluation of DNB Induced Fatigue in Heat Transfer Tubes S.V.B. Argonne. J.M. D.A. U.R. T. London. Ispra.A. Illinois. New Jersey. Coolant System and Materials Response E 3/1 * E 3/3 E 3/4 E 3/5 E 3/7 38 Dynamic Uniaxial and Biaxial Stress-Strain Relationships for Austenitic Stainless Steels C. Chedmail.F. J. Fluid-Structure Interaction Analysis of a Deck Structure During a HCDA R. Nuclear Installations Inspectorate.M. Rungis-Silic. A. U. Kulak. Thermal-Hydraulic and Structural Safety Analysis of SLSF P3 Experiment W. Jones. U. Kendall. Experiments and Code Verification I E 4/1 * E 4/2 E 4/4 E 4/5 E 4/6 E 4/7 Experimental Validation of the Containment Codes ASTARTE and SEURBNUK K. Kondo. Palamidessi. San Leandro.A. California. d.A. U. A. Giuliano.J.J. Reading. Verzelletti. Yamada. Arnold. Gouda. A. Ispra Establishment..A.Session E 4. Cagliostro. J. B. 39 . SRI International. Ispra. Germany. Università di Bologna. U. Rep. Comparison Between Calculations and Tests for a Support Structure of a LMFBR Tank Under the HCDA V.C. Italy Energetics of Simulated HCDA Bubble Expansions: Some Potential Attenuation Mechanisms R. G. Winfrith. Bologna. Dorchester. S.K. Dorset.A. Kendall.S. Illinois. M. UKAEA. M.H. CNEN Dipartimento Reattori Veloci. Dorset.. Italy The Development and Validation of Thin Shell Models in Computer Codes for Fast Reactor Containment Analysis K.C. Physics International Co. P. Fed.R. Ando.West. Jones.K.S. v. Cenerini. Japan Session E 5. Berkshire. The Netherlands. Broadhouse.S. Bologna. California. MOD(PE)AWREAldermaston. Tokyo. Yerkess.. D. Ispra Establishment. UKAEA. M. Chang.A. Control Data GmbH. Menlo Park.Tobin.S.W. Frankfurt/Main. Wang. U. Dorchester. J.J. H. A.J.C. D..R. Scala.J.Y. Illinois. Atomic Energy Establishment. L. Argonne. U. Argonne. Benuzzi.V. Commission of the European Communities. Hoek. Argonne National Laboratory. University of Tokyo. Cowler. AMN S. U. Argonne National Laboratory.C.p. A. Petroski.W. Recent Results on PEC Reactor HCDA Containment Investigations R. Ispra. Physics International Co. Italy Experiment and Analysis on Pressure Pulse Propagation in a Plastically Deforming Pipe Y. Y. Genova. Ploeger. ICECO Simulation of the COVA Experiment C. AEE Winfrith. Experiments and Code Verification II E 5/1 E 5/2 E 5/3* Analysis of the HCDA-Simulation of the 1/6-scaled SNR-300 Fast Breeder Reactor with the PISCES™-2DELK-Code W. Pohl. Commission of the European Communities. Fracture Experiments with Cracked and Embrittled Hexcan Sections H.S. Β.S. Petroski. Comparison of REXCO Code Predictions with SRI SM­2 Experi­ mental Results Y.E. Axisa. Menlo Park. D. Salz. Baltes. Kernforschungszentrum Karlsruhe. Petroski. D. Gesellschaft für Reaktorsicherheit. Ar­ gonne. U. Illinois.F. Germany Session E 6. Evanston. Illinois. T. Kernforschungszentrum Karlsruhe.E 5/4 E 5/5 E 5/6 Structural Response of a 1 /20­Scale Model of the CRBR to a Simu­ lated H CDA C M .A. Villard. A. Saitama. Seino. H . U. Illinois.J. Core Components Response E 6/1* Effects of Cracks on the Response of Shell Structures H. Germany E 6/5 The Dynamic Response of Cracked Hexagonal Subassembly Ducts J. U.S . CEA/CEN­S aclay DEMT. Belytschko. Kulak.F. France 40 . Fed. The Simulation of Small Scale Explosion Tests with the German Fluid­Structure Interaction Code ARES B.J. Gibert. H oang. Omiya City. Mitsubishi Atomic Power Industries. E 6/6 Flow Splits and Bowing Performances of Fuel Pins in Wire Wrap­ ped FBR Fuel Assemblies K. Argonne. Illinois. U. E 6/2 Three­Dimensional Finite­Element Computations of the Trans­ ient Response of Components Typical of a Reactor Structure J. Argonne.A. Malmberg. T. Kennedy. Cagliostro.S .J. E 6/4* Prediction of Energy Absorption Capability and Damage Distribu­ tion of a Complete LMFBR Subassembly Under Pressure Pulses H. Rep. Zehlein. Argonne. A. Illinois. Argonne National Labora­ tory.S. Ash. R. Schoeberle. Itoh.. Marchertas. University of Illinois at Chicago Circle. Rep. Fed. US A. T. Karlsruhe.W.A. California.S .L. E 6/3* Quasi­Eulerian Formulation for Fluid­Structure Interaction J. Argonne National Laboratory.H . J. Inc. Chang. R. Gif­ sur­Yvette. Argonne National Laboratory. Y. Karlsruhe. Chicago. S RI International. Kubota. Argonne National Laboratory. Illinois. US A. S.. Köln. Argonne. Gvildys. Northwestern University.J. W. Glazik. Jr.M. Romander.B. Japan E 6/7 Flow Induced Vibrations of LMFBR Structures F. Argonne National Laboratory. Illinois. R. Gif­sur­ Yvette G. Electricité de France. Pra­ gue. France The sign (·| designates Invited Lectures. Chalk River. C­Ε Power Sy­ stems. U... Paris La Défense. Rep./CEN­Saclay DEMT. Hugot. Paris La Défense. STRUCTURAL ANALYSIS OF REACTOR CORE AND COOLANT CIRCUIT STRUCTURES Session F 1. Toronto. Inc./CEN­S aclay DEMT. Fed. H. G. Engel. A title mentioned on the Table of Contents but not followed by a summary or a paper means that the paper was not available at the time of finishing of the book. Lee. Assedo. Analysis of Pressure Tube Elongation and End Shield Interac­ tions in the CAN DU Reactors A. Epstein. Special Problems F 2/1 F 2/2 Vibration Studies on a Three Loop PWR Internals Model R. Ger­ many Pump Induced Fluctuating Pressure in a Reactor Coolant Pipe L.. Gif­sur­Yvette. Kraftwerk Union AG.K.<SG.A.R. Castello. RJ. Assedo. R. Kuzelka.TABLE OF CONTENTS Division F. Chandra.J.S . Erlangen. Grid­perfo­ rated Plate Compound. MacEwen. Fed. A. Berkner. Gibert. Inc. Baylac. Connecticut. i.M. Kraftwerk Union AG.B. FRAMATOME. Gibert.A. Ontario. Paris La Défense. France Nuclear Reactor Surveillance ­ Neutron Noise Measurements and Vibration Analysis on French PWR Internal Structures R. U. Mitchell. Rep. Beeston. S. Czecholovakia Plastic Analysis of the Core Barrel Flange Deformations According to Non­Symmetric Bending Loadings U. Ontario. Session F 2.R. Epstein. Idaho. Ca­ nada Vibration of PWR Internals Considering Their Edge Conditions and Holes V. National Research Institute for Machine Design. CEA. FRAMATOME. EG. Causey. e. T.O Jamieson. Germany Stressand Displacement Analysis of a Core Plate. SEPTEN. S. A paper number missing in the numeral order means that the paper was cancelled or withdrawn. Idaho Falls. Combustion Engineering. Windsor. A. Modelled as an Equivalent Beam System R. CEA. 41 . Idaho.S. Atomic Energy of Canada Ltd. Frank. Ontario Hydro. G. A. Reactor Core Structures F 1/1 F 1/2 F 1 /3 F 1/4 F 1/5 F 1/6 Stress Relaxation Analysis for Irradiation Creep and Swelling in Pressure Tubes J. Erlangen. Burr. /CEN-Saclay DEMT. Prost. Tremblais. Heeschen. S. CEA. Fed. Ltd. Japan Session F 3. NOVATOME.. Cesari.. Dipartimento Reattori Veloci. Germany Theoretical and Experimental Analysis on Tee Piping Components F. Curioni. Y. Ibaraki.S. Yokohama./CEN-Saclay DEMT. Ishikawajima Harima Heavy Industries Co. Votava. T. T.N. Takasago. Erlangen. Bagneux. B.C Shao. Takasago Technical Institute. Division of Reactor Safety Research. H. Office of Nuclear Regulatory Research. Umemoto. SOCOTEC. Doyen.E. Le Plessis Robinson. C. Hofmann. Erlangen. Imazu. Watanabe. K. Paris la Défense.P. D. F 2/8 Theoretical and Experimental Study on Induction Heating Stress Improvement (IHSI) of Nuclear Primary Piping Y. Paris. Jakubowicz. Yagawa.A. Meneghini. P. Piping: Structural Analysis F 3/1 F 3/2 F 3/3 F 3/4 F 3/5 42 Experimental and Elastic-Plastic Numerical Analysis of a PWR Piping Elbow Subjected to Pressure Cycling J. Toshiba Corporation.. U.C.S. Descleve.. CEA. Mitsubishi Heavy Industries. Kraftwerk Union AG. McLoughlin. Nakamura...F 2/3 Application of Acoustic Emission as a Monitoring System During Hydrostatic Tests of Nuclear Reactor Components E. Bologna. Japan . Mechanical Engineering Research Laboratory. Bertaut. Kraftwerk Union AG. Enomoto. Foult. S. Gif-sur-Yvette. Rep. The Tokyo Electric Power Co. Nuclear Regulatory Commission. FRAMATOME. Hitachi Ltd. Century Research Center Corporation. France In-Plane and Out-of-Plane Bending Tests on Carbon Steel Pipe Bends D. Germany F 2/4 Prediction of the Vibratory Behaviour of a Multistage Gaseous Diffusion Plant P. Ltd. Briot. Tokyo. Brouard. Italy Simplified Creep Buckling Analysis of Elbows under In-Plane Bending A. Vrillon. Tokyo. T.N. C. Inc. University of Tokyo. K. O-arai Engineering Center.. Fed. G. A.J. Washington. France Stesses in a Curved Pipe Subject to an In-plane Bending Moment E. Power Reactor and Nuclear Fuel Development Corporation. France F 2/6* Stress Corrosion Cracking Experiments in Piping of Light Water Reactor Power Plants L. J. U. S. Gif-sur-Yvette. Département Génie Industriel et Nucléaire. Ando. Nakayama. USSI. A. Tokyo. Rep. Hitachishi. Hayase. U.J. Tokyo. P. Uesugi. Upton. Hartzman. S. New York. Issler. Y. S. Palusamy. Tokyo. U. Bezler. Kraftwerk Union AG. Windsor. M. Italy Detailed Analyses of Three Elbow-Pipe Assemblies for Typical Load Cases T. 43 . Kano.p. Kernforschungszentrum Karlsruhe. Geidel. Century Research Center Corporation.. U. Institute of Radition Protection.-R. Genova. Pittsburgh. Griesbach.S. AMN S. Campbell.N. Vibrationof Three-Dimensional Piping Subject to Pump Pulsation R. Takeda. Westinghouse Electric Corporation. Japan Stress Distribution and Flexibility of the Suction Bend of the Primary Sodium/Pump LMFBR .J. Power Reactor and Nuclear Fuel Development Corporation.E.. Stork Boilers. Germany Session F 5. Westinghouse Nuclear Europe. Combustion Engineering. Karlsruhe. Stuttgart. PWR Systems Division.A.A. Bethesda. U. Fracture Mechanics F 5/1* F 5/2 Opening and Extension of Circumferential Cracks in a Pipe Subject to Dynamic Loads D. H. Maryland. Iwata.S. Real-Time Numerical Evaluation of Dynamic Tests with Sudden Closing of Valves in Piping Systems K. Consultant. Rep. Wada. Bruxelles. W. Universität Stuttgart. Keskinen. Chirigos. Tokyo. Lazzeri.C Hennart. Helsinki. J.. Connecticut. Connecticut. Windsor. Nuclear Regulatory Commission. T.S. Ayres. Elastic-Plastic Response of PWR Coolant Pipes Containing Postulated Circumferential Flaws S. Fed. Belgium Nonlinear Dynamic Analysis of Piping Systems Using the Pseudo Force Method S. Pennsylvania. Leimbach. T. Germany Acoustic Pressure Pulsations in Pressurized Water Reactors MM. Asai. Katzenmeier. Prachuktam.A.K. Offenbach. Brookhaven National Laboratory. Finland Study and Measurement of Impact Damping in PWR Reactor Coolant System Seismic and Accident Restraints J. The Netherlands Session F 4. Staatliche Materialprüfungsanstalt (MPA). Bochum-Linden. Fed. Kwee. Combustion Engineering Inc. USA. Rep. Inc. K. G.J. Hengelo.S.SNR 300 H. Cepkauskas. Piping: Dynamic Analysis F 4/1 * F 4/2 F 4/3 F 4/4 F 4/5 F 4/6 Structural Behaviour of Piping Systems under Accident Conditions L. USA.F 3/6 F 3/1 F 3/8 An Elastoplastic Elbow Element: Theory and Applications L. Istituto di Impianti Nucleari. C.J. Connors. Ontario Hydro Research. Toronto. Berkeley.A. Saint­Paul­lez­Durance. Facoltà di Ingegneria. Gif­sur­Yvette.F 5/3 F 5/4 F 5/5 F 5/6 F 5/7 F 5/8 F 5/9 F 5/10 F 5/11 F 5/12 F 5/13 Numerical Study of Dynamic Crack Growth Including Fluid Inter­ action D. Idaho. E. Lebey. Mukherjee. T.. Tomassetti. M. Berkeley. U. Bethmont.C.W. U./CEN­S aclay DEMT. CEA. Μ. Tennessee. Caidis. C. Griffiths. The Failure of Ductile Plates Containing Thin Ligaments I./CEN­DMG/S EM. CEA. Okamura.C. Reale. Booker.E. Kurotobi.E. Problems Identified in Quantifying Leak before Break in Pressure Containing Structures B.J. S. J. Ductile Failure of Cracked Member under Combined Loading of Membrane and Bending Stresses H. 6/1 * Experimental Studies of PWR Primary Piping under LOCA Conditions C. University of Wales. Moscow. Sermet.A. Comitato Nazionale per l'Energia Nucleare. Smith. P. H. E.J.J. U. France Crack Growth Rate of PWR Piping M. CR. U. Carmignani./CEN­Cadarache. Oak Ridge.S. Courbevoie. Oak Ridge National Laboratory.L. Experimental J and COD Analysis of Crack Initiation in Through­ Thickness Cracked Pipes C. M. CEGB Berkeley Nu­ clear Laboratories. D. U. D. CEGB Berkeley Nu­ clear Laboratories. B. Pisa. Cauquelin.K. Idaho. Japan Estimating Structural Integrity of Type 304 Stainless Steel Plates and Pipes Containing Small Defects W. Darlaston.J.L. Paris la Défense.J. Idaho Falls. Inc. Booker. J. Gloucestershire. E. Elastic Plastic Fracture Toughness Values for a Hastelloy Sample Submitted to Static Load P.G. Brinkman. Corwin. Hellen.L Vanderglas. Connors.A. Tokyo. France 44 . F. Canada Characterizing Fatigue Crack Propagation in 2 1 Λ Cr­1 Mo Steel for Steam Generator Applications W. Roma. Grenoble. Reuter.A. R.W. & G.K. Pipe Rupture F. Darlaston. Caumette. Casac­ cia. Garcia. Swansea. University of Idaho. EG. Gloucestershire. FRAMATOME. CEGB Berkeley Nuclear Labaratories. J.K. Goodall.A. FRAMATOME. On the Behavior of Reinforced Mitre Bends Containing Defects B.S.R. Italy Session F 6.L. Morgand. J. France Determination of Vibration Strain Limits of A106B Piping Steel B. H inton. G.R. Owen.S . Idaho.A. Doyen. Ontario. Hellen.K. Berkeley. Taylor.P. Goucestershiere. University of Tokyo. Place.Κ. Churier. R.L. U. Kent. Silva. U. MAPI Engineering Center. G. Germany Comparative Study of Models for Pipe-Whip Analysis M. J. Italy 45 .B. Cheissoux.G. Offenbach. R. J.K. Jedlicka.A. Saint-Paullez-Durance. H. Tennessee Valley Authority. Helsinki. Garcia. Transient Pressure Reductions and Flow Areas Resulting from the Ductile Fracture of Pressurised Cylindrical Vessels G. California. K. Parmeggiani. Baum.S. Roemer. Imatran Voima Osakeyhtiö. Kraftwerk Union AG.S. CEGB Scientific Services Centre. M. G. Tennessee. Technical Research Center of Finland. T.L. C. Finland Pneumatic Rupture of Pipes: The Development of the Breach M. Kawanishi. Mitsubishi Heavy Industries. T. Habedank.E. Courbevoie. Tokyo. Heller. Nishikawa. FRAMATOME. Rio de Janeiro. Mondkar. DIAPRS . CISE. Japan Experimental Studies of PWR Secondary Piping in Case of Steam Break A. Brazil Safety of Pipe Whip Restraints C Burducea. Kangas. Takasago Technical Institute.P./CEN-Cadarache. M. Takasago-City. Kraftwerk Union AG. Theuer. Fed. Berkeley. Mitsubishi Atomic Power Industries. Elastic-Plastic Dynamic Behavior of Guard Pipes due to Sudden Opening of Longitudinal Cracks in the Inner Pipe and Crash to the Guard Pipe Wall E.A. U.A.A. Rep.A.A Computer Program for Dynamic Inelastic Analysis of Ruptured Piping D. Berkeley. Possa. Fed. Chevallard.E. Massachusetts. Kukkola. U. Bevilacqua. Boston. Stone & Webster Engineering Corporation. Experiments and Application to Pipe Whip Restraint Design K. Eke. Session F 7. CEGB Berkeley Nuclear Laboratories. J.F 6/2 F 6/3 F 6/4 F 6/5 F 6/6 Experimental Study of Pipe Reaction Force and Jet Impingement Load at the Pipe Break K. U.H. A. Erlangen.R. Milano. Knoxville. Gravesend. Tsúruto. Ikonen. University of California. C. France Local Crush Rigidity of Pipes. Germany Simulation of the Dynamic Loads and Stresses Due to Explosive Rupture of a Pressure Tube in a Scaled Down Model of the CIRENE Reactor Structure G. Centro Informazioni Studi Esperienze. Nagatogawa. Kitade.L. K.. Rep. Pipe Rupture: Methodology F 7/1 F 7/3 F1/4 F1/5 F 7/6 F 111 Design Considerations for Application of Metallic Honeycomb as an Energy Absorber W. Promon Engenharia S. L. Martin. Famiglietti.K. Helsinki. M. Lee. T. Canada Optimisation of Pipe Restraint Spacing in the Neighbourhood of Metal Containment. Ko. Scholl. Atomic Energy of Canada Ltd. Kitagawa. Y. Kernforschungszentrum Karlsruhe. Ohnami.A. Rogers. Chiba. Pressure Vessels or Other Equipment L.. Fed. Tokyo.D. U. F. California. R.. Rep. Chiba University.F 7/8 Numerical and Experimental Results on the Consequences of a Bursting Pressure Tube in a D 2 0 Power Reactor R. Switzerland An Economical Produre for Small Pipe Support Design G. U. Grillenberger. Gesellschaft für Reaktorsicherheit.C. Ltd. Kitagawa. T. Yamada. Heat Exchangers F 9/1 F 9/2 F 9/3 F 9/4 F 9/5* 46 A New Design Code for 1. Rep.-H. Milano. Japan Development of Analytical Procedure for the Design of 1. Mannheim. Hamanaka.K. Chiba University. Italy Session F 8. H. Japan Design of Heat Exchangers for High-Temperature Reactors J. Hochtemperatur-Reaktorbau GmbH. Karlsruhe.. The Hague. Goto.V. Saiga..5 Mwt Helium Heat Exchanger M. Tokyo. Famiglietti. Rautenberg. Carson. Red. Chiba.. Bechtel Power Corporation. IshikawajimaHarima Heavy Industries Co. Germany Analytical and Experimental Studies of Tube/Support Interactions in Multi-Span Heat Exchanger Tubes P. Germany Tests on a 1. Ludwig. Udoguchi. Chalk River. Kyoto. Umeda. Montreal. Fredericton. Bazergui. Spilker. Ontario. New Brunswick. M.M. Motor-Columbus Consulting Engineers.A. Leoni. Hamanaka. California. Bolted Flange Assembly with Spiral-Wound Gaskets A. Lardenoye. Ecole Polytechnique. Neratoom B.P. Goto. The Netherlands . Tokyo.J. J. University of New Brunswick. T. Gupta. C/SE. University of Tokyo. R. Ritsumeikan University Kyoto. Ishikawajima-Harima Heavy Industries Co. Ltd. Centro Informazioni Studi Esperienze. Byron Jackson Pump Division. Baraf.G. Saiga.. L.S. Marrujo.S. Y.H. Quebec.L. M. Garching. T.5 Mwt Helium Gas Intermediate Heat Exchanger J.W. K. Canada Some Advanced Methods in Stress Analysis of Sodium-Heat Transfer Components P. Baden. T. Los Angeles. Yeh. M. Experimental and Analytical Results of HDR Blowdown Tests Concerning Dynamic Valve Behaviour T. Components and Support Systems F 8/1 F 8/2 F 8/3 F 8/4 F 8/5 Minimizing Unbalance Response of the CRBRP Sodium Pumps V. Y.75 m O. Ciacci. Udoguchi. Session F 9. A. Inc.C. Westinghouse Electric Corporation. R. Swiss Federal Institute for Reactor Research. S. J. Brno. Ogura. Mager. J. Yuuki. S an Jose.Y. 47 .S A. Washington. Nakagiri. University of Tokyo. Milne. Bilek. Tokyo. Technische Universität Wien. Z. G 1/6 Fracture and Break­Through due to Surface Crack in Reactor Environment under Earthquake Conditions H. Czechoslovakia G 1/3 Evaluation of the Defect Tolerance of Pressure Vessels under Combined Thermal and Pressure Loads I. G 1/4 Radiation Embrittlement Saturation Effect in Commercial Light water Reactors K. General Electric Co. Overviews of Integrity Assessment G 1/1* Fracture Testing in Support of RPV Failure Prevention in Switzer­ land T. Combustion Engineering.J..TABLE OF CONTENTS Division G. Würenlin­ gen. Kitagawa. LE.S. Leatherhead. Institute of Physical Metallurgy. Varga.S. U.. S urrey. Stahlkopf.H. Nuclear Energy Engineering Dept.. Vienna. Palo Alto.. T. Nuclear S afety Division. U. A. Schaefer. G.U. Connecticut. — A title mentioned on the Table of Contents but not followed by a summary or a paper means that the paper was not available at the time of finishing of the book. Prantl. Notes: — The sign (·) designates Invited Lectures. Koziol. U. D. Njo. Swiss Federal Office of Energy. Penn­ sylvania. N.O. STRUCTURAL ANALYSIS OF STEEL REACTOR PRESSURE VESSELS Session G 1. K. CERL. CEGB. S witzerland G 1/2 Comments on Brittle Fracture Control and Structural Integrity in Nuclear Power Plant Components M. California. U.R. — A paper number missing in the numeral order means that the paper was cancelled or withdrawn. New York.S A. Inc.K. Man. H olzmann. Naval Research Laboratory. Austria. The Metal Properties Council.E. California. Japan G 1 Π* U. D. Institute of Industrial Science. Windsor. Steele. Würenlingen. Pittsburgh. Metal Properties Council Activities Pertinent to Reactor Vessel Integrity T. Ranganath. Marston. EPRI. G 1/5 Fracture Mechanics Evaluation of a Boiling Water Reactor Vessel Following a Postuladed Loss of Coolant Accident S. Windscale Works.Session G 2. U. Dietmann.Gillemot. K. U.J. Culcheth. Abington. Fracture Toughness Measurements G 2/1* Fracture Toughness of Pressure Vessel Steels from Small Specimens R..K. a Failure Criteria for Neutron Irradiated Materials F. Palo A/to. T. Witt. Robinson. Germany G 2/3a Biaxial Nominal State of Stress at the Crack Front H. UKAEA. G 2/3 The Influence of the Stress State on Fracture Toughness Further Results D.I. Erbe. Fracture Mechanics: Elasto-Plastic G 3/1* G 3/2 48 Elasto-Plastic Fracture Mechanics Applied to the Safety Assessment of Nuclear Power Stations N. G 2/7 Revised Fracture Toughness Reference Curves W. U. U. Manchester. California.I. Bundesanstalt für Materialprüfung (BAM). Materials Research & Computer Simulation.H.K. J. Session G 3.K.N. Lancashire. G 2/2 The Determination of Critical Fracture Criteria Parameters from Small Specimen Testing F.A. U. Smith. Westinghouse Electric Corporation. Wullaert. S. Ziebs. Khonkaen University. Palo Alto. London.U. The British Petroleum Company Ltd. Universität Stuttgart.K.J. Marston. C. British Nuclear Fuels Ltd. Goleta. Helms. Fed. and Testing of a Uniform Applied Load Flat Plate Testing Machine A. Hungarian Academy of Sciences. Garwood. California. Sellafield. J. The Welding Institute. Stuttgart. Rep. G 2/5 A2-and3-Dimensional Elasto-Plastic Finite Element Analysis of an SENB Fracture Specimen N. Electric Power Research Institute.. U. Adams. Oldfield. Design.S.J. Fracture Control Corporation. Kussmaul. Safety and Reliability Directorate. EPRI. USA. U. H. H. Aurich.SA. Hungary . London.. Pittsburgh.E.A. R.. Berlin. Server.A.E. Adams.Crook. University of Manchester/'UMIST. W. Pennsylvania.U. Stahlkopf. Marston. Veith. Warrington. G 2/6 An Overview of Crack Arrest as it Applies to ReactorVessel Integrity T. California.J. Central Research Institute for Physics. Cumberland. K. Germany G 2/4 The Philosophy. Khonkaen.S. California. PWR Systems Division. Quirk. Cambridge. E. Staatliche Materialprüfungsanstalt (MPA). Goleta.L. The British Petroleum Company Ltd. Thailand Absorbed Specific Energy of Fracture. Budapest. K. Wüthrich. Washington University. Lehigh University. U. The Application of Post Yield Fracture Methodology to the Evaluation of Large Structures J. Institut für Festkörpermechanik der Fraunhofer Gesellschaft. A.D. Bethlehem. Winkler. Landes. Fed.J. Paris. Kraftwerk Union AG. W.A.-Measurements in Instrumented Impact Tests J.F.S. Stress Intensity Distributions in Nozzle Corner Cracks of Complex Geometry C.S. Beinert. Peters. A. U. Stockholm. Session G 4.C.S. Fracture Mechanics: Stable Crack Growth G 5/1* The Use of CT-and Bend Specimens for Tearing Modulus Determinations A.P. Germany Session G 5. On the Validity of Kj .A.J. Virginia Polytechnic Institute. Research and Development Center. U.H. Westinghouse Electric Corporation. Institut für Festkörpermechanik der Fraunhofer Gesellschaft. Kathiresan. Missouri.S. Kalthoff. Georgia Institute of Technology. Pennsylvania. U. USA. Gerscha. Hardrath. Fleischman. Erdogan. Washington. Sweden. Delale.F. St. A.S. Blacksburg. C.A. Pennsylvania. Freiburg. Kalthoff.N. Fed. Gomez. J. 49 . Jain. Georgia. Kobayashi. Rep. Royal Institute of Technology. Louis. W. Pittsburgh.W. The Effect of Transverse Shear and Material Orthotropy in Cracked Cylindrical and Spherical Shells F. S. Baden. Love. W. Brown Boveri Research Center. F. W. Klemm. PWR Systems Division.G 3/3 G 3/4 Energy Based Methods for Determining Elastic Plastic Fracture F.SA. T. Witt. J. Westinghouse Electric Corporation. Erlangen. Switzerland G 5/1 a* The Status of Tearing Instability Analysis withdrawn P. Pennsylvania. Smith. Germany The Response of Pressure Vessel Steel Specimens on Drop Weight Loading S. U. Pittsburgh.A. M. Emery. Freiburg.F. Carlsson. University of Washington.S. U.S. Winkler. Rep. Fracture Mechanics: Special Aspects G 4/1* G 4/2 G 4/3 G 4/4 G 4/5 G 4/6 Further Studies on Stress Intensity Factors of Semi-Elliptical Cracks in Pressurized Cylinders A. Virginia.J. Stress Intensity Factor Solutions for Arbitrarily Shaped Surface Flaws in Reactor Pressure Vessel Nozzle Corners S.A. Atlanta. Seattle.T. Atluri. Schenectady.L. R. Washington. SRI International. U.C. I. Jr. Santa Barbara. Y. Β. Pennsylvania. General Electric Corporate Research Et Development Center. New York. Joint Manchester University/'UMIST Metallurgy Depart­ ment. K. Burback. Pittsburgh. Liebowitz. U. Tominaga. U. Kumar.. Session G 6.. Sakaguchi. Wei. Wilkinson. R. Fracture Mechanics: Materials Modeling G 6/1 * Evidence for the Relative Importance of Dynamic Fracture Tough­ ness D.S. Smith. Curran. U.J. Bethlehem.A.S.S. Bilek. Shih. Seaman. H.C Newman. Andrews. Shih. Session G 7. California.K.A. U. Kure-City. Japan Stress Analysis and Fracture of Surface Cracks in Cylindrical Pressure Vessels J. Menlo Park. Noda-City. J. Consideration of Nonsteady State Crack Growth in Materials Evaluation and Design S.D. Kikuchi. General Electric Corporate Research and Development Center. Hamp­ ton.K.A. Hudak. .A. Hiro­ shima-Ken. Ltd. Raju. Manchester. Lehigh University. Ireland. Miyamoto.S. Dao. Effects Technology.. CAS. Pennsylvania. S. Japan G 6/2* Effects of Plasticity and Crack Geometry on Fracture H. U. W. G 6/3 The Effect of Microstructure on the Fracture Toughness of Struc­ tural Steels M. Brno. Ζ.R. T. Kure-Shi. Chiba. Babcock-Hitachi K. Maruyama.G 5/2 G 5/4 G 5/5 Crack Initiation and Growth under Fully Plastic Conditions with Applications to Pressure Vessel Steels CF. Science University of Tokyo.C. The George Washington University.A. D. D. Schenecta­ dy. Westinghouse Electric Corporation. Vlach. U. Fracture Mechanics: Computation G 7/2 G 7/3 50 Evaluation of Three-Dimensional J-lntegral of Semi-Elliptical Surface Crack in Pressure Vessel M. Virginia. Jr.R..P. Subramonian. Inc. Stable Ductile Crack Growth in Reactor Pressure Vessel Steels E.A. V. Hi­ roshima Prefecture. NASA Langley Research Center.. Kure Works.S.A.P. Institute of Physical Metallurgy. J. Holzmann. Lee. G 6/5 Characterizations of Continuing Fracture in Elastic-Plastic Solids CF. New York. USA..S. Shockey. Research and Development Center. L.S. N. Babcock-Hitachi. California.R. Czechoslovakia G 6/4 Computational Modeling of Microstructural Ductile Fracture Processes in A 533 Β Pressure Vessel Steel D. CEGB. Tour Fiat. Leatherhead. J.P. Centre de Recherche d'Unieux.S. Ohio. France G 8/2 Verification of the Resistance of PWR Thermal Sleeves to Thermal Fatigue M. U. J. Laboratoire du Creusot.K. Pellissier-Tanon. Columbus. Etablissement de Saint Marcel. Gehlen. Creusot-Loire. Fracture Mechanics: Thermal Effects G 9/2 G 9/4 G 9/6 Dynamic Fracture Analysis of Thermal Shock Loading in Nuclear Pressure Vessels P. Ponsot. Y.M. Amzallag. Mercier. FRAMATOME. Service de l'Industrie et des Mines. Hahn. Creusot-Loire. Rabbe. Unieux. Columbus. F. France Session G 9. Saint Marcel. P. Ohio State University. Engineering System International. Cyclic Elastic Analysis of a PWR Nozzle Subjected to a Repeated Thermal Shock J. Bosser. Paris. M. Surrey.G.A. Creusot-Loire. Le Creusot. Saint Marcel. Ohio. Locci.C.F.Session G 8. FRAMATOME. Rungis-Silic.C. Fatigue G 8/1 * A Criterion for Analysing Fatigue Crack Initation in Geometrical Singularities J. CH. GT. 51 . Bureau de Contrôle de la Construction Nucléaire. Battelle Columbus Laboratories. Paris. FRAMATOME. Kanninen. Unieux. A. Centre de Recherche d'Unieux. Popelar. Cheli. France A Fracture Mechanics Approach to Predicting the Effects of Warm Prestressing and its Applications to Pressure Vessels G. U. D'Escatha. Devaux. C. Etablissement de Saint Marcel. Prost. Research Laboratories. FRAMATOME. Dijon. TS. India 52 . Bangalore. B. India G10/6 Thermal and Structural Anaysis of the Support Region of an LMFBR Reactor Vessel A. A. Kowalske. EDF/SEPTEN. France G 10/5 A Semi-Analytical Technique for the Design of Rolled Joints R. Sinha. SOCOTEC/GIN-AME. Trombay. Stress Analysis G 10/1* Interpretation of Strain Measurements on Nuclear Pressure Vessels S. Seth. Lecarpentier. A. Hunsbedt./CEN-Saclay DEMT. P. Paris. Kraus. Bombay.K. Krishnan. Sunnyvale. Dattaguru.K. Colaba. California. Kakodkar. S.A.S. G 10/7 Finite Element Analysis of Inclined Nozzle-Plate Junctions KB. Indian Institute of Science. Andersen. Bombay. Government of India. A. P.I. Risø National Laboratory. Bhabha Atomic Research Centre. Engbaek. Power Projects Engineering Division. Gif-sur-Yvette.. Roskilde. CEA. Advanced Reactor Systems Department. Germany G 10/3 Structural Analysis of a PWR Vessel Nozzle-to-Hemisphere P. Denmark G 10/2 Bolted Joints as a Problem of Elastically Supported Slabs D. Paris. Dixit. Millard. Technischer Überwachungsverein Norddeutschland. U. Ramamurthy. Fed. V.K.Session G 10. A. Bourrier. Hamburg. Rep. Rao. General Electric Co. Fed. K. Fed. Universität Karlsruhe. HK. Kirmser. Zemann. Német. — A title mentioned on the Table of Contents but not followed by a summary or a paper means that the paper was not ava lable at the time of finishing of the book. Ziegeldorf. Creep. Seeberger. Braunschweig.S. Germany H 1/5 H 1/6 H 1/7 Moisture Transport and Vapor Release of Concrete Structures at Temperatures > 100° C K. Karlsruhe. Germany — The sign ("I designates Invited Lectures. STRUCTURAL ENGINEERING OF PRESTRESSED REACTOR PRESSURE VESSELS Session H 1.und Baugesellschaft. H. Ingenieurbüro Alois Aschl. Kansas State University. Strength and Thermal Expansion of Concrete at Elevated Temperatures M. Fed. München. Fed. H. Weissbacher. Takenaka Technical Research Laboratory. Manhattan.A. Berlin (West). Austria H 112 Strength Characteristics of Concrete in the Temperature Range of 20° to 200° C R. Sakuta. Rep. Schneider. Moosecker. Yoshioka.D. Seibersdorf. Germany Moisture Transfer in a Concrete Slab C. Kasami.C Hundt. P. Seibersdorf. Kordina. Bundesanstalt für Materialprüfung. Materials Behavior II H 2/1 Thermal Expansion of Concrete for Nuclear Structures S. Tokyo.TABLE OF CONTENTS Division H. H. AschI. Germany H 1/3 Heat and Moisture Transfer in Concrete Under the Influence of Temperature J. Technische Universität Braunschweig. München. Kottas. Rep. J.L. Rep. H.H. Y. Hilsdorf. — A paper number missing in the numeral order means that the paper was cancelled or withdrawn. Kleiser. Kansas. Karlsruhe. J. Technische Universität München. U. U. Reaktorbau Forschungs. 53 .K. Germany H 1/4 Concrete for PCRVs: Mechanical Properties at Elevated Temperatures and Residual Mechanical Behaviour after Triaxial Preloading H. Rep. W. Japan Session H 2. Materials Behavior I H 1/1* Properties of Concrete at Elevated Temperatures L. Universität Karlsruhe. Österreichische Studiengesellschaft für Atomenergie.G. Siang. Hilsdorf. Huang. K. Germany Ultimate Strength Criteria of Concrete Under Bi-axial and Triaxial Loading G. B.A. Rodriguez. Innovations in Prestressed Concrete Pressure Vessel Design P. Rebora. Oland.H. California. Bergamo. Italy.S. S. U. Glasgow.Y.. Robutti.P. E. Zemann. Kneuss. Surrey. Weissbacher. HK.K. U. Greenstreet.B. Tennessee. California. Forgie. and Surveillance of PCVs H 3/1* H 3/2 H 3/3 H 3/4 H 3/5 54 Latest Developments in Prestressed Concrete Vessels for GasCooled Reactors F. James Williamson & Partners. Lausanne. Oak Ridge. Reaktorbau Forschungs. Ronzoni. C. . Hilsdorf. Wu. Feasibility Study of Prestressed Concrete Pressure Vessels for Coal Gasifiers C. Rendei Palmer 8. San Diego. New York. R.Tritton.-D. Lin International. CEGB. Seibersdorf. W.L.A. IPEN. General Atomic Company. T. Rep. Surveillance of Prestressed Concrete Pressure Vessels Under Commissioning and Operational Conditions at Hunterston .Y. J. Hornby. The Strain Behaviour of a Prestressed Concrete Reactor Pressure Vessel after 12 Years Operation I. San Francisco.und BaugeseHschaft. Glasgow.A. Chow. Oak Ridge National Laboratory. ISMES. U. Favrod. S. N. Universität Karlsruhe. Ecole Polytechnique Fédérale de Lausanne. Scotland. Holland. Callahan. U. Glasgow. Design. Denmark Model Based on the Intrinsic Behaviour of the Concrete Under Cyclical Loads for the Dynamic Analysis of Three-Dimensional Structures J. U.B' Power Station H.Y. U.W.S.Y. Italy Failure Strength and Elastic Limit for Concrete: A Comparative Study G. L.H 2/2 H 2/3 H 2/4 H 2/5 H 2/6 H 2/7 Measurements Inside the Structural Concrete of a PCPV at Elevated Temperatures H. T. South of Scotland Electricity Board.S. Seeberger. Leatherhead. U. Ebasco Services. Research. Fed. withdrawn Session H 3. National Laboratory Risø. Roma.M. Roskilde. Ople. Jr.SA. Austria Effect of Nuclear Radiation on Mechanical Properties of Concrete J. J. N. Università di Roma.S. Valente. Lin.A. Switzerland Some Notes on the Dynamic Properties of Unsaturated Concrete ST. Seibersdorf.K. Karlsruhe. Aird. Österreichische Studiengesellschaft für Atomenergie. De Ngo. Ottosen.. Kansai Electric Power Co. Dodge. Tennessee. Ingenieurbüro Prof. H 4/2 An Exploration of the Design fora PCCV Head Slab with Very Large Penetrations Using a Dynamic Relaxation Computer Program F.S. Garas. W. Irobe. Ltd.A.H 3/6 H 3/7 H 3/8 Grouted and Nongrouted Tendons for Prestressed Concrete Pressure Vessels D. Cheshire. Bilfinger & Berger Bau-AG. National Engineering Laboratory.G. Oak Ridge. Aspects of the Design of Modern PCRV with Respect to the H HT-Vessel G.R.K. Risley.N.L. Kuroiwa. Middlesex. Waine.G.s. Mannheim. Oak Ridge National Laboratory. Smith.J. H 4/6 Verification of the Non-Linear Finite Element Code .. Oak Ridge. U. U.K.K...K Garas. Morgan. I. Rep. Kansai Electric Power Co. Southall.R. Structural Analysis of PCVs and Components H 4/1 * Experimental and Analytical Studies of Shear Behaviour of Slabs Subjected to Multiaxial Stress Conditions F.A. B. 55 . Fanning. Tennessee. Research and Development in Support of the Design of a Prestressed Concrete Pressure Vessel for a Working Pressure of 69 N/mm2 (10. M. Schnellenbach. Nuclear Power Co. Davies. Fleischer. Dodge.) F. Zerna St Dr. Middlesex. U.T.K. Germany Session H 4. Speidel.ADINA Applicable to the Analysis of Heated Concrete Structures I. Taylor Woodrow Construction Ltd. LI. Oak Ridge. Germany H 4/5 Test of the Second Model of the GCFR Steam Generator Cavitiy Closure Plug J. P. G. U.K. U. Bochum. Amagasakishi.. U. Oak Ridge National Laboratory. Schnellenbach. Naus. Southall.000 p. Nihon University.i. H 4/7 Methods for Calculating Inelastic Response of Prestressed Concrete Pressure Vessels and Vessel Closures D. c./o.. Taylor Woodrow Construction Ltd.. Waine. Fed. Nakamachi. Ohno.G. Middlesex. U. (Risley) Ltd.Callahan. Scotland. Fed. W.A.K. K. Warrington. Southall. East Kilbride.C Robinson.P. C C Fleischer. Nakanoshima.R.. Schimmelpfennig. M. Glasgow. Oak Ridge National Laboratory. Japan H 4/4 Parametric Study on Ligament Stresses in Multi-Cavity Prestressed Concrete Reactor Vessels (PCRVs) S. Kita-ku.S. H 4/3 Failure Criterion of Concrete Type Material and Punching Failure Analysis of Thick Mortar Plate T. Technical Research Center. Wakaogi. CC. Tennessee. B. Rep. Taylor Woodrow Construction Ltd. Garas.S. Sir Robert McAlpine & Sons. Schnellenbach.&C Steinmüller GmbH. L. California./CEN-Saclay. H.Abe. U. Rep. Wien. Lausanne.S. Mutzl. Bastien. Inspection and Repair J. Rebora.E. Ecole Polytechnique Fédérale de Lausanne. General Atomic Company. Bochum. Zerna . Fed. Gorholt. A. CEA. Comparison with Tests C. U. Liner and Thermal Barrier Systems H 5/1 H 5/2 H 5/3 H 5/4 H 5/5 H 5/6 H 5/7 56 Lateral Deflection of PCRV Liners in the Plastic Range W.. Gummersbach. W. Rodriguez.Dr. Switzerland Creep Behavior Under Sustained Temperature Gradient in a Model of Prestressed Concrete Reactor Vessels H. Stress and Fatigue Analysis. Gif-sur-Yvette. Ingenieurbüro Prof.A. Fed.E. Reaktorbau Forschungs.Including Thermal Creep Effects . H.A.S. U. Abiko. Leatherhead.K. R. Felten. France Testing and Analyses of a High Temperature Duct for GasCooled Reactors W. P. California. U. France Design of Steel-Liners and Their Anchorage with Regard to Non-Linear Behaviour of Liner-Material and Anchorage R. CEA/CEN-Saclay.Y. Hinterleitner. Güldenpfennig. Central Research Institute of Electric Power Industry. Japan Session H 5.S. P. General Atomic Company. San Diego.W. Chiba. J.S.N. DEMT. Grainger. Betts.H 4/8 H 4/9 Model . Austria Concept.und Baugesellschaft. Operation. Roberge.-D. Oberpichler. Aoyagi. Rep. The Elastic Hot Liner-Design. B. Black. Hornby. DEMT. B. VÖEST-Alpine Montan AG. General Atomic Company. San Diego. California.for the Analysis of Three-Dimensional Concrete Structures. Gif-sur-Yvette. Felten. San Diego. Liner Leak Simulation Tests on Prestressed Concrete Reactor Pressure Vessels I.Ohnuma. Black. IPEN.A. Germany . Surrey. Seibersdorf. CEGB Research Laboratories. Favrod. Germany Testing and Analysis of a High Temperature Thermal Barrier for Gas-Cooled Reactors W. Analysis and Construction of the Liner for Hot-Working Prestressed Cast Iron Pressure Vessels J. H interleitner. Guelicher. Mayr. Bounin. S iempelkamp. Kraftwerk­Union AG. P. E. Reaktorbau Forschungs­ und Baugesellschaft. Rep. Fritz Österreichische Studiengesellschaft für Atomenergie.&C S teinmüller GmbH. Nesitka. Reaktorbau Forschungs­ und Bauge­ sellschaft. S eibers­ dorf. Hochtemperatur­Reaktorbau GmbH. Wien. H. M. Reaktorbau For­ schungs­ und Baugesellschaft. S immering­Graz­Pauker AG. Német. Ber­ gisch Gladbach. S eibersdorf. Ettel. J. Germany 57 . Rep. Red. Fed. Mannheim.P. Austria Session H 7. H. Fed. Schwiers. Schwiers. Albrecht. Germany Η 6/5 Assessment and Structural Analysis of a PCPV with H ot Liner and Adjustable Wall Temperature A. M. Mannheim. Austria Η 6/6 Thermal Behaviour of a PCPV with Adjustable Wall Temperature A. Krefeld. Scheming. Gesellschaft für Hochtemperaturreaktor­Technik. J. Hochtemperatur­Reaktorbau GmbH. Testing and Operational Safety of a PCPV with Elastic H ot Liner and Adjustable Wall Temperature J. W. Ger­ many. W. Rep. Schwiers. Germany Criteria of Design and Analysis for Cold­ and H ot­Working Pre­ stressed Cast Iron Pressure Vessels (PCIV) D. Hochtemperatur­Reaktorbau GmbH. S eibersdorf. Erlangen. Mannheim. Fed. Mitterbacher. Gangl. Jahns. H. S eibers­ dorf. Fed. Hochtemperatur­Reaktorbau GmbH. Construction. K. K. L. Sei­ bersdorf. Austria H 6/2 Advanced Prestressed Concrete Pressure Vessels for Gas­Cooled Fast Breeder Reactors H. Austria Η 6/4 The Characteristics of the PCRV of the H H T Demonstration Plant J. H. Rep. Rep. Concept and Research for a PCV with Hot Liner H 6/1 " Concept. H interleitner. Walluschek. S iempelkamp. S eibersdorf. Gangl. Reaktorbau Forschungs­ und Baugesellschaft. Beine. P.G. Österreichische S tudiengesellschaft für Atomenergie. W. Witt. Mannheim. Kumpf. H . Germany. E. S ei­ bersdorf.­G. B. Austria Η 6/3 Feasibility of a Multicavity PCPV with Elastic H ot Liner for H TR HG. Német. Concepts and Research for a PCIV H 7/1 H 7/2 The Particular Features of PCIVs for H TR and other Applications in Nuclear Stations L.Session H 6. H interleitner. Scheming. Warnke. Reaktorbau Forschungs­ und Baugesellschaft. Gummersbach. Rau. Krefeld. Blair.K. Warrington. Stelling. Kupermann. Wester.G. Speculations on the Design of a Containment Vessel with a Hot Liner for Use with Fast Reactor Systems I. Illinois. London. Risley.P. UK. Head. Thomas.L. Middlesex.S.G.B.A. Hochtemperatur-Reaktorbau GmbH. Concept and Research for a PCV for the LMFBR H 8/1* H 8/2 H 8/4 H 8/5 H 8/6 H 8/7 58 Transient Analysis of LMFBR Reinforced/Prestressed Concrete Containment A. Germany Structural Analysis of Cellular Blocks for a Prestressed Cast Iron Reactor Pressure Vessel R. H.. Nuclear Power Co. Comparison of Transient PCRV Model Test Results with Analysis A. J. Middlesex. S. Illinois.S.. Sunnyvale. D. Fed.J. Stephenson. Wolff.EA. Northwestern University. T. (Risley) Ltd. P.. Staatliches Materialprüfungsamt NW..H.-A. U. Z. Nuclear Power Co. Taylor Woodrow Construction Ltd. Schwiers. (Whetstone) Ltd. Evanston. U. Albeson. Belytschko. Argonne. Bazant.LI. Germany Session H 8. Whetstone. Southall. Argonne National Laboratory. Taylor Woodrow Construction Ltd.H. Gluekler.S. . Culcheth. Argonne. Imperial College. U.H. H. K. Argonne National Laboratory. Northwestern University. General Electric Co. Ma. Blundell. Argonne. H. Dortmund. Fed. Construction and Pressure Test of a PCIV Gas Storage Vessel for the THTR-300 E. Ahmed. Rep. U. Marchertas. Evanston. Design and Development of a High Thermal Conductivity Concrete for the Sodium Cooled Fast Reactor R. Belytschko. U. USA. Mannheim.H 7/3 H 7/4 H 7/5 Design. U.L.K. Marchertas. Advanced Reactor Systems Department. Ultrasonic Testing of Large Blocks for Prestressed Cast Iron Pressure Vessels H. Thermal and Thermal Stress Analysis of a Pool Type LMFBR Deck Structure M.KA.H.. Local Thermal and Structural Behavior of Concrete at Elevated Temperatures E.A. T. Illinois. Davies.K. Siempelkamp. Leicester.A. Krefeld. Lethert. Illinois. Rep.B. W. Illinois. Southall. California. Argonne National Laboratory.. Warrington. TABLE OF CONTENTS Division J. LOADING CONDITIONS AND STRUCTURAL ANALYSIS OF REACTOR CONTAINMENT Session J 1. General Design Criteria and Containment Selection J 1/1* J 1/2 J 1/4 J 1/5 J 1/6 J 1/9 Current Summary of International Extreme Load Design Requirements for Nuclear Power Plant Facilities J.D. Stevenson, J.D. Stevenson Consultants, Cleveland, Ohio, U.S.A. Evaluation of Load Combination Equations for ASME Section III Division 1 Components S.W. Tagart, Jr., Nuclear Services Corporation, Campbell, California, U.S.A. A Probabilistic Approach to the Design of Nuclear Containment Structures P. Petrinä, Sargenta LundyEngineers, Chicago, Illinois, U.S.A. Risks of Nuclear Containment Structures due to Aircraft Crashes and Earthquake Loadings J. Bauer, Technische Universität München, München Fed. Rep. Germany withdrawn Design and Construction of the Prestressed Concrete Containments of the French Standard 900 MWe PWR R. Bordet, J.L. Costaz, J.F. Laboudigue, Electricité de France, SEPTEN, Paris, France Experience in the Safety Assessment of the SNR-300-Containment J. Langhans, Gesellschaft für Reaktorsicherheit, Köln, Fed. Rep. Germany Notes: — The sign (·) designates Invited Lectures. — A title mentioned on the Table of Contents but not followed by a summary or a paper means that the paper was not available at the time of finishing of the book. — A paper number missing in the numeral order means that the paper was cancelled or withdrawn. 59 Session J 2. BWR Containment Design J 2/1* Design Loads, Loading Combinations and Structural Acceptance Criteria for BWR Containments in the United States N.W. Edwards, NUTECH, Inc., San Jose, California, U.S.A. J 2/4 A Theoretical and Experimental Study of the Structural Responses to Safety/Relief Valve Discharge Loads T. Henriksson, J. Fredell, ASEA-ATOM, Västerås, Sweden J 2/6 MARK II Containment Dynamic Analysis and Assessment for Hydrodynamic Loads M. Michail. G. Shah, L.-O Hua, Bechtel Power Corporation, San Francisco, California, U.S.A. withdrawn Response of a BWR MARK II Containment Structure to Chugging Loads B. Bedrosian, M. Ettouney, Burns & Roe, Inc., Woodbury, New York, USA. Structural Dynamic Analysis of SRVA Loads for BWR MARK III Containment System H.O Han, C.J. Lin. Gilbert Associates, Inc., Reading, Pennsylvania, U.S.A. Mathematical Modeling of a MARK lll/BWR-6 Containment for LOCA and SRV Analysis P.A. Larkin, R.E. Stoner, R.L. Beck.T.F. Huang, Bechtel Power Corporation. Gaithersburg, Maryland, U.S.A. J 2/7 J 2/8 J 2/9 Session J 3. Concrete Containment Design and Analysis J 3/1 J 3/2 J 3/3 J 3/4 J 3/5 60 Application of the Split-Rigidity Concept to Concrete Cracking in Reactor Containment Design K.P. Buchert, S.K. Sen, Bechtel Power Corporation, Gaithersburg, Maryland, U.S.A. Behaviour of Concrete Containment under Over-Pressure Conditions R.J. Atchison, G.J.K. Asmis, F.R. Campbell, Atomic Energy Control Board, Ottawa, Ontario, Canada Effect of Crack Formation Process and Tension Stiffening on Thermal Stresses Relaxation in Reinforced Concrete Containments G. Macchi, Università di Pavia, Pavia, D. Sangalli, Studio Tecnico Macchi-Papini e C s.a.s.. Mi/ano, Italy Effective Tensile Stiffening in Prestressed Concrete Wall Segments L. Chitnuyanondh, S. Rizkalla, D.W. Murray, J.G. MacGregor, University of A/berta, Edmonton, Alberta, Canada Modelling and Predicting Behavior of Prestressed Concrete Secondary Containment Structures Using BOSOR 5 D.W. Murray, L. Chitnuyanondh, C. Wong, University of Alberta, Edmonton, Alberta, Canada J 3/7 J 3/8 J 3/9 J 3/10 J3/11 Analysis of Concrete Containments for Non-Linear Strain Gradients A. Walser, D.J. Carreira, Sargenta Lundy Engineers, Chicago, Illinois, U.S.A. Computer Plotting and Calculation of Containment Prestressing Cables .. Benamou, Electricité de France, SEPTEN, Paris, .. Picaut, P. Pouyet, Coyne & Bellier, Paris, France Lateral Rigidity of Cracked Concrete Structures A. Castellani, C. Chesi, Politecnico di Milano, Milano, Italy Thermo-Elastic Stress Analysis of Containment Wall Penetrations Using Improved Finite Element Formulation D.T. Ramani, A. Dimopoulos, Sargent & Lundy Engineers, Inc., Chicago, Illinois, U.SA. B. M. Hegl in, Beratung für Statik, Dynamik und Energie, Dürten, Switzerland Elastoplastic Analysis of Internally Pressurized ,Cut-andCover Type Underground Nuclear Reactor Containments G. Mahrenholtz, Technische Universität Hannover, Hannover, Fed. Rep. Germany, D.V. Reddy, W. Bobby, Memorial University of Newfoundland, St. Johns, Newfoundland, Canada Session J 4. Concrete Containment: - Testing Behavior J 4/1 * J 4/2 J 4/4 J 4/5 Design Concept of Concrete Containment Vessels for Shear and Thermal Stresses K. Ichikawa, Shimizu Construction Co., Ltd., Tokyo, Y. Aoyagi, Central Research Institute of Electric Power Industry, Abiko-City, Chiba, Y. Watanabe, The Japan Atomic Power Company, Tokyo, Japan A Test of a Model of a Thin-Walled Prestressed Concrete Secondary Containment Structure S. Rizkalla, S.H. Simmonds, J.G. MacGregor, University of Alberta, Edmonton, Alberta, Canada Behavior of Reinforced Concrete Containment Models under the Combined Action of Internal Pressure and Lateral Force T. Uchida, N. Ohmori, T. Takahashi, S. Watanabe, Kajima Institute of Construction Technology, Tokyo, H. Abe, Y. Aoyagi, Central Research Institute of Electric Power Industry, Abiko-shi, Chiba, Japan Behaviours of Reinforced Concrete Containment Models Under Thermal Gradient and Internal Pressure Y. Aoyagi, H. Ohnuma, Central Research Institute of Electric Power Industry, Abiko-shi, Chiba Y. Yoshioka, K. Okada, M. Ueda, Takenaka Technical Research Laboratory, Tokyo, Japan 61 A. Righetti. Blacksburg. S.S. Graubner. Central Research Institute of Electric Power Industry. Session J 5. Yamada. California. Abiko City.J 4/6 J 4/7 J 4/8 J 4/9 Design Method of Shell Wall End of Reinforced Concrete Containment Vessel (RCCV) Against Radial Shear Y. Germany J 5/6 J 5/7 J 5/8 62 . Lazzeri. Tokyo. Chiba. Inc. Evanston. Shimizu Construction Co. Fed. Università di Genova. Singh.. P. U. Erlangen. M. Genova. Bozzo.P. Tokyo. K. Japan J 5/4 Plate on Elastic Foundation Subject to Thermal Loading H. Los Angeles. Tokyo.. Genova. Po/itechnika Warszawska.Tabakman.A.J. Virginia Polytechnic Institute and State University. Japan An Experimental Approach to the Design of Network Reinforcement Against In-plane Shear in Reinforced Concrete Containments Y.A. O Isobata. Scibak.. Berro. Research Laboratory of Shimizu Construction Co. Rep. Gambarova.D. Aoyagi. Singh.A. Tanaka. AMN S. Ltd. Donten. Technical Research Laboratory of Maeda Construction Company. U. Illinois.A. Y. Warsaw. Sadowski. G. Chicago. Sargent & Lundy. Japan Results of Strength Tests on a 1:10 Model of Reactor Containment K. Illinois. Self Limiting Loads for Concrete Structures L.p. Bechtel Power Corporation. Yamakawa. Danisch.. Lin. Inelastic Analysis and Design of Ductile Structures Submitted to Induced Vibrations of Extreme Events R. Aoyagi. Bazant. Chiba. Knauff. Central Research Institute of Electric Power Industry. Ltd. A.A.S. Poland Ductility and Failure of Net-Reinforced Concrete Shell Walls Z. Virginia. U. Design and Analysis of Salbs and Structures J 5/2 Static and Dynamic Analysis of Reactor Containment Base Mat on Elastic Foundation under Transient Loads T. Italy Analysis of Drywell Floor Slab for Random Lateral LOCA Loads on Downcomers M.. W. F. N. Abiko City. U. Valathur. M. Kraftwerk Union AG.P. Northwestern University.S. Engineers. E. Fontenayaux-Roses.L. Bantle. A. Germany Elasto-Plastic Analysis of Nozzle Intersections in Reactor Containments J. Fed. Rep. Sweden Stability Investigations of Spherical Steel Shell Containment A. S.M./Département de Sûreté Nucléaire.Experimental and Numerical Analysis J./CEN-Saclay STA. Berriaud. Laboudigue. Rep. J. Avet-Flancard. Swedish State Power Board.C. France 63 . France Impact and Impulsive Loading on Thin Shell Structures Y. Ispra. Dulac. Germany Performance of Scandinavian BWR-Containrnents During Pressure Tests A. Crutzen. S. Paris. Germany Session J 7. J. Stockholm.W. ICEN. Universität Stuttgart. Ramm. Costes. SEPTEN.R. Germany Optimization of the Containment Nozzles A. CE. P. CEA /CEN-Saclay DEMT. Rep. Fed. Sättele. Bundesanstalt für Materialprüfung (BAM). Brandes.Session J 6. Jamet. CEA. Kraftwerk Union AG. Fed. Fontenay-aux-Roses. Bundesanstalt für Materialprüfung (BAM). Berlin (West). Bantle. E. Bornscheuer. Andersen. Costaz. DSR. Kraftwerk Union AG. Gif-sur-Yvette R. Vällingby. Stuttgart. France A Realistic Structural Analysis of the Integrity of the Liner of Reinforced and Prestressed Concrete Containments F. Herter. J. F. Berlin (West). Frankfurt am Main. Italy Experimental Investigation of Reinforced Concrete Behaviour due to Impact Load K. Boye-Møller. Habip.A. Germany Inelastic Behavior of Reinforced Concrete Slabs Subjected to Impact Loads . Impact Load Analysis and Design I J 7/1 * J 7/2 J 7/3 J 7/4 Test and Calculation of the Local Behaviour of Concrete Structures under Missile Impact C. Structural and Leak Testing and Design of Containment Components J 6/1 J 6/3 J 6/5* J 6/6 J 6/7 J 6/8 J 6/9 A Containment Wall with Integrated Venting D. Fed. Commission of the European Communities. Verpeaux. Electricité de France. P. Universität Stuttgart. Frankfurt am Main. J. Buchhardt. Andersen. L. K. Rep. Brandi. CEA. Gif-sur-Yvette. Ispra Establishment. P.W. Engelbrektson. Stuttgart. Limberger. Hoffmann.M. Bornscheuer.F. VBB Vattenbyggnadsbyran. Germany Experimental Study of a Spherical PWR-Containment with Geometrical Imperfections at the Welds F. U. Toronto. Culcheth.S. Germany Dynamic Measurements During the Test Series with the GasOperated Accelerator at Meppen H. Weithäuser. U. Davies. F. J 7/11 Energy Absorbing Missile Barrier Systems A. Function Behavior of a Gas-Operated Accelerator for Kinetic Energy Projectiles H. R. Safety and Reliability Directorate.M. Zerna .P. New York.H. Sage.LI. Germany Approximate Calculation of the Impact of Missiles onto Reinforced Concrete Structures and Comparison of Test Results W. Bochum. E. Burns & Roe.S. P. Germany Experimental Investigations to Determine the Kinetic Ultimate Bearing Capacity of Reinforced Concrete Slabs Subject to Deformable Missiles W. Rep. Radini. Rep. Impact Load Analysis and Design II J 8/1 J 8/2 J 8/3 J 8/4 J 8/5 J 8/6* 64 Scaling Laws Applied to Impact Testing and Computer Assessments Made to Compare Tests at Two Scales I.Dr. Meschkat. Fed. Middlesex. Frankfurt IMain. Rep. Fed. Germany . Bechtel Power Corporation. U. E.. Inc.M. H. Stanqenberg. Woodbury.R. Hochtief AG. A. An FRGMRT-UKAEA Co-operation in Tests to Validate Computer Codes and Scaling Laws F. Buttmann. Maryland. Ingenieurbüro Prof. Fed. J 7/9 Analysis of the Overall Structural Behavior due to the Impact of Deformable Missiles M. Carlton. Meschkat. B. Ontario Hydro. Hsueh. Danay.J.K. Canada Session J 8. Brown Boveri & Cie AG. J. Rep. Riech.J 7/5 Impact Testing of Steel Fibre Reinforced Concrete Slabs with Liner F. Gaithersburg. Rep.K. für Reaktorsicherheit. Heine. Riech. Rüdiger. UKAEA. J.J.A. D. R. Germany J 7/6 Behavior of Reinforced Concrete Barriers Subject to the Impact of Turbine Missiles P.S. Warrington.. Fed. Jonas. Meppen. P. Lancashire. H. Schellenbach. Foulness. Sen. Rüdiger. Pfeiffer..A. Atomic Weapons Research Establishment. R.K. Köln. Jonas. McMahon. Essex. Meppen. Hochtief AG.K. Fed. Germany Response of Reinforced Concrete Targets to Impacting Soft Missiles. Meyers. Southall. O'Brien. T. Mannheim. S. Taylor Woodrow Construction Ltd. Tang. U. Deans. Ontario. Ges. Ettouney.R.L. Frankfurt/Main. J. Electric Power Research Institute. U. Chiba. Kappler. Bruxelles. Cheshire. J. Gouda. Curso de Pós-Graduacão em Engenharia Civil.K.. P.D. Technische Universität München. v. Kost. N. Miyamoto. Utrecht. The Netherlands Full Scale Turbine-Missile Casing Exit Tests withdrawn H. J. Dorchester. Rungis-Silic. Sharpe. Babcock-Brown Boveri Reaktor GmbH. Chedmail. Ibaraki. Atomic Energy Establishment.d.F. München.I. J. Hoek. UKAEA.J. Fed. H. Brown. Bauer. Rep. New Mexico. Kamil. Renard.-J. Aircraft Impact Load J 9/1 J 9/2 J 9/3 J 9/4 Analyses of Critical Structures and Contained Equipment for Aircraft Impact Loadings H. G. Jowett.A. Riera. RS. Japan Fall of a 75 ton Fuel Element Container in a Storage Pool and the Subsequent Loading of the Pool Walls C. Porto Alegre. Rep. Carter.. Engineering System International S. Experimental Study on Strength of Steel Plates Subjected to Missile Impact H. Bredero's Bouwbedrijf Nederland B.SA. Bianchini. J. Mannheim..G.J 8/7 J 8/8 J 8/9 J 8/11 J 8/12 Local Failure of Reinforced Concrete under Missile Impact Loading M.. Experimental Validation of the EURDYN and CADROS Finite Element Codes for the Calculation of Metal Target Response to LowVelocity Missiles A. Dorset. Session J 9. Toshiba Corporation. Belgium 65 . J. Offenbach (Main). R.C. U.SA. Science University of Tokyo. Inc. H. v. Electrobel S. Curtress. Albuquerque. Palo Alto. H.R. N. Toshiba R Et D Center. Fed. U. G.V.T.A. Yoshimura. U. Schamaun. Krutzik. Noda-shi.. Inc. N. Physics International.. Culcheth. Germany Numerical Analysis of the Local and Global Structural Response of a Reactor Building Under Airplane Crash Loading J. Physics International. Germany A Critical Reappraisal of Nuclear Power Plant Safety against Accidental Aircraft Impact J. Warrington. UKAEA. M. Kraftwerk Union AG.J. Gouda. Schuëller. Pittner.E. S. Engineering Decision Company. Yoshizawa.L. Winfrith. Ohte. S.d. Frankfurt (Main). Neilson. California. Hitachi Ltd. Engineering Decision Analysis Company. Palo Alto. Sandia Laboratories. Dubois.K. Chiba. Florie. Ree. S.L. California. Hitachi Research Laboratory. Shankar. France J. G.J. Sliter.. Safety and Reliability Directorate. Shida. Kawasaki-shi. Brazil The Effect of Crash Zones in the Design of Nuclear Structures K.D. J.­H. Frank­ furt/Main. Fed. Ree. Électricité de France. Direction de l'Equipement. P. Pohl. Deterministic and Probabilistic Studies A. Kraftwerk­Union AG. Ankara. Middle East Technical University. T. France J 10/2 On the Dynamic Analysis of Axisymmetric Structures Considering Non­Axisymmetric Concentrated Masses K. Fed. TÜV­Baden. Krutzik. Utrecht. G. Direction des Etudes et Recher­ ches. The Netherlands Comparison of Response Spectra for Aircraft Impact Calculated by a Beam­Model and a 3D­Shell­Model J. Response of an Embedded Reactor Containment to Underground Blast Loading Y. Linder.K. Lannoy. Kot. Ingenieurbüro Dynamik spezieller S trukturen. Bochum.V. Krivy.d. Hoek.J. Gesellschaft für Reaktorsicherheit.d. Kaiser. Germany Airplane Crash and External Explosions — Design Standards in the Federal Republic of Germany M. Α. Germany Nonlinear Behaviour of Reinforced Concrete Shells under Aircraft Impact F. G. Ruhr­Universität Bochum. Golan. Rep.S. v. Gouda. Physics International. Consultant. Winkel.. Rep. Philip. Kiciman. N. Germany . Fed. Gobert. Illinois. Rep.J 9/5 J 9/6 J 9/7 J 9/8 Analysis of the Behaviour of a Concrete Structure due to an Air­ plane Impact and the Effects of the Reinforcements H. N. D. Kivity. M. Offenbach (Main). Control Data GmbH.A. Lemgo.M. Kraftwerk Union AG. Paris. Ger­ many J 10/4 J 10/5 J 10/6 J 10/7 66 Response of Containment Structures to Air Blast CA. Turula. W. Offenbach/Main. Schrader. Köln. U. v. Rep. Impulsive Load Analysis and Design J 10/1* Evaluation of H azards from Industrial Activities near Nuclear Power Plants. Argonne. Bredero's Bouwbedrijf Nederland B. Bork. W. Kuntze. Frankfurt/Main. Tel Aviv.J. Mannheim. Fed. Rep. Koch. Électricité de France. Argonne National Laboratory. Israel Finite Element Analysis of Reactor Containments under Blast Loa­ ding O. Turkey Pressure Vessel Rupture and Resulting Pressure­Wave­Loading of Surrounding Concrete Structures Calculated with the PISCES ­2 DELK­Code V.. Fed. Krutzik. Köln. S igolev Ltd. Kerntechnischer Ausschuß (KTA)­Geschäfts­ stelle bei der GRS . Germany Session J 10.. Saint Denis. Ibaraki.R. S argent & Lundy Engineers. Switzerland withdrawn K 1/6 Input Criterion for Seismic Analysis of Nuclear Power Plants D. PK.A.S. Genova. M. Watabe. Tokyo. Milano.S. ■ The sign (·) designates Invited Lectures. T. Tokyo. U. L.C. U. S an Francis­ co. Califor­ nia. K. Chiba. Watabe. A title mentioned on the Table of Contents but not followed by a summary or a paper means that the paper was not available at the time of finishing of the book. Ohsaki. Chicago. Davis. M. U. Italy K 1/8 A Model for Soil Behavior under Monotonie and Cyclic Loading Conditions Y. Degen.S A. Oliver. Inc. Tohdo. 67 . Politecnico di Milano. Building Research Institute. R.. Ibaraki. Ltd. Motor­Columbus Consulting Engineers. Poland R. Hueckel. Japan K 1/2 Generation of Simulated Three­dimensional Earthquake Ground Motions M. University of California. U. Dafalias. Lazzeri. Singh. Masao.. Baden. California. Iwasaki. Japan K 1/5 Artificial Accelerograms for Multiaxial Earthquake Excitation P.S .M. Polish Academy of Sciences..A.F. Berkeley. Gupta. Toda Construction Co. AMN S . K Ml H ysteresis Behaviour of Soils and Rocks T. I. Ground M otion K 1/1* Analyses on Various Parameters for the Simulation of Three­ dimensional Earthquake Ground Motions M. Italy K 1/10 A Class of Models for Identification and Simulation of Earthquake Ground Motions R. University of California. Fujita Corporation. Building Research Institute. Nuclear Power Plant Division.S. California. Akky.. Tokyo. K 1/4 Phase Characteristics of Earthquake Accelerogram and Its Appli­ cation Y. 0. Idriss. Japan K 1/3 Primary Variables Influencing Generation of Earthquake Motions by a Deconvolution Process I. Cecconi. Pister. Toda Construction Co.M. Giuliano. Tokyo. M. A paper number missing in the numeral order means that the paper was cancelled or withdrawn. Warsaw. V. Genova. Agrawal.A.pA.. SEISM IC RESPONSE ANALYSIS OF NUCLEAR POWER PLANT SYSTEM S K(a) Session K 1 . Illinois.. Ltd. Università di Genova.TABLE OF CONTENTS Division K. Institute of Fundamental Technological Research. University of Tokyo. G. Nova. S. Ohkawa. Tohdo. Woodward­Clyde Consultants. K 1/9 On the Effects of Using Wide Range Earthquakes S. Pezzi. K 3/2 Systems Analysis Methods Used in the Seismic Safety Margins Research Program G.E.A. Atchison. University of Tokyo. Culcheth. Long Beach. California.K. H.A. Ontario. Massachusetts. Long Beach. R. Philip.G. Lowe and Garrick. Cornell. Asmis.A. Ohio. 68 . Fontenay-aux-Roses.J. Risk Analysis I K 2/1* K 2/2 K 2/3 K 2/4 K 2/5 K 2/6 K 2/7 K 2/8 Probabilistic Seismic Safety Study of an Existing Nuclear Power Plant R. Japan KTA 2201 .D. University of Tokyo. Cambridge.F. UKAEA Safety and Reliability Directorate.S.K. Fugro. Wells. U.J. J.H. Ottawa. Case Western Reserve University. Cleveland. Engineering Decision Analysis Company. Perla. Köln. Probabilistic Approach of Reference Seismic Ground Motions D.S. California. Risk Analysis II K 3/1 * An Overview of the Seismic Safety Margins Research Program R. U. Inc.S. USA. CE. California. Irvine. Atomic Energy Control Board. Inc. Warrington. California. San Francisco. California. Cummings.B. Canada Session K 3. France Probabilistic Evaluation of the SSE Design Spectrum for a Nuclear Power Plant Site: A Case Study R. Alderson.J. Gorman. CA./CEN-DSN. Massachusetts Institute of Technology. Stevenson. California. R.D. EDS Nuclear. Tokarz. Stevenson Consultants. Crouse.E. Campbell. Shibata. J. C. On a Method of Evaluation of Failure Rate of Equipment and Pipings under Excess-Earthquake Loadings H. Lawrence Livermore Laboratory..Session K 2. Probability of Failure of Piping Designed to Seismically Induced Emergency and Faulted Condition Limits M. U. Institute of Industrial Science. A Method for the Estimation of the Probability of Damage due to Earthquakes M. Pickard.D. California. Smith F. Livermore. Lawrence Livermore Laboratory. M. Guzman.An Approach to Reduction of Seismic Risk G.. A. Vaish. Kerntechnischer Ausschuß (KTA)-Geschäftsstelle. Bork. Irvine.A.Seismic Design Standards in the Federal Republic of Germany G. Wheaton.S.A. Fed. Ohio.. Costes.D. Kennedy. Consultant. Cleveland. Rep. U. Livermore. Germany The MCE (Maximum Credible Earthquake) . Okamura. U. Tokyo.A.P. H. R. Tokyo. Inc. J. Tokyo. P. Κ 3/6 Soil Structure Interaction Analysis for the US NRC Seismic Safety Margins Research Program J.A. Dong. Lawrence Livermore Laboratory. V. Lawrence Livermore Laborato­ ry. Session Κ 4.S. Κ 3/9 Definition of Component and Structural Fragility for Use in the Seismic Safety Margins Research Program R. Livermore. U. California.S. Livermore. Κ 3/5 Attenuation Relationships of Peak Ground Acceleration Versus Magnitude and Distance Considering Magnitude and Distance as Random Variables C. Κ 3/7 Major Structural Response Methods Used in the Seismic Safety Margins Research Program CK. California. Reading. Livermore. U. Li­ vermore.A. D. Livermore. Bernreuter. D.S. Lawrence Livermore Laboratory.J. Κ 3/4 Expert Opinion Encoding in Seismic Hazard Analysis OP. Califor­ nia. Califor­ nia. U. Japan Integrated Structural Design of Nuclear Power Plants for High Seismic Areas P. Chou. D.A. Bernreuter. TERA Corporation. Livermore. Berkeley.Y. Berkeley. Chung. Institute of Industrial Science.H. California. U.SA. Design Concepts Κ 4/1 * K 4/2 On Fundamental Concept of Anti-Earthquake Design of Equipment and Pipings H.S.A. Johnson. Shibata. Mortgat. TERA Corporation. Rieck. University of Tokyo. Lawrence Livermore Laboratory.A. Κ 3/10 Reserve Seismic Capacity Determination of a Nuclear Power Plant Braced Frame with Piping T. Vagliente.A.L..A. Livermore. California. Lawrence Livermore Laboratory.S.S. KW.G.L.K 3/3 Development of Seismic Input for Use in the Seismic Safety Mar­ gins Research Program D. Lawrence Livermore Laboratory. Bernreuter. Lawrence Livermore Laboratory. USA. T. Califor­ nia. U. Cali­ fornia. Johnson. Pennsylvania. Cali­ fornia. Mortgat.S.N. To­ kyo. Nelson. Lawrence Livermore Laboratory. Lo. Gilbert Associates. Inc. U. Campbell.A.J. U. 69 . U. Κ 3/8 Subsystem Response Determination lor the US NRC Seismic Sa­ fety Margins Research Program J. Japan Atomic Power Company. M.J. Kato. Livermore.L. Cali­ fornia. Seed. G.W. von Riesemann. F.A.J. Irvine. Inc. Richter. P. Dostal. Belgium Soil-Structure Interaction: Modeling Effects on Structural Response P.SA. California. J.K 4/3 K 4/4 K 4/5 K 4/6 K 4/7 Concepts for Seismic Response Attenuation of Nuclear Power Plant Containments R.. Kamil. Engineering Decision Analysis Co. U.K. CF. U.. Reddy.A.S. Sunnyvale. California. Kraftwerk Union AG. P. P.V.S. U.. Massachusetts. Part 1: Station Arrangements.A. Sun. R. Sfone & Webster Engineering Corporation. California. . Electrowatt Engineering Services Ltd.C. Bruxelles.B.V.A. Kost. General Electric Co. California. Irvine.SA. Fluor Engineers and Constructors. Sharpe. Memorial University of Newfoundland. H. Thangam Babu. Reeves. Palo Alto.P. California. Webster.. California. Berkeley. Albuquerque.J. M. Krutzik. Arockiasamy. General Electric Company. San Francisco. Renard. U. N.. Pal..S.A. St. W. Arnold. Stetson. Switzerland Seismic Input for Soil Structure Interaction Analysis E. Zürich. Obernhuber.S. Wolf.A. P. Engineering Decision Analysis Company. California..A. California. Soil-Structure Interaction I K 5/1* K 5/2 K 5/3 K 5/4 70 Travelling Wave Effects in Soil-Structure Interaction J. University of California. Berger. Canada Session K 5. U. M. Advanced Reactor Systems Department. Palo Alto. Dames & Moore. New Mexico. Considerations in the Design of Nuclear Power Plants in High Seismic Regions.D. Rep. San Jose. Inc. Electrobel S. Sandia Laboratories. Kennedy. Newfoundland. Alternative Structural Systems for High Density Fuel Storage Racks in Existing Facilities J. Probabilistic Seismic Fluid-Structure Interaction of Floating Nuclear Plants Platforms M. Johns.P. Reed. An Investigation into Seismic Design Feasibility of Pool-Type LMFBR's N. Banerjee. Germany Investigation of the Treatment of Damping in Soil-Structure Interaction Analysis H. U. D. Offenbach.B. Part 2: Component Qualification A. Fed. Inc. Inc. Engineering Decision Analysis Company. Nuclear Energy Operation. Boston... V. H . S witzerland 71 .M. Kraftwerk Union AG. Structure­to­Structure Interaction Analysis for a Nuclear Power Plant C. Cofer. Waas. Lam.A. Italy The Finite Element Complex Response Method for Solving Prob­ lems of Embedded Multiple Structures J. A. California. Università di Genova. Brennan. Germany The Influence of Uplift and Sliding Nonlinearities on Seismic Re­ sponse of a Small Test Reactor Building L. Cheshire. Weber.K 5/5 Comparison of Soil­Structure Interaction by Different Ground Models T. Krutzik. Ohio. U. Engineering Decision Analysis Company.S . California. J. S witzerland Building­Soil­Building Interaction in Seismic Analysis of Nuclear Power Plants A. H. Offenbach. Boveri & Cie. Mukherjee. Germany Dynamic Interaction of Adjacent Structures Founded on Layered Soil G.J. Stura. Michigan. U. R.A. Nuclear Power Company (Risley) Limited.N. Inc. Tanaka. D. Akron. Engineering Decision Analysis Company. Y.M. Inc. California. Kuwabara.. Mueller. Rep. Scavuzzo. Taisei Corpo­ ration. Baden. Germany Nonlinear Analysis of a Deeply Embedded Power Plant Building Subjected to Earthquake Load S. Ahmed. Y. Palo Alto. D. G. Seismic Design Method for Arbitrary Propagating Waves M. The University of Akron. Del Grosso. W. Agüero. Hoggatt. Frank­ furt (Main).K.C. Fed. Motor Columbus Consulting Engineers. New York.. Kyushu. Rep. Ogiwara. U. Vardanega.S. Kyushu Electric Power Company. General Motors Institute. Suwabe.A. Soil-Structure Interaction II Κ 6/1* Κ 6/3 Κ 6/4 Κ 6/5 Κ 6/6 Κ 6/7 Κ 6/8 Κ 6/9 Soil Structure Interaction Analyses by Different Methods G. Inc. Waas. Fed. Japan Κ 5/6 Torsional Structural Response from Free­Field Ground Motion P. Hochtief AG. K. Furrer. Warrington. Rutherford. Woodbury. Vallecitos Nuclear Center. Kost.S .J. Κ 5/7 Session Κ 6. Hochtief AG. Engineering Decision Analysis Company. Tokyo.A.S A. Sharpe. Takemori. Pleasanton. Genova.L. Kamil. Frankfurt am Main. Fed. Ettouney.H.. U. Rep. Risley. Parker. R. Gantayat. Frankfurt am Main. Palo A/to. Burns and Roe. Baden. K. N. A. H . Detroit. Kamil. General Electric Company. Investigation of the Influence of Interaction of Two Adjacent Struc­ tures on Their Responses A.. Brown.A. D. C. U. St.N.V. S.S.. Ontario Hydro. Bechtel Power Corporation.SA. Mark. Santa Monica. Ontario. J. Bechtel National. Koori. Tow.S. Inc. Canada . Tokyo. Howard. J. U. Chiyoda Chemical Engineering & Construction Corporation. Pennsylvania. General Atomic Company. Westinghouse Electric Corporation. Pittsburgh. S. U. California.H. Newfoundland. Uchiyama. D. Seismic Response Analysis for a Deeply Embedded Nuclear Power Plant W.J. and Software.SA. California. California.A. Seismic Stresses in Buried Piping of Arbitrary Configuration J. San Francisco. El-Tahan. California.M. Toronto. California. PWR System Division. Masao. Tanaka. Japan Seismic Response Comparisons for an Embedded High Temperature Gas-Cooled Reactor (HTGR) on a High Seismic Site W. Takasaki. Tokyo Electric Power Co. U. Memorial University of Newfoundland. San Francisco. K. P. Tang. Systems. California. Lawrence Livermore Laboratory. Yamamoto. California. San Francisco.W. Y. John's.. Johnson. Ltd. Underground Structures K 7/1 * K 7/2 K 7/3 K 7/4 K 7/5 K 7/6 K 7/7 K 7/8 K 7/9 72 Earthquake Response of Nuclear Reactor Building Deeply Embedded in Soil T.J. Kawasaki.. III. U.. Celebi. Pagay.K. U. Bechtel Power Corporation. Chatterjee. Japan Seismic Response of the ' Cut-and-Cover' Type Reactor Containments Considering Nonlinear Soil Behavior H. Bechtel National.. M. Fujita Corporation. Chatterjee. Canada Seismic Design of Long Underground Structures S. Loceff. Chen. D. Reddy.A. ANCO Engineers. F. T. San Francisco. Science. Yokohama. M. Inc. San Diego. Day. Ibáñez. S. Livermore.E. Inc.Session K 7.S. Tokyo.H. Analytical and Experimental Investigation of the Dynamic Response of Underground Nuclear Power Plants G. California. Inelastic Seismic Analysis of a Deeply Embedded Reinforced Concrete Reactor Building M. Kajima Institute of Construction Technology. Schlafer. Y.A. Experimental and Analytical Studies of a Deeply Embedded Reactor Building Model Considering Soil-Building Interaction (Part I) H. Ohta. Deans. La Jolla. . Critical Seismic Response of Nuclear Reactors R.A. Berkeley. Kozeki.H. Nonlinear Analysis of a BWR Reactor Building Subjected to Both Thermal and Earthquake Loadings K.S . L. Inc. Reading. Madison. New York. Ruhr­Universität Bochum. G. Sigal. G. Kajima Corporation. New Jersey.A. A. Westinghouse Electric Corporation.P.A. M. Ujiie. Pennsyl­ vania.E. J.. Guilinger.N. Tokyo.S . Goradia.. Tsugawa. Electrowatt Engineering S ervices Ltd.S.F. Wolf.L. Sackman.J. Philippacopoulos.A.A. Burns and Roe. Germany Response of a Nonlinear System to Various Spectral Excitation Time Decompositions J. Chen. U. U. Koplik. S. Tokyo. New York. Japan Seismic Response of a Structure Subjected to Rotational Base Ex­ citation W.A.. S.. Zürich. Combination of Torsional. Rep. Towards Safe and Economic Seismic Design of Cooling Towers of Extreme H eight W.K(b) Session K 8. Fed.S . Bochum. Muto Institute of S tructural Mechanics. Kurosaki. Advanced Reac­ tors Division. T. Poly­ technic Institute of New York.S.. Curreri. Giuliano. Brookhaven National Laboratory. Califor­ nia. S witzerland Session K 9. P. Böhm. Italy On Upperbound Instructure Response Spectra T. Yun.B. On the Seismic Design Spectra for H eavy Components and Com­ parisons with the Usual FRS Techniques S. Genova. U. Lazzeri.Kelly. U.C.S . Shah. Pittsburgh.E. AMN S . Atalik. U. Response of Structures K 8/1* K 8/2 K 8/3 K 8/4 K 8/5 K 8/6 K 8/7 K 8/8 K 8/9 The Uncoupling Criteria for Subsystem Seismic Analysis C. Drenick. Gilbert/Commonwealth Companies.M. V. Japan Fatigue Analysis Method for Seismic Structural Response A. Mitsui Engineering and S hipbuilding Co. Skrikerud. V. Mutual Pounding of Adjacent Structures During Earthquakes J. Krätzig.J. Rotational and Translational Responses in the Seismic Analysis of a Nuclear Power Plant A. Spain 73 . P. Tokyo. K. Westinghouse Electric Cor­ poration. University of California. Brooklyn. C. Pennsylvania. Muto. Morrone.B. Floor Response Analysis K 9/1* Κ 9/2 Κ 9/3 Equipment Response Spectra for Nuclear Power Plant Sys­ tems J. Bezler. Aihara. Bechtel Espana.S. K. Meskouris. P. Wang. Madrid.A. Ka­ jima Corp.. U. Pennsylvania. PWR S ystems Division. H . Upton. B. Oradell.pA. Cecconi. Ltd. /CEN-Saclay DEMT. AG. Sterkel. University of California.. Japan K 10/9 A Simplified Aseismic Design Procedure for Piping Systems N. Row. California. Powell. Hitachi City. S. Rep.K 9/4 Κ 9/5 Floor Response Spectra Considering Elasto-Plastic Behaviour of Nuclear Power Facilities T. N. The Kansai Electric Power Company. Rep. Mitsubishi Atomic Power Industries.. Ogiwara. Η. Consultant. Sunnyvale.E. U. Hitachi Works.D. California. Berkeley.A. S. Berkeley. Bochum-Linden. T. Brown. Meligi. Kuwabara.G. Germany Κ 10/5 Beam Versus Shell Seismic Analysis of Large Diameter Thin Walled LMFBR Piping N. Mizuno. ARSD. Kraftwerk Union AG. Sargenta Lundy Engineers. Japan 74 .S. Tokyo.Cho. Gotoh. K 10/7 Relation Between Clearance of the Seismic Restraint for Nuclear Power Piping System and Vibration Characteristics T. Hitachi City. Ibaraki-ken.H. U. BoveriS Cie. Gif-sur-Yvette.Missing Mass" Correction in Modal Analysis of Piping Systems G. Krause. General Electric Company.A. F. Kawakatsu. Japan Κ 10/6 Design of Prequalif ied Support Systems Subjected to Dynamic Lo­ ads R. F. Chi­ cago. Response of Piping and Equipment I Κ 10/1* Effect of Energy Absorbing Supports on Seismic Pipe Stresses G. France Session Κ 10. Japan Direct Methods to Calculate Seismic Floor Response Spectra F.. Jeanpierre. Hitachi Ltd. Illinois. Y. USA. Mannheim. Sunnyvale. Germany Κ 10/3 .-R.P. K. Fed. Taisei Corporation.U. Inc. Kitade. Tokyo. Fed. D. Offenbach (Main). California.H. A.. Advanced Reactor Systems De­ partment. Powell.L.A. Raheja. Yoshinaga. Livolant. Hitachi Ltd. Mizuno. M.S. Κ 10/4 Residual Load Method for Modal Analysis of Piping Systems Sub­ jected to Seismic Excitation G. Pal.. U. General Electric Company. Roullier. Hitachi Ltd.S. Pal.A.S. Takemori. Κ 10/2 Comparison of Multiple Support Excitation Solution Techniques for Piping Systems K. CEA. University of California. Y. Leimbach. Califor­ nia. Ontario. K. Inc... Lazzeri. Mitsubishi Atomic Power Industries. No­ tre Dame. Tezduyar. USA. Ibaraki-ken. K. Ontario.C. Ltd. Nakatogawa. Ansaldo.N. Agrone. Pennsylvania.H. Anderson. Genova. Shiraki. Acres. Filippi. Takasago.. Genova R. Toronto. Italy γ§ .. Ontario. Response of Piping and Equipment II K 11/1 * Structural Damping Values as a Function of Dynamic Response Stress and Deformation Levels J.S. T.. Lazzeri. F. K 11/2 Arguments in Favour of Structures. CG. Pittsburgh.T.Session K 1 1 . Canada K 11/8 Coupled Lateral-Torsional Response of Equipment Mounted in CANDU Nuclear Power Plants M. CG. Vivoda.pA. U. Niino. L. Ontario. Ariman. Liu. Toronto.. Ltd. P. Inc. Belgium K 11/3 Investigation on the Design Damping Values for Seismic Analy­ sis of Nuclear Power Plant Piping Systems H. Ohio.pA. To­ kyo..H. Tokyo Electric Power Co. Gunyasu. A. Toronto. Ontario Hydro. M. Duff. Lee.-W.A. Hennart.S. Heidebrecht. University of Notre Dame. P.S. Canada K 11/6 Seismic Response Analysis of Nuclear Power Plant Auxiliary Me­ chanical Equipment C. Tokyo. U. Loceff.B. Italy K 11/11 Seismic and Accident Analysis of Electrical Machinery G. AMN S. Stevenson Consultants.D. J. E. U.F. Ikeda.S. K 11/5 Nonlinear Transient Dynamic Response of Pressure Relief Valves for a Negative Containment System T. Shibata. Mississauga. Japan K 11/4 On Seismically Induced Vibrations of Pressure Vessels with Cu­ touts and Cracks H. Lin. Sheridan Park Re­ search Community. University of Tokyo. K 11/10 Seismic Design of Cableways: A CAD Approach L. PWR Systems Divi­ sion. Tang.A. K 11/7 Seismic Interaction Effects for Steam Generators in CANDU 600 MWe Nuclear Power Plants T.H. Duff. L. Pennsylvania. AMN S. Mitsubishi Heavy Indu­ stries.. Hitachi. Takasago Technical Institute.S. Mississauga. Ishac. T. Tokyo. Toronto. T.T. Ontario..A. Ontario Hydro. Hitachi Works.H. Stevenson.. Atomic Energy of Canada Limited. Nuclear Technology Division. Inc. Ontario. Hamilton. Indiana. Tokyo. Acres. J. Ltd. Sheridan Park Re­ search Community. Ltd.P..D. Aziz. Monfalcone.Hyogo-ken. Tokyo Shibaura Electric Co. Ontario. Cleveland. Strona. Aziz. Westinghouse Electric Corpo­ ration.C. Cambien. Bru­ xelles. Atomic Energy of Canada Limited. McMaster University. Pittsburgh. Systems and Equipment Seismic Qualification by Analysis R. Westinghouse Nuclear Europe. Canada K 11/9 Seismic Analysis of Category I Crane Structures T. Pagano. Westinghouse Electric Corporation. Institute of Industrial Science. J. M. California. Koplik. General Electric Company. Ohio. Babcock Et Wilcox Co. Argonne National Laboratory. Chicago.. U. Curreri.-J. Upton. H. Inc. K 12/6 A Three-Dimensional Computer Code for the Nonlinear Dynamic Response of an HTGR Core M. Germany K 12/8 Explicit Evaluation of the Apparent Fluid Mass at the Vibration of Fluid Filled Cylindrical Tanks D. Kraus. Hochtemperatur-Reaktorbau GmbH. Reich.. Motohashi.S. Argonne.S. Ahmed. Rep. VÖEST-Alpine AG. L.A. Muto Institute of Structural Mechanics.F.C. Bezler.A. Tokyo. Illinois. Kuroda. Sunnyvale. H. Lestingi. Leonard. Kemter. Reactor Core and Fluid Related Structures K 12/1 A Three-Dimensional Test Program for the Nonlinear Dynamic Behavior of an HTGR Core J. Barberton. Muto. Inc. Illinois. K 12/7 Evaluation of Seismic Movements of a Pebble Bed Reactor Core as Basis for Shaking Experiments H. Illinois Institute of Technology. Tokyo. Subudhi. B. Ahmed. Fischer. Electric Power Development Company.Session K 12.S.U. Illinois. K.. U. Japan K 12/4 Seismic Analysis of the Reactor Assembly of a 1000 MWe-LMFBR Pool Reactor C. Glöckner. Linz.S. Mannheim. P. Brown. Electric Power Development Co.SA. U. Goradia. J. Advanced Reactor Systems Department. withdrawn K 12/2 Two-Dimensional Vibration Test and Its Simulation Analysis for a Horizontal Slice Model of HTGR Core K.W. Muto. 76 . S. Subudhi. Ohio S. S. K.F. Koplik. Brookhaven National Laboratory. University of Akron. Argonne. Tokyo. Akron. Chu. Hochtemperatur-Reaktorbau GmbH.S. Curreri.A. Brookhaven National Laboratory. Muto Institute of Structural Mechanics. B. Upton.A. Nuclear Equipment Division. G. Tokyo. Austria K 12/9 Experimental Seismic Test of Fluid Coupled Co-Axial Cylinders M. U. D. Y.. Fed. K 12/5 A Study of Structural Attachments of a Pool Type LMFBR Vessel Through Seismic Analysis of a Simplified Three Dimensional Finite Element Model H. Lasker.A. Argonne National Laboratory. F. Yang. Ma. New York. J. New York. Schmidt. U. U.J.U. Jülich. M. Kasai. Kuroda. Japan K 12/3 Forced Vibration Test of 1/5 Scale Model of CANDU Core K. K 12/10 Evaluation of Fluid Sloshing Effects in Large Suspended Flexible Tanks J. Hochtemperatur-Reaktorbau GmbH. H. Chubu Electric Power Com­ pany. Jeandidier. Kraftwerk Union AG. California. Mizuno. Battelle-lnstitut e.V.M. Takasago. Steinhilber.V. Brennan. Hoffmann. Rep. I.SA. Bedrosian. Habedank. Frankfurt am Main. Moribe. H. Fujita. Jehlicka.J. Mitsubishi Heavy Indu­ stries. New York. Karls­ ruhe. Livolant. Κ 12/12 Dynamic Analysis of Storage Racks for Spent Fuel Assemblies G. K. CEA. Fed. D. C. Swelim. Hyogo Prefecture. Frankfurt am Main.I CEN-Saclay DEMT.. J. Tamaki. Battelle-lnstitut e. Arai. Κ 13/6 Assessment of Seismic Safety for Components of the THTR-300 M We by Shake Tests G.. H. T. A. Karls­ ruhe. N. Rep. General Electric Company. Gauvain. Steinhilber. Germany Κ 13/4 Forced Vibration Test of BWR Type Nuclear Reactor Buildings Considering Through Soil Coupling between Adjacent Build­ ings N. Pleasanton. Japan Κ 13/5 Seismic Qualification of General Electric Test Reactor Safety-Re­ lated Valves C A . Germany withdrawn Κ 13/7 Field Vibration Test Results and Design for Reactor Coolant Piping Systems of ATR . H. Kircher. Dynamic Testing and Qualification Κ 1 3 / 1 * Tests and Calculation of the Seismic Behaviour of Concrete Structures J. Fed. M. Inc. Kushida. Japan 11 . Malcher. France Κ 13/2 Low Level Earthquake Testing of the HDR: Comparisons of Calculations and Measurements for the Reactor Building P. Rep. Rep. U.K 12/11 Dynamic Pressures in Annulus-Shaped Pressure Suppression Pools of Boiling Water Reactors Generated by Earthquake Ground Motions B. L. Nagoya. Fed. K.M. Palo Alto. Fed. Hoggatt. Inc. Malcher.. Sugiyama.S. Kernforschungszentrum Karlsruhe. Vallecitos Nuclear Center. U. Y. Omiya City. Neubrech. Jehlicka. Germany Session Κ 1 3 . Takenaka Technical Research Laboratory. Gif-sur-Yvette. Kernforschungszentrum Karlsruhe. Mannheim. Takasago Technical Institute. Engineering Decision Analysis Company. L. Igarashi.. California.FUGEN" T. L.W. Frank­ furt am Main.Tsushima.A. Ettouney. Mitsubishi Atomic Power Industries. Germany Κ 13/3 Low Level Earthquake Testing of the HDR: Comparisons of Calculations and Measurements for Mechanical Equipment P. Inc. Habip. Reed. Burns and Roe. Wood­ bury. Tokyo... University of New Mexico. U. Poland Κ 13/12 Nonlinear Experimental Response of Semi­Scale Model of Nuclear Power Plant Structures to Simulated Earthquake­Like Ground Mo­ tion C. Shimizu.S A. Albuquerque. Chan. H. K. Tokyo. C. Tokyo. Donten. M. Taisei Corpora­ tion. Shiraki. 78 . M.. Warsaw. Palo Alto. California. Scibak. Osaka. Higgins. Kitade.K 13/8 Vibrational Characteristics of Primary Reactor Coolant System K. Kansai Electric Power Company. Japan Κ 13/10 The Results of Dynamic Tests on 1:10 Model of Containment for Nuclear Reactor K.E. K. W. Fujita. Mitsubishi Heavy Industries. Hagiwara. H oward. Knauff. Politechnika War­ szawska. G.J. P. S anta Monica. Ltd. Kawakatsu. Takasago. Ibáñez.. Tsuchiya. New Mexico. Inc. Ltd. Electric Power Research Institute. Japan Κ 13/9 Experimental and Analytical Studies on Aseismic Design of Ven­ tilation Ducts K. ANCO Engineers.. A Sadowski. H . T. California. Mitsubishi Atomic Power Industries. Suzuki. Rep. Sadakov. S ervice Informatique et Mathématiques Appliquées. Università di Roma. Guelin. Advanced Theories II L 2/1 * Reliability of Elastic­Plastic Structures C. Electricité de France. Fed. Ruhr­Universität Bochum. P. Italy L 2/2* Cyclic Loading on Elastic. Institute of Fundamental Technological Research. Gokhfeld. Université de Grenoble. Chelyabinsk. Martynenko. Lehmann. Needleman. Warsaw.S. Chelyabinsk: U.S. Mroz. 79 .M. Technical University of Denmark.R. Murakami. Poland L 2/3* H igh­Temperature Design of Elastic­Plastic Structures D. USA. Poland Order. France On History Dependence of Stress­Strain Diagrams and Creep Cur­ ves under Variable Repeated Loading D. The sign {*) designates Invited Lectures. M ATERIALS M ODELING AND INELASTIC ANALYSIS OF M ETAL STRUCTURES Session L 1. Boisserie. Chatou. Tvergaard. ■ A paper number missing in the numeral order means that the paper was cancelled or withdrawn. Perzyna. Warsaw. H eat. Intrinsic Dissipation and Inelastic Analysis J.A. Nagoya. Gokhfeld.A. Brown University. O. Advanced Theories I L 1/1* Coupling Phenomena in Thermoplasticity Th. A title mentioned on the Table of Contents but not followed by a summary or a paper means that the paper was not available at the time of finishing of the book. Viscoplastic Structures Z. Providence. Roma. Polish Academy of Sciences. U. Chelyabinsk Polytechnical Institute. Chelyabinsk Poly­ technical· Institute. Tensor Function Approach to Constitutive Equations of Inelasticity S. 3ochum. L 1/4* L 1/5 L 1/6 L 11l Session L 2. Polish Academy of S ciences.R.S . Japan.S . Ger­ many L 1/3' Structural Collapse due to Plastic Instability V. Grenoble. Chikusa­ku. Rhode Is/and.E. M. Gavarini.TABLE OF CONTENTS Division L.S. Institute of Fundamental Technological Research. Flow and Fracture of Inelastic Materials ­ Application to Modern Reactor Technology P. Nagoya University. Lyngby. Den­ mark A. France Shakedown Analysis by Displacement Method and Equilibrium Finite Element H. Liège. University of Southwestern Louisiana. Polish Academy of Sciences. Warsaw.O Hibbeler. Scotland.SA. J. Milano. Polizzotto. Columbus.. L. Glasgow. Czechoslovak Academy of Sciences. C. London. F. Improved Boundary-Integral Equation Method for Time-Dependent Inelastic Deformation in Metals M. General Electric Company.S. New York. U. Bruxelles.R. Methods I L3/1* L 3/2* L 3/3 L 3/4 L 3/5 L 3/6 Mathematical Programming Methods in Engineering Plasticity G.J. Institute of Solid State Physics. Inelastic Analysis of Structures with Applications to Cyclic Loadings J. Nashiro. J.L 2/4* L 2/6 Constitutive Modelling in Plasticity J. Cincinnati. Republic of China Viscous Growth of Thin Pressurized Shells Subjected to Thermal Cycling R. Laflen. Spence. Kosinski. Inglebert. J. Elastoplastic Incrementai Finite Element Analysis of Ductile Metal Structures W. Imperial College of Science and Technology. Cornell University.K. A Nonlinear Endochronic Theory of Cyclic Plastic Hardening and Softening W. Palermo. Mazzarella. Louisiana. University ofStrathclyde. J. Belgium Local Bounds on Dissipation Energy in Shakedown Theory C.H.. Panzeca. Zarka. Ecole Polytechnique. S. T.N. U. Lafayette. Hsinchu. Politecnico di Milano. Session L 4. A Damage Postulate for Nonproportional Cyclic Plasticity B. Battelle Columbus Laboratories. Morjaria.SA. Nguyen Dang. T.-H. Chen. Boyle. U.C.S.T.R. Munro. Italy Finite Deformation. Poland Session L 3. Ohio. Maier. Engel.S. Õ. National Tsing Hua University. Institute of Fundamental Technological Research. U. Kratochvil. U. Mukherjee. Leis.A. . Università di Palermo. Methods II L 4/1* L 4/2 L4/3 80 Elastic-Plastic Analysis Methods for Piping Systems J. G.K. Italy. Prague. Université de Liège. Ohio. Taiwan.N. Ithaca.S.S.R. Palgen. Palaiseau. CEA.A. and M. Lebey. France L 5/2 L 5/3 L 5/4 L 5/8 Stress Intensification and Creep Rupture J. Fracture. Gif-sur. University of Leicester. Glasgow. Boyle. National Engineering Laboratory. Ando. Gif-sur-Yvette. University of Tokyo. Strain Analyses of Nonlinear Crack Behavior at Elevated Temperature by Finite Element Method and Moiré Topographical Method T. L5/1b* Damage Modelling for Prediction of Plastic and Creep Fatique Failure in Structures J.R. Scotland. Columbus. France Dynamic Plastic Buckling of Shells: a Reconsideration of the Vaughan-Florence Analysis G.Yvette.Use for Material Characterization J. Veluswami. Ohio State University. L. Aizawa. M. Henderson. Bui-Quoc. U.L 4/5 L 4/6 L4/7 L 4/8 Fundamental Concepts in the Reference Stress Method for Creep Design J.D. Indian Institute of Technology. A. Lemaitre.K. Université P. East Kilbride.K. University of Strathclyde.K. Millard. Session L 5. G.T. U. Ferguson. Québec. de Pater. Enschede. Roche.CM. P. Scotland. Leicester. F. C. U. Madras. Cachan. Massachusetts. Horvay. Glasgow. Experimental Tests on Ratchet of Tubular Specimens (Torsion and Tension) . Cousseran./CEN-Saclay DEMT. F. Japan A Model of Quasi-Static Crack Growth ina Double Cantilever Beam at Elevated Temperature LS. University of Massachusetts.A. I CEN-Saclay DEMT. Ohio. A Finite Element Formulation for Large Elastic-Plastic Deformations P. India. Montréal.S. CEA. The Netherlands Inelastic Analysis of Piping Systems: A Beam-Type Method for Creep and Plasticity R. Biron. Fu. Stockton.Hayhurst. Ecole Polytechnique. Curie (Paris VI). Canada L 5/1 a* Approximate Methods of Analysis for Creep Rupture D. Hoffmann. R. Rupture L 5/1 Predictions of Creep Behavior of Some Stainless Steels on the Basis of Short-Term Tensile Properties T. Amherst.A.SA. 81 . Gortemaker. Yagawa. U. Twenfe University of Technology. France.L Roche. Y. U. A. A. Session L 6. Codes and Criteria L 6/1* L 6/3 L 6/4 L 6/5 L 6/6 Development of Inelastic Design Criteria and Codes W.J. O'Donnell, J.S. Porowski, O'Donnell & Associates, Inc., Pittsburgh, Pennsylvania, U.S.A. High Temperature Design Evaluations by a Creep Ratchetting Theory H.U. Ahmed, Argonne National Laboratory, Argonne, Illinois, U.S.A. Requirements on the Mechanical Design of Reactor Systems Operating at Elevated Temperature H. Schulz, M. Glahn, Gesellschaft für Reaktorsicherheit, Köln, Fed. Rep. Germany Rules for the Analysis of Mechanical Structures at Elevated Temperatures H. Jakubowicz, CEA./CEN-Saclay DEMT, Gif-sur-Yvette P. Petrequin, CEA./CEN-Saclay SRMA, Gif-sur-Yvette K. Schaller, CEA./CEN-Cadarache, DRNR/STRS, Saint-Paul-lezDurance, France Shakedown Analysis by Finite Element Incremental Procedures A. Borkowski, M. Kleiber, Polish Academy of Sciences, Institute of Fundamental Technological Research, Warsaw, Poland Session L 7. Materials Behavior L 7/1 L 7/2 L7/3 L 7/4 L7/6 L 7/7 82 Thermoviscoplasticity Based on Total Strain and Overstress E. Krempl, E.P. Cernocky, M.C.M. Liu, Rensselaer Polytechnic Institute, Troy, New York, U.S.A. Effect of Past Loading on the Current Stress of Rigid Plastic Materials Y.S. Lee, G.J. Böhm, S.A. Swamy, Westinghouse Electric Corporation, Pittsburgh, Pennsylvania, U.SA. Constitutive Equations of Viscoplasticity for Neutron Irradiated Mild Steel R.B. Pecherski, Polish Academy of Sciences, Institute of Fundamental Technological Research, Warsaw, Poland Tensile Properties of Zircaloy-4 and 304 Stainless Steel at Constant True Strain-Rates and Elevated Temperatures CS. Hartley, D.A. Jenkins, J.-J. Lee, University of Florida, Gainesville, Florida, U.S.A. see C 3 / 1 3 Slip Theory of Creep Deformation of Face-Centered-Cubic Polycrystalline Aggregates S.V. Guerreiro Ribeiro, Comissão Nacional de Energia Nuclear, Rio de Janeiro, Brazil, T.H. Lin, University of California, Los Angeles, California, U.S.A. A Continuum Model for a Metal that Recrystallizes During the Deformation History A.D. Narayana, D.C. Stouffer, University of Cincinnati, Cincinnati, Ohio, U.S.A. L 7/8 Low Cycle Fatigue of Steels for Nuclear Pressure Vessels in H ot Water C. Gamier, G. Kowalczuk, R. Roche, CEA./CEN­S aclay DEMT, Gif­sur­ Yvette, Β. Barrachin, IPS N, Paris, France Session L 8. Applications I L 8/1 L 8/2 L 8/3 L 8/4 L 8/5 L 8/6 Creep Collapse of a Cylindrical Shell Subjected to External Pres­ sure at H igh Temperature K. Nagato, N. Takikawa, Kawasaki Heavy Industries, Ltd., Tokyo, Japan Creep Deflection Analysis of Fuel Channels in CANDU Nuclear Re­ actors M.J. Pettigrew, S.B. Lambert, Atomic Energy of Canada Limited, Chalk River Nuclear Laboratories, Chalk River, Ontario, Canada Nonlinear, Dynamic, Plastic Component­Support Analysis W. Elfmann, U. Heeschen, G. Müller, Kraftwerk Union AG, Erlan­ gen, Fed. Rep. Germany Viscoplastic Axisymmetrical Buckling of Spherical Shell Subjected to Radial Pressure Impulse W. Wojewódski, P. Lewinski, Politechnica Warszawska, Warsaw, Poland Some Design Aspects of Duplex Tubing J.M. Chern, D.H. Pai, Foster Wheeler Energy Corporation, Living­ ston, New Jersey, U.S .A. Creep Collapse of Non­Uniform Circular Tubes Subjected to Exter­ nal Pressure and Non­Uniform Temperature DJ. Lee, J.V. Parker, Nuclear Power Company (Risley) Limited, Risley, Warrington, Cheshire, U.K. Session L 9. Applications II L 9/3 L 9/4 L 9/5 L 9/6 Applications of Endochronic Plasticity in the Dynamic Finite Ele­ ment Analysis of Structures R.A. Valentin, B.J. H sieh, H.C Lin, Argonne National Laboratory, Argonne, Illinois, U.S .A. Influence of Weldments in the H igh Temperature Low Cycle Fati­ gue Resistance of AISI 304 and 316 Stainless Steel Tubular Ele­ ments C Carmignani, E. Manfredi, E. Vitale, Università di Pisa, Pisa, Italy The Development and Validation of Numerical Procedures for the Prediction of Shipping Cask Puncture R.A. Larder, D.F. Arthur, J.O. Hallquist, Lawrence Livermore Labo­ ratory, Livermore, California, U.S .A. Plastic Deformation of Steel Shock Absorbing Structures D. Aquaro, G. Forasassi, Università di Pisa, Pisa, Italy 83 L 9/8 L 9/9 Analysis and Design of Containment Liner/Anchorage System T.H. Liu, F. Loceff, W.E. Moore, Westinghouse Electric Corporation, Pittsburgh, Pennsylvania, U.SA. Inelastic Analysis of Plane Stress Problems M.M. Ettouney, R.P. Daddazio, J.A. Brennan, J.E. Richardson, Burns & Roe, Inc., Woodbury, New York, U.S.A. Session L 10. Simplified Methods L 10/1* Plastic Design of Complex Shape Structural Elements W. Szczepinski, Polish Academy of Sciences, Institute of Fundamental Technological Research, Warsaw, Poland L 10/2* Simplified Methods in Inelastic Analysis RS. Barsoum, Combustion Engineering, Inc., Windsor, Connecticut, U.S.A. L 10/3 Creep Ratcheting Bounds Based on Elastic Core Concept J.S. Porowski, W.J. O'Donnell, O'Donnell Associates, Inc., Pittsburgh, Pennsylvania, U.S.A. L 10/4 Creep Behavior of Piping Components under Combined Loading A. Suzuki, Ishikawajima-Harima Heavy Industries Co., Tokyo, Japan L 10/5 Simplified Inelastic Analysis Method of Perforated Plates K. Uragami, K. Nakamura, K. Asada, Takasago Technical Research Institute, Mitsubishi Heavy Industries, Ltd., Takasago, Hyogo, T. Kano, Power Reactor and Nuclear Fuel Development Corporation, Tokyo, Japan L 10/7 Plastic Frames: Reduction of the Kinematical Inequality and Optimization P. Brousse, Université de Paris VI, Paris, France Session L 1 1 . Damage L 11/1* Material Damage in Structural Analysis J. Huit, J. Janson, Chalmers University of Technology, Göteborg, Sweden L 11 /3 Modelization of the Strain Memory Effect on the Cyclic Hardening of 316 Stainless Steel J.L. Chaboche, Office National d'Etudes et de Recherches Aérospatiales, Châtillon, K. Dang Van, G. Cordier, Ecole Polytechnique, Palaiseau, France L 11/4 Damage Equations for Creep Rupture in Steels G. Piatti, Commission of the European Communities, J.R.C. Ispra Establishment, Ispra, Italy, G. Bernasconi, Politecnico di Milano, Milano, Italy, F.A. Cozzarelli, Sfafe University of New York at Buffalo, Buffalo, New York, U.S.A. 84 Phillips. G. Poland Simplified Methods of Inelastic Analysis for Components Operating within the Creep Range R. Italy Session L 12. Gloucestershire. The Behaviour of Plates Subjected to Steady Mechanical Load and Rapid Thermal Transients on Both Surfaces A. GEC Power Engineering Limited.M. Ispra Establishment. U.A. CEA. Commission of the European Communities.N. Ng. Ispra Establishment. Università di Pisa. Oak Ridge National Laboratory.K.C.Y. Leicester. Roche. Piatti Commission of the European Communities.A.S. R. Berkeley. del Puglia. Notre Dame. J. Florence E. CEGB.K. Bernasconi.H. Experimental Tests on Vessel Heads M. Pisa. Manfredi. L 12/4 High Temperature Low Cycle Fatigue Damage Analysis of Welded Stainless Steel Tubular Elements A. Goodall. Università degli Studi di Firenze. Probabilistic Methods in Plastic Structural Analysis G. L. Jones.R. Matteazzi. U.T. Chikusa-ku. Berkeley Nuclear Laboratories.K.R. Pabisek. Politecnico di Milano.R. Firenze. J. Gloucestershire. Matera. Milano. Nagoya. Italy 85 . Murakami. Piatti. Indiana. Lee. E.A. U. U. G. Ispra. Ellis. Otter. CEGB. Neutral and Shakedown Domains of Circular Plates Subjected to Cycles of Pressure and Temperature Z. University of Notre Dame.H. Ispra. Gif-sur-Yvette. Tennessee. G.C.L 11 /5 L 11 /6 L 11/7 L 11/8 L 11/9* Life Prediction of Simple Structures Subject to Cyclic Primary and Secondary Loading Resulting in Creep and Plasticity N. Nagoya University. Berkeley. Ainsworth. Oak Ridge. Whetstone./CEN-Saclay DEMT.N. Pugh. Robinson. I. R. J. L12/6 Inelastic Stress-Strain Relationships for the AISI 310 Stainless Steel in the Temperature Range 20°-900°C S. Alix. Tanaka.S. France L 12/3 Time Dependence in Biaxial Yield of Type 316 Stainless Steel at Room Temperature J. Italy L12/5 Yielding of 6061-T6 Aluminum Tubings Under Dynamic Biaxial Loadings D. Goodman. Japan L 12/2 Inelastic Buckling Analysis. U. D. Technical University of Cracow. Krakow. CE. Berkeley Nuclear Laboratories. Augusti. Waszczyszyn.L. Experiments I L 12/1 Creep Buckling and Instability of Circular Cylindrical Shells in Axial Compression S. Università di Florence. E.W.R. R. . Germany Experimental Analysis on Elasto-Plastic Behaviour of T-Branched Stainless Steel Pipe P. CNEN Casaccia. Tomassetti.G. Nerli. Research and Development Center. Fed. lida. Sherbourne.Konter. Poland Session L13. G. Ennis. Wilson. Ontario.. K.SA. . Poznan. U. Hitachi Ltd. Ibaragi. Università di Florence.H.N. Husslage. U. Y. Reale. Hitachi-shi.M. A. Waterloo. W.J. Inc. Rep.S. Osaka. Hitachi Ship Building and Engineering Ltd. Ohsawa.L 12/7 Creep-Fatigue Interaction on 1. The Netherlands An Analysis of the Relaxation of Residual Stresses by Using Vibrational Conditioning K. Structural Beam Shapes under Cyclic Inelastic Loads S. Roma. W. Pennsylvania. CM. Rogalska..N. Jülich. Kernforschungszentrum Karlsruhe. P. D. Wesenberg. M. Including Irradiation Effects R. Germany L 12/8 Low-Cycle Fatigue Behaviours of 304 Stainless Steel Piping Elbows at Elevated Temperature K. Toronto.W. Metal Research Institute. Janssen. G. Cittì. Sakai-shi. Institute for Mechanical Constructions.N.S. Maxwell. University of Waterloo.A. P. Ontario. T. S.A.T. Dowling. Italy The Response of Flat Plates Subjected to a Centrally Distributed Heat Flux D. Canada High Temperature Alloys for the Primary Circuit of a Prototype Nuclear Process Heat Plant P.A.K. H. Rissone. Albuquerque. Westinghouse Electric Corporation. E. G. N.. Pittsburgh. Technical University of Poznan. Apeldoorn. Kennedy. Krishnasamy. Y.K. Science Applications. Anderko.A. W.E. Litewka. Stone. Fed.L. Tokyo. Schmitt. Schuster. Fukuda. Florence.O.4948 Austenitic Stainless Steel. T.. Ontario Hydro Research Division. Wahi. Karlsruhe. Rep. New Mexico.O. Kernforschungsanlage Jülich. California. San Leandro. Adams. U. Experiments II L 13/1 L13/3 L13/4 L13/5 L 13/6 L 13/7 L 13/8 86 Effect ot Biaxial Loading and Geometry on Prediction of Low-Cycle Fatigue Life A. University of Tokyo. Ito. Hitachi Research Laboratory.E. Sandia Laboratories. Scheibe. Delft. Japan L 12/9 Plastic Flow of the Perforated Materials with Square Penetration Pattern A. Analysis of Notch Strain for Cyclic Loading N. Osaka. Y. T. lida. Hitachi Research Laboratory. Hitachi Ltd. Fuji Electric Co. Chiba University. University of Tokyo. Ibaragi. Hitachi Ship Building and Engineering Ltd.. Y. Ltd. Y. Japan L 13/10 Structural Behavior of Welded Superalloy Cylinder with Internal Pressure in High Temperature Environment T. Tokyo.. Udoguchi. Sakai-shi. Hitachi-shi. Ito.L 13/9 Creep and Relaxation Behaviours of 304 Stainless Steel Piping Elbows K. Yokosuka. Tokyo. Japan 87 . Ohsawa. M. University of Tokyo.. Fukuda. Asada. Nakanishi. Chiba. U. Rep. The MacNeal-Schwendler Corporation. Arnaudeau. University of California. Engineering Technology Associates. Haug. U.S.M.J. Cleary. M 2/2* Computational Aspects of Inelastic Analysis J. Massachusetts. Surrey. Bethpage. Session M 2. M 1/3 PAM-NL: A General Finite Element Program for the Nonlinear Thermomechanical Analysis of Structures E.A. K.M.A. K. A paper number missing in the numeral order means that the paper was cancelled or withdrawn.TABLE OF CONTENTS Division M. Epsom. J. LE. ISD. U. M 1/5 The Computer Program System for Structural Design of Nuclear Power Plant S. Stuttgart. M. 88 . Los Angeles. M 1/7* Algorithmic and Other Aspects of Large Scale Lagrangian Computation by Finite Element and Finite Difference Techniques GL. Aihara. METHODS FOR STRUCTURAL ANALYSIS Session M 1. Vaz. Gloudeman.J. Numerical Implementation of Inelastic Material Models M 2/1* On Constitutive Modelling in Finite Element Analysis K. New York. Engineering System International. K. Sasagawa.K. Warwickshire. FC. Integrated Methods of Structural Analysis M 1/1* Integrated Computer-Based Systems: Survey and Outlook J. Grumman Aerospace Corporation. Atkins Research and Development. Levy.A. Argyris.O Knowles. M.H. J. Willam. Kajima Corporation. RungisSilic.R. Japan M 1/6 Engineering Capabilities of the ASASIN Program N. Powell. M 1/2 Finite Element Three-Dimensional Elastic-Plastic Creep Analysis A. Satoh. G.A. Locci. A title mentioned on the Table of Contents but not followed by a summary or a paper means that the paper was not available at the time of finishing of the book. V. Snyder.F. Stoker. Bathe. Goudreau. U.S. California. Massachusetts Institute of Technology. Tokyo. S. U. Le Plessis Robinson. Trbojevic. Berkeley. Lawrence Livermore Laboratory.D. Livermore. Germany The sign (·) designates Invited Lectures. France M 1/4 Further Developments of Capabilities in the Program ANSR for Nonlinear Finite Element Analysis DP. Universität Stuttgart.S. Mondkar. U.P.S. Cambridge. Nuneaton.A. Stokingford.S.H. Architectural Design Division. California. California. Atsumi. Fed. Novatome Industries. de Villiers. 89 . Vitiello. UK. Politecnico di Milano. Finzi-Nova-Castellani Associated Engineers. France Membrane versus Shell Type Elements in Finite Element Analysis of Box Type Buildings G. The Netherlands Energy Research Foundation. Design and Simplified Methods of Analysis M 3/1 M 3/2 M 3/3 M 3/4 M 3/5 M 3/6 Optimal Shapes of Pressure Vessel Heads to Minimize Shearing Stress J. Bruinette. Rep.S. Krishnamoorthy. California. Sargent & Lundy Engineers. L.A. Italy Super Element Model Development and Analysis of the Mark I Torus Structure L. San Francisco. California. San Francisco. Litton. Petten. CS. A. Poitiers. C Wong.A. van Rij. Pandahnathan.A. Powell.S. Three Dimensional Finite Element Linear Analysis of Reinforced Concrete Structures M. Swansea. France Implementation of Endochronic Theory for Concrete with Extension to Include Cracking G. Capetown. Republic of South Africa. Inc. Middleton. Chitnuyanondh. Inbasakaran. University of Alberta. Plastic Analysis of the Core Barrel Flange Deformations According to Non-Symmetric Bending Loadings U.A.O Bianchini. V.-C Hua. California. Coimbatore Institute of Technology. Edmonton.J. Coimbatore. J.H.W. University of California. Pietri. U. Canetta. U. Rungis-Silic. India Nonlinear Finite Element Analysis of RC Structures Subjected to Thermal Load TP.M 2/3 M 2/4 M 2/5 M 2/6 M 2/7 M 2/8 A Finite Element Model for Plane Strain Plasticity with Velocity Discontinuities H. Alberta.S. IP. Session M 3. Khatua. Italy Methods of Two-Steps Inelastic Analysis of Liners E. Germany see F 1/4 Thermal Shocks in Solar Boiler Tubes and Mechanical Tolerance to Heating Velocity C Gamby. University of Wales. A. de Rouvray. Milano. Al-Dabbagh.S. Kruger & Stoffberg. Erlangen.M. The Netherlands Computer Implementation of an Elastic-Plastic Concrete Relationship D. U. P. Dubois. Milano. Murray.. Université de Poitiers. PMB Systems Engineering. Kraftwerk Union AG. Chicago. U. Canada Coupled Damage Modes (CDM) Plasticity Models for the Simulation of Complex Materials Used in Reactors J. Bechtel Power Corporation. Berkeley.. Fed. Illinois. Engineering System International. R.W. Berkner.G. A. Jullien. Québec.L. California. M 4/4 Matrix Analysis of the Asymmetrical Bending of Conical ShellBeams and Their Singular Assemblies A. NERSA-ENEL.V. A.M 3/7 Study of an Axisymmetric Model for the Parametric Analysis of a 3D Complex Steel Structure A.S. Illinois. Lyon. E. Shell Technology Associates. M 4/6 Large Deflection Elastic-Plastic Analysis of Shells of Revolution with a Quasilinearization Algorithm H. Argonne National Laboratory. P.W. Leonard. Chen.S. NERSA. Rodet. W. Surrey. Reading. California. Argonne. U. U.K. U. California. Computational Techniques for Plate and Shell Analysis I M 4/1* Finite Elements for Large Displacement General Shell Analyses R.U.SA. Ward.A. Paris. U. Atkins Research and Development. Chicago. Morel. Belgium M 4/5 A Finite Element Model for Nonlinear Shells of Revolution W.. Steele. Taylor.H. Pennsylvania.A. Rozenblum. D. Inc. Cook. INSA. Coppens. Palo Alto. Stanford. C Goto.A Shell Code Using Asymptotic Results CR. Los Alamos Scientific Laboratory. Brais.A.S. Ahmed. University of California. Stanford University. M 4/3 FAST . F. Failure Analysis Associates. Moffett Field. M 4/2 Analysis of Shell Components by Finite Elements R. M 3/10 A Mechanistic Assessment of Structural Failure for Missile Impacts on Concrete Structures P. Paris. France M 3/9 Safety Investigation of a Spent Fuel Pool for Installation of High Capacity Fuel Racks T. Epsom. Kiedrzynski. Pratt. Société d'Etudes et d'Equipement d'Entreprises. Villeurbanne. Besnier. G. Godbout. NASA Ames Research Center. T. California. Montréal.uk. NERSA-EDF. Amir-Mazaheri. Berkeley. U. U. Pulliam. California.H. Bruxelles. Gilbert Associates. France M 3/8 Comparison Between a 3D Photoelastic Model and an Axisymmetric Finite Element Calculus A. Lyon. 90 . Compagnie Internationale de Services en Informatique. E. Ranjan. Morel. Université de Montréal. Sawi. G. Illinois. Illinois Institute of Technology. Chang. Zolzettich. A. Los Alamos. L. New Mexico.S. J. Palo Alto. Somma. Lyon. Université Libre de Bruxelles.A. Canada Session M 4. F. R. Crutzen. Monterey. Italy 91 . Jr. Tao. California. Kumamoto University. San Carlos. Japan Elasto/Visco-Plastic Analysis of Axisymmetrical Shells under Asymmetrical Loading K. A New Finite Element for Structural Analysis of Piping Systems H. Stuttgart.-Louis. New York. Gif-sur-Yvette. M 5/3 M 5/4 M 5/5 M 5/6 M 5/7 M 5/9 The Use of the Semiloof Shell Element in the BERSAFE Finite Element System T.K. California. A. J. Koppers Company. Germany M 5/2 A Note on Imperfection Sensitivity of Externally Pressurized Shells R. Cornell University. Asai./CEN-Saclay DEMT ISMTS. McDonnell Doug/as Automation. Svalbonas. Inc. E. Ithaca. ISD. Experience with a New Triangular Doubly-Curved Element for Shell Analysis S. T. Century Research Center Corporation.S. Gloucestershire.M 4/7 M 4/8 Elasto/Visco-Plastic Deformations of Thin Shells of Revolution S. Japan Session M 5. Ispra. CEGB. St. K. Tokyo.A. Kumamoto. Kumamoto University. Computational Techniques for Plate and Shell Analysis II M 5/1 Analysis of the Buckling Behaviour of Structures M. U. Use of the Equilibrium Equations Based on the Deformed Body A Combescure. Ball.C. Iwata. Abel. König.R. S. Takezono. J. Naval Postgraduate School. U. Berkeley Nuclear Laboratories. Power Reactor and Nuclear Fuel Development Corporation. Universität Stuttgart. U. U.S. Hoffmann. Anamet Laboratories. Berkeley. Akashi.K. Missouri. Japan Non-Linear Analysis of Shells (Large Displacements).-C Wu. Tokyo.B.. Paxson. USA. Takezono. Kumamoto. Inc. Commission of the European Communities. Ispra Establishment. A Thin Shell Dynamic Transient Non-Linear Analysis Program Y.F.A. France Incorporation of an Eigenvalue Dynamic Buckling Criteria into Direct Integration Procedures V. Hellen.. Rep. York. CEA. Fed.S.. Citerley.L. Takeda. RE. S. Pennsylvania. CISE. Redmer. Pattanayak. Tanabe. Gupta. Takeda. Chicago. California. Hallquist. Germany M 6/8 Implicit Treatment of the Large Deformation Response of Inelastic Solids with Slide-Lines J. Brusa. U. Ando.K. J. M. A. T. Chicago. Yagawa. G.A. Zeitner. Brandes. Italy M 6/6 Dynamic Analysis of Buried Structures Subjected to Shock Loads T.O. Deeken. A. M 6/7 A Numerical Method for Complex Structural Dynamics in Nuclear Plant Facilities W. Tokyo. Illinois. Japan 92 .S. Lawrence Livermore Laboratory.S. Khatua. Y. Computational Methods within Finite Element Analysis II M 7/1* Quasi-Newton Iteration in Non-Linear Structural Dynamics M.Session M 6. Japan M 6/5 A Procedure to Obtain Unconditionally Stable Explicit Methods for Structural Problems L. Illinois Institute of Technology. Liège.A. Illinois. Geradin. Ciacci. Rheinisch-Westfälische Technische Hochschule Aachen. R. Schomburg. Century Research Corporation. Fed. Bundesanstalt für Materialprüfung. Illinois Institute of Technology Research Institute. Rep. Aachen.K. A. Power Reactor and Nuclear Fuel Development Corporation. Illinois. Berlin (West). Tokyo. Ishiwata. Rep. Belgium M 7/2 Efficient Solution Procedures of Simultaneous Equations for Large Nonlinear Finite Element Systems M.A. University of Tokyo. Malkus. S. U. Germany M 6/4 EPAS-Finite Element Program for Analysis of Nonlinear Behavior of Nuclear Power Piping G. Computational Techniques within Finite Element Analysis I M 6/1 * Penalty Methods in Finite Element Analysis of Fluids and Structures D. Erlangen. Century Research Center Corporation. Fed. K. Chicago. Livermore.S. Tokyo. Iwata. Sargenta Lundy Engineers. Université de Liège.P. Tokyo. Milano.S. Greco. Germany M 6/3 Contact Finite Elements U. Kraftwerk Union AG. U. Watanabe. H. Hogge. Session M 7. M 6/2 A Boundary Method to Solve Mixed Boundary Value Problems by Consistent Weighting to the Different Boundary Conditions K. Louis.ICEN Saclay DEMT. Heitkampf GmbH. Rep. Germany A Method of Solution of the Eigenproblems of Large Structural Systems in an Arbitrarily Specified Range J. C.F. Paris. A. California. Bauunternehmung E. France Modal Analysis and Estimation of the Calculation Errors W.and Structural Reliability G. J. A. U. Wrana. Republic of South Africa 93 . Krings. Gif-sur-Yvette. Germany M 8/3 The Development of Time-History Design Criteria for Uncertain Transient Loads JR.C.R. Churchill. P. Hoffmann. Rep. M 8/5 COVASTOL: A Computer Code for the Estimation of Pressure Vessel Failure Probability A C Lucia. Gesellschaft für Reaktorsicherheit. Atomic Energy Board. U. Université de Paris VI.R. Licensing Branch. Italy. Mannheim J. Technische Hochschule Darmstadt. Fed. Basu. Ispra Establishment. Marriott. Commission of the European Communities. Erlangen. P. St.S. Rep.L. Cracow. Kraftwerk Union AG. Schuëller. Benjamin. Technische Universität München. Dubois. Erlangen. Brandt. Kraftwerk Union AG.A.S. Probabilistic Methods in Structural Analysis M 8/1 * Some Aspects of the Interaction Between Systems. Fed. Herne. B. Wellein. R. Brousse. University of Cracow.W. Orkisz. Brunnhuber. Missouri. CISI Saclay..A. Boveri & Cie AG. J. CEA. Remesh Algorithms for the Finite Element and Finite Difference Calculation of Solid and Fluid Continuum Mechanics Problems J.I. Chavant. Eibaz R. Gif-sur-Yvette. Fed. Inc. Fed. France Session M 8. Rungis-Silic. Schmitt. Palo Alto. Germany Adaptive versus Standard Finite Element Programs: Data for Comparison of Costs and Accuracy A.M 7/3 M 7/4 M 7/5 M 7/6 M 7/7 M 7/8 Linear Dynamic Analysis by Hybrid Displacement Finite Element Models K. J. Schmitt. Garching. Bergamo. Engineering Decision Analysis Company. Kafka. München. Chedmail. W. Ispra. Italy M 8/6 Methods to Determine the Influence of Quality Assurance on the Reliability of Primary Components of a PWR W. Darmstadt. Peano. Rep. Brown. ISMES. Pelindaba. Germany M 8/7 Effects of Correlation between Defects and Material Properties on Component Failure Probability D. Poland Solutions of Associated Problems in Structural Optimization P. Wissmann. Washington University. Engineering System International. U.A. Numerical Procedures for Fracture Mechanics M 9/1 M 9/2 M 9/3 M 9/4 M 9/5 M 9/6 M 9/7 M 9/8 M 9/9 A Numerical Comparison of Post Yield Fracture Behaviour in Rotor Steels T. Ezawa.S. G. F. Pennsylvania. Mitsui Mining and Smelting Company. Shaffer.D./CEN-Saclay DEMT.K. I. Ontario.K.-H. Raheja.T. Canada M 8/9 Design Stresses in Probabilistic Form for Ellipsoidal and Toroidal Pressure Vessels CO.A. Sargent & Lundy Engineers. Gürdogan. National Tsing Hua University. R. U. Smith. Tokyo. Berkeley Nuclear Laboratories. CEA. France On the J-lntegral for Nonhomogeneous Cracked Composites W.L. Y. Kececioglu. University of Tokyo. Akay. Gif-sur-Yvette.H.A. An Investigation of Degenerate Isoparametric Finite Elements for Stress Intensity Computations H. France Handy Incorporation of Bond and Singularity Elements in the Finite Element Solution Routine Y..U. Cho. Canadian Forces Command and Staff College.S.S. Lamarre. CEA. Gif-sur-Yvette. U. U.. Chicago. Middle East Technical University. D. Yamada. Taiwan.M 8/8 Reliability of Mechanical Components Subjected to Combined Alternating and Mean Stresses with a Nonconstant Stress Ratio D. Jouris. Omaha. Nebraska. Cheshire. . Nishiguchi. Westinghouse Research and Development Center. Warrington. Okabe. O. Republic of China Fracture Mechanics Evaluation of Reactor Vessel Using Stress Intensity Factors from Enriched Finite Elements D. CEGB. Ankara. Ramani. Institute of Industrial Science.K. University of Arizona.V. Roche. U. M. Laf ore. Pittsburgh.. Risley. Nuclear Power Company (Risley) Ltd. Turkey A New Mixed Mode Fracture Mechanics Criterion P. Chen. Session M 9.S. Arizona. U. Toronto. University of Nebraska at Omaha.L. Berkeley. withdrawn Improved Practical Lower Bound for Fracture Toughness Data G. Illinois. Ltd. Tokyo. Gloucestershire. Defect Vectors and Path Integrals in Fracture Mechanics R.A. Tucson./CEN-Saclay DEMT. Hellen.M. Japan The Analysis of Structures Containing Defects Using Isoparametric Elements B.B. Brierley. Hsinchu. Day P. S. Advances in Linear Boundary and Initial Value Problems M 11 /1 Solution of Plane Stress and Plate Bending Problems by Boundary Integral Equations R. General Atomic Company. Session M 1 1 . Los Angeles. Technische Hochschule Darmstadt. Woo.A. Subudhi. Rep.D. Bundesanstalt für Materialprüfung.K. Inc. University of Nebraska. M 11/3 Thermal Stresses in Cylindrical Shells Under Arbitrary Temperature Distribution W. Sargent & Lundy Engineers. Dynamic Modelling in Seismic Analysis M 10/1 Application of Far Field Asymptotic Solutions in Global-Local Finite Elements R.A. Berlin (West). P.Session M 10. San Francisco. Brunswick Corporation. Germany M 10/3a Some Considerations on the Dynamic Structure-Soil-Structure Interaction Analysis W. K. California. R. Chicago. University of California. Wu. U. Scholl. Nebraska. Germany 95 . Schnell. Berlin (West). Engineers. USA. Blume & Associates.L. Ebasco Services. Patel. Kirmser. Bundesanstalt für Materialprüfung.G. Fed. Y. Illinois. M. San Diego. M 10/2 An Interior Collocation Method for Vibration of a Rectangular Plate Carrying Attached Mass Y. Contreras. Kansas State University. M 10/6 Stochastic Finite Element Structural Models H. Defense Products Division. M 10/5 Approximations for Dynamic Modeling ST. Darmstadt. U. Muki. U.A. Manhattan. U.S. New York..I.SA. Meyer... M 10/7 Nonlinear Response to the Multiple Sine Wave Excitation of a Softening-Hardening System B. Columbia University.D. Chou. S. Grover. A.Y. Dong. Koplik. N. H. SB.A. New York. Curreri. USA. URS/John A. Germany M 10/4 Quasi-Nonlinear Dynamic Analysis C. Holzlöhner. E. Upton.S.E. Lincoln.S.S. U. Odar.A. Matthees. Nebraska. Huang. U. Chiù. M 11/2 Applications of the Fundamental Solution for a Thermal Shock on a Finite Orthotropic Cylindrical Thin Shell C. J. New York.L. M 10/3 The Use of an Equivalent Homogeneous Half-Space in Soil-Structure Interaction Analyses U. Kansas. N. Lincoln. Brookhaven National Laboratory. California. J.M 11/4 Transient Thermal Stresses in a Transversely Isotropic Thick Plate with a Cylindrical Hole due to Surface Heat-Generations Y. Japan M 11/6 Elastic Behavior of Thick Plates and Shells with Cutouts CP. Cash. withdrawn 96 . W.A. Osaka. Vendhan. U. Y.W. Takeuti. University of Osaka Prefecture.A. U. Massachusetts. Sakai. Livermore. University of Massachusetts.S.S. Sugano. Feng. Lawrence Livermore Laboratory. Amherst. California.P.A. M 11/7 The Application of the Energy Principle to 3-Dimensional Shell Problems W. Nash. Tennessee. Los Angeles.1/1'Magnetic Confinement Fusion Reactor Systems R.C.S. Ispra Establishment.TABLE OF CONTENTS Division N.E. U. G. J. Oak Ridge. Casini. Livermore. U. Università di Napoli. General Atomic Company.2/4 Engineering Design of the SOLASE-H Laser Fusion Hybrid Reactor S. J. J. Conn. — A title m e n t i o n e d on the Table of C o n t e n t s but not f o l l o w e d by a s u m m a r y or a paper means t*iat the paper w a s not available at t h e t i m e of finishing of t h e book. N 1.S.A. Fontenay-auxRoses.W.R. California. France N1. — A paper n u m b e r missing m t h e n u m e r a l order means that the paper w a s cancelled or w i t h d r a w n 97 .E. N 1. Lawrence Livermore Laboratory. Madison.A. Lawrence Livermore Laboratory. van Renterghem. Moses. U. University of California. Monsler. Kastenberg. University of Wisconsin. W. California. Farfaletti-Casali. R.1/5 Structural Engineering Problems in FINTOR Conceptual Designs M. Centre d'Etudes Nucléaires. MATERIALS ENGINEERING.A. CEA. M. Aymar. Napolijtaly Session N 1. Moir.S. Abdel-Khalik. Wisconsin. California. Commission of the European Communities. J. Ispra.A. Biggio.J. Meier.S.2/2 Electric Power from Laser Fusion: The HYLIFE Concept M.S. Okrent.I. F.2/5* Fusion Reactor Safety D.R. N 1. Livermore.A. AND STRUCTURAL MECHANICS PROBLEMS OF FUTURE FUSION REACTOR POWER PLANTS Session N 1. Shannon. University of Wisconsin. G. N 1. et al. Conn.M.R.A. Rawls.1/3* Mirror Fusion Reactor Design W. Carlson. Rieger. G. U.A. U. California. Madison. Wisconsin. Blink. General Atomic Company.1. Département de Physique du Plasma et de la Fusion Contrôlée. Hovingh. U. Rubinacci..2.. Engineering Concepts of Inertial Confinement and Hybrid Fusion Reactor Systems and Safety Considerations N 1.SA.A.2/1* Inertial Confinement of Fusion Reactors R. Walter. G. Jr.W.2/3* Structural Concerns in Fusion Hybrid Reactors K. Oak Ridge National Laboratory.S. Schultz. J. THERMAL. N 1. Engineering Concepts of Magnetic Confinement Fusion Reactor Systems N 1. R.W.1/2*The USA/TNS Programs: Engineering Considerations T. N 1. W. Neef. San Diego. California. P. San Diego. Notes: — T h e sign ("I designates Invited Lectures. USA. Maurer. Dustmann. Messemer. Fed. Kot. U. Erb. U. California. Structural Analysis of M agnets Ν 2 . Kernforschungszentrum Karlsruhe.Session N 1. Colorado. US A. Tatro. Rep. Kearney.A.3/4* Heat Transfer in Inertial Confinement Fusion Reactor Systems J. N 2. Karlsruhe. U. Argonne. W. N 1. R.3/6 Shock and Blast Load Attenuation in Inertial Confinement Fusion Reactors CA. U.F. Rep.1/4 Finite Element Structural Analysis of Coil and Casing of a Large Superconducting Toroidal LCT­Magnet J.3/3 Thermal Analysis of a H igh­Temperature Falling Bed Fusion Reactor Blanket J. California. Universität Karlsruhe. San Diego. General Dynamics Convair.A. Illinois.3.L.S A. Illinois. N 1. A. Upton. de Paz.SA. Grünhagen. H . Bechtel National. Powell. O'Neill. N 1. N 1.1/6 Method for Determining the Magnet Shape in Toroidal Arrange­ ments J. Karlsruhe. Thermal-Fluid Dynamics of Fusion Power Reactor Systems N 1. N 1. Brookhaven National Laboratory.D.R.W. New York.A. J. Kernforschungszentrum Karlsruhe. U. Reich.S. Erb. Rep. 1 / Γ Existing and Future Structural Analysis Techniques and Their App­ lication to Superconducting Magnets M.3/2 Thermo­Fluid Mechanics of Liquid or Gas Cooled Tubular First Walls J. Lawrence Livermore Laboratory. Solar Energy Research Institute. Brookhaven National Laboratory.1/5 On the Mechanical Anisotropy in Superconducting Toroidal Coil Windings F.S . Zehlein.A.SA. Upton. Germany 98 . California. Golden. G. S an Francisco. Germany N 2. Fed. Karlsruhe. U. Livermore. Germany N 2.3/8 Cooldown and Warmup Thermal Analysis of the Mirror Fusion Test Facility (MFTF) Superconducting Magnet R. New York.E. Hovingh. Harkness. N 1. Arendt.3/1'Thermal­Hydraulic Considerations in Magnetically Confined Fu­ sion Reactors D. Filio.3/5 H ydrodynamic Effects in Inertial Fusion Reactors S. S. C­Η.Thomson. Session N 2. Argonne. Fed. Argonne National Laboratory.SA. Kernforschungszentrum Karlsruhe. U. Argonne National Laboratory. Karlsruhe.F.1.S . . Washington. Frascati. C.W. Cambridge. CEA..C. Bethpage. Spadoni. Boveri & Cie.2/3 Applications of Metallic Composites in the Magnet System of a Demonstration Fusion Reactor R. Lawrence Livermore Laboratory. T. Mannheim. Bourrier. J.C. Upton. California.S. E. Matera.C. U. Fed. Brown. Brown. Paris. J. Balderes. N 2. J.K. Prothero. Massachusetts. Hammel. New York. Gif-sur-Yvette.S. France Session N 2. Italy N 2. Dalder. R.H. Long.R.A. Potts. Hsieh. Bologna. General Dynamics Convair Division. N 2. CEA./CEN-Saclay. Livermore. Dubois. U. ICEN.. P. Newcastle. Laboratorio Gas lonizatti. Bezler. New York.1/9 Fields Analysis of TFR 604 Copper Coils P. Buck. Coppi.W. California. U. Ispra.V. Grumman Aerospace Corporation.2/4 The Structural Design of Superconducting Magnets for the Large Coil Program W.T. D. Germany N 2.2/2 General Dynamics Convair Division Approach to Structural Analysis of Large Superconducting Coils R. Pasotti. U. Massachusetts Institute of Technology.1/7 Structural Analysis of Non-Circular Coils for Fusion Experiments K. Tennessee. Millard. Commission of the European Communities.E. Ricci. G.C.Y. Taroni. San Diego. Henning. U. Oak Ridge National Laboratory. International Research and Development Co. United States Department of Energy. Magnet Technology N 2. Rep.J. Baldi.SA. A. 99 . Fontenay-aux-Roses. N. Bundy.2/5 Structural Design of DEALS Magnet P. A.A. Centro Calcolo.S. Brookhaven National Laboratory..2/1'Structural Materials for Fusion Magnets CD. Stoddart.1/8 Structural Analysis of Compact Experiments for Thermonuclear Ignition B.A. C. CNEN. N 2. Sacchetti.N 2..H. S. D. Gray. CNEN. Italy.T. Oak Ridge. Deschamps. M.2. Ltd.A. M. Italy N 2. U.-Ispra Establishment.N.S. SOCOTEC. W. A. A. Sako.G. St. Missouri. Rep.S. N 2. Session N 2. Masuda.W. U. Wisconsin. Association Euratom-IPP.C. Ibaraki-ken. California. University of Wisconsin. McDonnell Douglas Astronautics Co. Tokyo. U.M. Raeder. withdrawn 100 . T. Pendergrass.S. Y.G.Session N 2. Minato. Ando. First Wall Performance in Fusion Reactors N 2. Booth. Los Alamos Scientific Laboratory. Odette. Illinois.3/1 * A Review of Lifetime Analyses for the First Wall of a Tokamak-Based Reactor S. Department of Energy. W. L. Daenner.S. Yagawa.A Computer Program for Predicting the Lifetime of a Fusion Reactor First Wall W.S. Max-Planck-Institut für Plasmaphysik. Madison.R. Germany N 2. Lovell. Germany N 2. Frank. Los Alamos. E. Japan N 2.Wolter. U. California.. Fusion Blanket Structural Analysis N 2.A. U. Hejazi. J.A. J.A. Tokai Research Establishment. Missouri. Japan N 2.W.3/3 Approaches to Assessing the Failure Resistance of Fusion Reactor First Walls G. Japan Atomic Energy Research Institute. Cramer.3/6 Loads and Stresses in ICF Reactors withdrawn IO. University of Wisconsin.G. Iowa State University. G.H. N 2. U. Davis. Harkness. Radiation and Structural Mechanics Problems of Magnetic-Confinement CTR First Wall B. Wisconsin.S. Ma. Garching. Pollard. Iowa.A.S. Illinois. J.4/4 Stress Analysis of Blanket Vessel for JAERI Experimental Fusion Reactor K.3/2 FWLTB . Garching. Association EURATOM-IPP.4/5 The Structural Design Techniques Used in the Mirror Fusion Test Facility (MFTF) Vacuum Vessel L. N 2.A.A.S. Daenner.4.3.4/3 Dynamic and Static Structural Analysis of Liquid Lithium Blanket of Fusion Power Plant M.4/1* First Wall and Blanket Structure Performance W. Argonne.4/2 Fracture Mechanics Aspects of Irradiated Blanket Structures B. Washington. Madison.O Reuther. U. Fed. Ames. Lawrence Livermore Laboratory. J. University of California. Rep. Santa Barbara.A. Fed. University of Tokyo. Horie. Max-Planck-Institut für Plasmaphysik. Davis. Argonne National Laboratory.3/5 Stress Wave Edge Effects in ICTR Structural Components M. N 2. New Mexico. McDonnell Douglas Astronautics Company. Livermore. T.D. St. Louis.A. Bohachevsky. Louis. Northwestern University.S.3/7 Thermal. N 2.S. T. U. U.D. Evanston. /CEN-Saclay. McHenry. S. California. Arya-Mehr University of Technology.M.. University of Wisconsin. McCarville. U. Boulder. Madison. Paris. Y. N 2. Bathke. Roux. Reed. H.5/2 Radiation Effects on Elasticity of Metals M. Soenen. R. Lawrence Livermore Laboratory.J.4/7 Mechanical Static Analysis of the JET Vacuum Vessel B. DEMT. U. U. Isfahan..S. France N 2.W. Th. Teasdale. P. Oak Ridge National Laboratory.S. Illinois. Studiecentrum voor Kernenergie.S. Paris.A.S.A. Belgium N 2. Mol. Kulcinski. Evanston.A.G. U. N 2. Nemat-Nasser. C Dubois. S. Afzali. R.N. Los Alamos. Bourrier.A. Trantina./CEN-FAR (DPh-SCP).W. Hagenson. Soran.5/3 Corrosion of Structural Materials in Dynamic Lithium F. Bourrier.N 2. G.I. Los Alamos Scientific Laboratory.Cullingford.5/4 The Response of Stainless Steel to the Pellet Debris in a Laser Fusion Reactor T. Wisconsin. CEA.4/9 Engineering Design of a Direct-Cycle Steam-Generating Blanket for a Long-Pulse Fusion Reactor CE.5. N 2. U. Tennessee.L.E. P. R.SA. Aymar.Glenn.5/1 "The Change of Materials Properties During Irradiation in Fusion Reactor Service F. Millard.S.SA.CK. Session N 2.D. Hassanein. A.K. CE.5/5 Dynamic Loading of the Structural Wall in a Lithium Fall Fusion Reactor L. Oxon. JET Project Abingdon.P.H.A. N 2.P. France N 2. U. J. 101 . M. Oak Ridge. Fontenay-auxRoses.S. Wilkinson. P./CE. Krakowski.4/8 Structural Design Methods for Ceramics in Fusion Reactors G. CG. U. Livermore.5/7 Structural Alloys for Superconducting Magnets in Fusion Energy Systems H. Northwestern University. National Bureau of Standards. Schenectady.D. Streibl. R. U. Lievens. N 2. Iran. Materials and Plasma-Fluid Wall Interaction N 2. SOCOTEC. Foult. Colorado.A.A. Wiffen. A.4/6 Mechanical Studies for Supraconducting Toroidal Field Coils of Large Tokamak Fusion Device R. J. SOCOTEC. Fox. Cort. W. New Mexico. Gif-sur-Yvette. Casteels. DeKeyser. F.A. General Electric Corporate Research Et Development.L. New York. Tas. . AUTHORS INDEX . . K 6/7 Aihara S. N 2. Μ. G 10/1* Y. Amzallag C. Albrecht W. 1/3 E 3/1* H 8/5 H 7/1 M 2/8 K 2/4 L 12/2 D 3/4 M 3/8 E 3/3. Agrone M. Arai K.I. Anderson R. Andersen A. 4/4 G 3/1* H 8/6.Η. Albertini Albeson C. N 2.5.K.I.G. G 8/2 C 3/10.U. H.R. M.H. K 11/10 Agüero A. H 6/4.U.M.M.4/3 J 4/6. C 3/11 L 12/7 J 6/6. K 11/9 D 5/10 E 4/7. Andersen S. Anderson P. Anantharaman Anderko K. II. Ando W.Α.5/2 K 1/6 Agrawal P. K. Antony-Spies Aoyagi Y. L 13/8 Afzali M. G 2/5.R. Anand A.G. Andrews K J P. G 5/2 B 7/3 H 4/9. L 11/8 3/4 H. K 8/5. K 12/10.2/4 H 4/9.AbdeL-KhaUk Abe S. M 3/11 J 6/8 F 2/8. A-Moneim M. N 1. J 4/4. B 4/5 Akky M. H Aizawa T. Alujevic A. M 4/7 Akay H. Adams P. Amii—Mazahen' H.D. Aquaro D.I. K. M 5/3 Adams N.A. Abel J. Ainsworth Aird R. L 5/4 Akashi T. M 1/5 E 3/4 C K 12/5. M 9/6 Akkas N. Argyris J. 105 J 4/7 4/6 . J 4/5. Argon A. Al-Dabbagh Alderson Alix Α. J 4/1*.1/5 D 3/5 M 2/2* L 5/4.H. L 6/3. B 4/6.J. K 5/7 Ahmed H.K.A. Ahmed K. Arendt F. L 9/6 K 13/7 N 2.F.T. Ariman T. D 7/4, Arnaudeau F.C. Arnold L. E 4/1* Arnold P. K Arockiasamy Arros Asada Asai 5/3 Β 8/5 L 9/5 K. L 10/5 Y. L 13/10 S. Aschl F 3/7, H. H 1/4 J.E. E 6/2 Asmis G.J.K. M 5/5 J 3/2, K 2/8 Assedo R. F 2/1, F 2/2 Atalik T.S. K 9/3 Atchison R.J. J 3/2, At l u r i S.N. G 4/3 Atsumi K. M 1/5 Augusti G. Aurich L D. Axisa K 2/8 11/9* G 2/3 F. E 6/7 Avet-Flancard R. J 7/1* Aymar R. N 1.1/1*, Ayres D. F 5/1* T.S. K 11/5, Aziz Balderes Baldi Ball T. A.K. S. Barai N 2.2/5 E 5/6 Β. Bantle K 4/5 J 6/6, L. B. Barsoum R.S. Bastien R. L 10/2* H 5/6 P. M 7/7 Basu S. C 3/10, Bates J.F. C 3/9 Bathe K.J. M 2/1* C.G. Bauer J. Baum M.R. 106 6/8 L 7/8 Basu Baylac J F 8/4 Barrachin Bathke K 11/7 M 5/2 R.E. Banerjee N 2.4/6 N 2.2/2 R.W. Baltes K 11/4 K 4/7 D.F. Asada Ash M. J. Arthur E 3/5, M 1/3 G. N 2.4/9 J 9/3 f 6/5 F 2/1 C 3/11 Bazant Ζ.Ρ. Bazergui Beck Η 8/1*, A. R.L. Becker J 2/9 E.B. Bedrosian Β B. Beeston 5/4 J 2/7, J.M. F 1/1 J. G 4/5 Beine Β. Belytschko T.B. Benamou B 1/4, J.R. Benuzzi A. Berger U. Bernard A. 5/2 D 5/7 G. L 11/4, Bernreuter O.L. K 3/3, Berriaud C. A. F 2/4 Besnier F. H Bethmont M. L. P. F 7/5 F 4/5, Bhardwaj S.A. S.B. Bianchini J.C. M. D 3/7, D 5/6 J 9/4, M 2/5 1.1/5 G 1/2, M. L S. 5/1 0 3/7, D 5/6 H 5/5, H 5/6 Black W.E. Blair W. H 8/5 Blink J.A. N R. Bohachevsky Bongartz Booker Booker 1.2/2 H 8/5 1.0. G.J. N 2.3/6 K 8/7, Boisserie J.M. L K. C 2/2, F 5/12 M.K. L.A. Bordet R. L 7/2 1/6 B.L.P. Booth G 6/3 C 1/8 A. Blundell N 2.2/5 D 4/6 Ν Ζ. Singh Bohm K 12/1, H 5/5 Bevilacqua Bir K 8/3, 3/7 F 5/10 W.S. Billaux K 3/5 J 5/6 C. Biggio L 12/6 K 3/4, J 7/1* Bertaut Biron H 8/1*, F 1/4 Bernasconi B i lek E 6/3*, M 8/3 K Berkner Bhoje E 3/3, E 4/1* Ε. Bezler E 2/2, J 3/8 Benjamin Betts Κ 12/11 Η 7/1 Beinert Berro J 4/9 F 8/3 C 2/3 F 5/12 N 2.3/6 J 1/6 107 H 8/2 Bork J 9/7, M. Borkowski Bornscheuer F.W. J 6/7, M. Bounin D. H 7/2 Bourgeois C 1/1* P. Bourrier P. G 10/3, Boye-Moller K. J.T. L 4/1*, Bozzo F. J 5/6 Brais A. J 7/3, Brandi P. J 6/3 Brandt K. M 7/3 Brennan J.A. K 5/7, Brierley P. M 9/9 Brinkman CR. P. B.J. G.N. D. F 3/2 L 10/7, M.L. J 8/7 Brown S.J. B 5/13, Brown T. R. L. B. Bucheri K.P. Buchhardt Bui-Quoc F. T. L 5/1 R.L. C. G 6/4 F 7/6 T.K. F 1/1 P. Cagliostro Cambien J 6/3 N 2.2/5 Burducea Callahan J 3/1 N 2.1/7 J. Caldis M 8/5 0 21 λ K.E. Buttmann J 7/5 D.J. E.S. J.P. R.B. E 1/3, E 4/2, F 5/3 H 3/2, K 11/2 Campbell F.R. J 3/2 Campbell K.W. K 3/4 108 K 12/9 M 6/5 Brzoska Burr M 7/5 N 2.2/5 Brunnhuber Burback L 9/9 E 4/1* P. Bundy K 12/11, D 3/3 Brousse Buck M 6/2 F 5/12 Brouard Brusa L 4/5 F 2/4 Broadhouse Brown N 2.4/6, M 3/10 K. Brooks N 2.1/9, J 6/5* Boyle Briot J 6/9 G 8/2 Bosser Brandes K 2/7 L 6/6 Α. H 4/5 E 5/4 N 2.4/7 Κ 1/2 109 . Cenerini M.1/5 N 2. J 3/7 J 8/8 G. Casini 8/1 F 5/13. 4/9 G 9/6 G.M.P. Casteels F. Κ 7/7 Β M 7/8 2/8. Chatterjee Chavant M. Κ J. K Chan D. E 5/5 J 9/4. L 3/5.-H.H. Μ 9/4 7/6 Chern Chevallard E 3/3. Chedmail J.G.F.J. M 3/9 Chang Y. S.G. L 8/5 3/9 F 7/7 D 4/6 Chiba Ν.P.L. Ν 1. C. Chhatre K 9/2 7/7 E 4/4 R.Campbell R. Κ 7/6.P.H. B 1/1*. Cecconi L M 11/6 J. M 111 F 6/3 Chen C. J G.D. Ε 2/3. Cepkauskas Cernei 1/2 K 1/9. Cheissoux Cheli J. F 4/2 D 3/4 B. L 11/3 13/12 Chan C. Cernocky E. D 5/3 Chandra F S.E. Castellani Α. Μ 3/9 Chen W.M.R.W. E 5/3*. Chesi C. Carreira D. Celebi 9/4 F 6/1* C. Κ 2/1* F 5/2 Canetta G. A. F 6/1* Cauquelin Causey F K M. Chen W.L. Cesari L 7/1 F 3/4 F. Κ 8/1* Chen T.1/3* Carlton D. J Carmignani C. Chaboche J. F 2/1 Caumette P.W. Ε 3/7.G. 1/6 Chang R. Carter Cash P. M 3/4 Carlson G.A. A. N 1. Chargin Β M. J 8/9 Chiba 0.5/3 J 3/9 Castello G. Campbell T. H 3/3 Chu CK.2/1*. M 9/5 D 5/8 K 3/7 M 11/1 P.2/4 . Chow J 3/5. M 10/6 W.L. Combescure Conn F 7/8.I. H. 11/3 C 2/5 CA.P. J 6/1.1/8 G. B 1/1*.L. Cofer 1/4 F 5/9 R. L 11/4 N 2. S . K 2/3 Y.Y. Citeriey B 7/4 Κ 2/1* G. Chou S . B 4/9. N 2. Cords Cort Ν L. PS.4/2 E 5/1 G 2/4 C. Connors M 6/5 M 5/2 K 6/4 M. Cozzarelli 7/4 J 7/2. Ciacci Cittì R. E Chu M.C.L.A.S . K 10/6. Chitnuyanondh Chiù Cho F 5/2 L. R. K. D 1/2 CE. B. Chou CK.4/9 M 5/9 1.A.D. K 12/9 Chung D.L. F 5/12 Costaz J. B 5/13. F 5/4.2/4 N 2. Cornell F 5/6 M 4/4 Β. H.A. M 2/1* L. Cleary D.4/9 Corwin W. K 2/2 Courtois C Cousseran Cowler Cramer Crook Crouse Crutzen L M. F. Coroli 1. .B. Coppens M 5/6 Ν 1. B 2/4. N 2. 5/3 B 1/6. Cullingford 110 D 1/9 P. Chopra J 3/4.W. Chu H.J.R.Chirigos J. Contreras Cook 13/7 C 4/11 Α. Coleman 3/3 M 8/7 L M. J 1/6. CE.N.W. H. P. Cordier Ν M 4/5 G.R. Churchill Churier K A.C. M 2/4 M 10/5 F.Y. Cooper Coppi L H. J Costes D.H. C De Vi U i e r s Dienes E 2/3. G.3/1*. J 3/10 H 4/7 111 . Davis J./1* J 7/11 K. W. Deseleve Devaux Dimelfi M 10/7 G 6/4 Darlaston Darling K 12/6.K. H 4/5. F 5/6 R.3/2. N 2. K. K Cur ioni S. Curtress N. G 10/7 M. K 8/3. D 2/4. G 10/7 Dodge W.J. F 3/4 Curran D. N P.J. D 4/6 Dattaguru Davies I. Day B. K 6/6 Del P u g l i a A.3/3 De P a t e r De Paz De R o u v r a y A.Cummings G.N.4/1* E. N 1.P.W. E 1/5 Del Grosso A. R. Dimopoulos M 2/5 2.V.1/9 J. Deitrich 2.4/2 M 6/3 De K e y s e r Delale H 8/7. 1/8 L 11/3 J 5/8 F 5/4. Dafalias Danay J N 2. G 8/1* I. Daenner 9/9 N 2.J.E. B 4/3.Ll. Daddazio R.L. 7/6 J 7/11.P. L 12/4 De Ngo H 3/3 C L 4/6 J. Deschamps P. J.5/3 G 4/2 M. H 4/2. D 2/8 B. Dixit K.2. G 6/4 Curreri J.S.G. D 7/2 B 3/2a.C. K Deans J.W.B. B. 8/1 K 7/3 D 7/2 N F. Danisch Das L K 12/1. Deeken L. M 9/9 Day S. G 2/3a R. N 2. Dalder 3/2 A.M.F.R.C A. Delaval J N 2.F. K Dang Van Dao 8/7 Y. Dietmann F 2/4 M 2/6 B 6/2 H. J. 3/2* Erb d'Escatha F 5/10 C 4/3 J. Dostal M.W. C 4/8. Β 5/10. Dong R. G 10/1* Enderle Engbaek Engel J. G.E. . G 4/2 Y. N 1. J.N. J 7/9. A. Elbaz Κ 3/9 8/4 Dubois Duff Β 3/1* H 4/7 F.1/9.M. Erdogan N 2. L 9/9 M 7/E . Erbe H H. F 6/6 M 8/5 Ellis W. N 2. Epstein A. Elfmann Κ 13/10 D 7/3 G.J. F 7/7.­H .E. Farfalett i­Casali 112 M 2/5. N 2. L 8/3 J. . J. K 12/11.B. J 7/4 Dustmann C.1/6 H 6/5 J 2/7. B 6/1* P. G 8/1* M.Doñea Β 1/3. Eggen D. B 2/8.R. J 4/8.G. F 1/5 Engelbrektson J 6/5* Engelke B 3/7 L 13/6 Enni s V H. R.T.J. G 2/3 Ettei F.F.B.4/6 B 4/3. Dubois J. Ettouney E 2/3. K C N 2. CG. Dong S.J. B 8/7. M 10/1 Donten K.1/4. Dulac K 11/5. K 11/7 F 2/8 J.1/5 F 7/8 K 5/7. F 2/1. J. M 9/8 M. Drenick F 3/1. Enomoto K. Famiglietti Fanning J 9/4.1/5 Edwards N. E. Ezawa J 2/1* G 4/1* F 2/2 N 2. Y.F. P. L Engel R. L 12/3 K 7/9 El­Tahan Emery H . Κ 4/6 L 13/4 Dowling Doyen Ν. Einziger Eke R. D. H 4/8 Felten P.S. H 5/6 Feng W. L 12/8. Β 1/3 Β 2/5 Favrod J.Fasoli-Stella Fautz P. N 2.J. K 6/8 H 3/7.3/2 K 12/8 D 4/3 CC. Fisher 5/2 D 2/4.4/9 Frank Fritz H 4/2 G 4/4 S. K 13/8 Fukuda Y.M. 4/9 H 6/5. Fredell D 2/8 K 11/11 J.V. F 1/5 Frank T. C.K. G 3/1* Garzarolli Gavarini Gehl Gehlen Gehr F.F. F 3/1. Fischer L D 6/4 J.-D. Garcia J J.4/7 N 2. Frank M. H 5/5. A.3/6 Fu N 2. H 2/6.H. L M. Garnier C. H.G. F. R. Gangl M. Ferguson Fiero M 11/7 F.C.W. S. L 5/8 Fuchs H. Gartner Gauvain 13/9 M 3/3 Gantayat Garas D 2/1 H 4/2 F 6/3 7/8 D 2/1 K 13/1* L 2/1* C 1/6 G 9/2 C 2/2 113 . Filippi Fi I l o N D. H 4/1*. G. H 6/6 B 4/4. H.P. J Κ. Fujita Κ. Μ. L Furrer H. W.L. P. 2/4 H 6/1* L.D. K 6/5 Gambarova Gamby D. L 9/6 H 3/4 M. I. K 13/7. C 3/5 Garwood S. Forasassi Forkel Fouit Fox 1.B.-L. Fleischer T.R. F 6/1*. P. J.A.S.N.E. Fleischman Forgie G. B 3/9 Th. H 4/1*. G 3/2 J. G 5/1*a Goodall I. E 6/5 N 2.Geidel W. H J. F 5/5. Ghosh C 1/2 A. K 8/3.L. S. Gibert D 4/7 R.M. Giuliano V. M.2/4 Α. Ε.A. S. Gorholt W .L.M. J 5/8 J. L 6/4 J. Gregis K 12/6 L 4/6 Goudreau Greco L 11/8 M 4/3 Govindarajan Gray Β 8/4* K 2/5 Gortemaker Goto L 2/3* J 10/5 Goldstein F 2/1.M. Godbout 8/4 J 10/1* P.W . Goodman A. M 1/1* Gluekler E. F 4/6 Geradin M. Glöckner K 1/9. H 5/1 Gorman D. Glahn C 3/8 S. Glazik L. F. Gotoh P.L. J.J. Giencke B 4/1*. Griesmeyer B 1/5.H . Gillemot Gittus B 3/9.C.. Glenn M 3/10 D. L 1/7. Graveleau B 1/7 M 6/5 Greenstreet 114 5/2 Ν 2.K.L. Giuliani E 6/7. Β 3/2 Göller Β. W.J.F.L.N.A. D 5/6 Grainger B. Gomez M. H Graubner U. Jr. W.5/5 K 12/7 J. Gokhfeld Golan B 3/1* E 4/6. B 7/1* 3/2 E 2/3 T.­J. H .M. Β 8/3. F 5/1* C 1/2 M 1/7* K 9/2 F 2/2 . Ν. D. H T. B 5/1 Gorman M.J. Griesbach F 9/2 K 10/7 G.P. C Goto T. M 7/1* Gerscha A. Gloudeman Gobert B 1/3.L. L 11/6 Goradia H.H . F 9/1. G 4/6 Ghoniem N. Gri llenberger Grosberg F 8/2 T. Grover R.E.D.L.5/4 Hastings I. N Guelicher L.L.C. F 8/1 Gupta Gürdogan Guzman M 9/6 0.A.P. M 6/6 Gupta D. Hamanaka F 7/6.3/3. Harriague Hartley K 12/12 K 12/12 K G. H 7/4 F 3/3. K R. Habip 1/6 U.V. D 4/7 Grover R.J. Hayhurst Head 1/3 F 2/8 D.K.Griffiths F 5/5 J. Güldenpfennig S.W. L 5/1*a D 7/6. 2. L 7/4 N 2.C. Guerreiro Ribeiro Gui linger Gunyasu L 1/6 L 7/6 K 8/7 W.C. H.M.T. Harkness S .T.M. L 8/3 115 .K. Hayase B 8/4* L 9/5. Hardrath W. J. Halleux 2/3 Β 1/1*. D 7/6 A. M Y.J. C S . K V. Gvi I d y s Habedank G. B 8/2*. Hammel Han J. M 11/1 Grünhagen A.H. R. G. Harbourne B. F. Hagenson Hagiwara Hahn 2.1/4 J. Heeschen N 2. H 7/1 Guelin P. J.3/1* D 1/2 A.1/7 J 2/8 B 1/6 B 5/9 D 1/1* G 4/4 N 1. F 9/2 N 2. J. B 1/3 M 6/8 F 9/1. Hancock Hara S .4/9 H. H 5/4 K K. N Hai I f i n g e r Hallquist S . Hassanein Haug E 5/5 J 6/6. 13/9 G 9/2 J. 11/3 Gupta A. C 1/3 E.K.L. J.L. L.L. B 7/2 E 5/6 A. .S. W. M 10/3 Holzmann Horie M. Hellen R. K 6/4.3/4* K 13/12 C 3/12 J 7/9 M 3/6 Huang CL. I. N 2. Henderson L 5/2 J. Holman G. M 7/8 Hofmann E.C Higgins K 11/2 J 2/4 Hering Hinton F 5/6 M 11/2 K 13/1*. B 2/8.S.F. H 6/2.J.C.W. Hennart J.2/5 Hsueh Hua T. L 4/7.2/2. Heidebrecht Heine A. B 6/2. P.K. G 1/2. Hilsdorf D 2/5 J 7/3 R. Hoffmann H. T. L 9/3 Hsieh S.W. H 5/2 N 1. Hinterleitner Hirt L 3/6 C. Hellen T. K 11/8 J 8/2 H. H 6/3.C. J 7/1*. Hibbeler E.A.J.Y. F 3/3 Hofmann H. Herren M. C 2/1* Herter J. M 7/1* Hoggatt Hogge Holland J. D 2/4. M 5/4 Hellenberg Heller H.Heglin J 3/10 B. N 2. B 3/10 Holzlöhner U. J 2/9 116 G 6/3 N 2. B 3/4. H 2/1. F 5/4. H 3/5.S. L 4/8 Hovingh J. Helms G 2/3 R. Henning CD.E. H 2/3 H 5/3.W. D 7/4 F 7/4 M. L. Hsieh B.A.D. H 1/2. Horvay G.2/1* Henriksson T.C F 4/4. K 7/5.M.A. Howard G. Hoang K 13/12 H. Huang T.J.4/3 Hornby Hsu H 6/5 F 5/3 C.R.K. M 5/6. N 1. Y. K 13/5 M. B 2/3 D. H 1/6. B 4/1*. H 3/4 B 8/8 Holtbecker H. L Y. Isobata Issler Ito Itoh H 6/4 J 0. R. K 1/3 K 13/7 Igarashi Iida K.C L / J 7/1* F 6/5 1/2 L 11/1* J. Inbasakaran Inglebert Ireland Irisa Irobe M. Iwasaki R. Jr. K 1/7 Hughes T. Jamet 12/8 E 6/6 K. T.J. Jahns L 13/9 11/3 F 6/4 K. Janson L ' F 3/7. Imazu * L 12/8.C. K Jackson D Jain H A. K 13/12 K. Ikonen 13/1 J Ichikawa Idriss 1/3 û 10/6 P. L 11/1* J. Jamieson Janssen 13/9 1/4 M 5/5.Huber Α. G 5/5 Hudman G. M 2/7 L 3/2 * G 6/1 * Y. Ishiwata S. D 1/4 M. Hunsbedt A. D. L 13/1 K 13/1 * 117 .. T. Hughes Hugot Hult D 7/2 T.J. B 2/3 Hudak S.M.R. 4/6 F 4/1* L. Ikeda B 1/2 H. F 2/2 G.F.M. Iwata K.J. K F 3/5 A. G. P.T.D. C 4/3 Hueckel T. W. Jeandidier F 3/1 C.H. Husslage W. G. 4/1 I. H 4/3 K 11/8 Ishac M. Ibanez L < 7/5.R. M 7/2 5/3 7/1 G 4/1* Jakubowicz H . Hundt H J. L. Κ 9/5 Jedlicka J. L 11/5 Jouris G. K 6/8 . K 7/2 Joly J.M. Katz F.E. B 5/6 Kappler H . C 3/13. Kececioglu D. F 6/2 Kawakatsu T. B 1/3. Kamil H . H G. Kaspar G 4/6 E 3/7 N 1.F. Kafka M 3/8 P.2/5* K 4/1* B 6/1*. K 3/8. E 4/1*. D 5/2 N 1. D 6/4. G 4/3 M . Kalthoff Kamal D 4/7.J. Känning Kano J.F. G 10/5 J.L. Katzenmeier G. K 3/6. E 2/6. D 5/1* B 4/8 J. K 9/4. K 13/3 B 3/2 Jonas W.A.A. K 9/1* Kemter F. S.W. Kakodkar J 10/2 A.M. J 9/1. B 6/6 F 4/1* Kawanishi K. K 12/7 Kendall 118 K.3/1* M 8/8 Kelly J. E 4/1* Jones R. F 3/7. Jenkins D. C 4/3 Johnson J. Kanninen M.V. J 9/3 Kasai K 12/3 Y. K. K 13/8 Kazimierzak Kearney B. E 4/5 K 6/4. Β 4/1*. J 8/5. D. 1/7 Kastenberg W. B 5/11 Johnson D. Kaiser M 8/1* A. F 7/6 Jehlicka P. J 8/6* Jones A.Jeanpierre F.C.E. Kasami H . G 9/2 T. Kangas F 6/4 M. Kalinowski Kalnins A. L 10/5 C 3/5 Kathiresan Kato K 5/4.T. K 13/2. L 7/4 Jiyawan R. Jowett J. Jullien M 9/2 J 8/7 F. G 4/5. H 2/1 6/6 C 2/5 G.A. Kjaer­Pedersen N. M 10/7 K 6/8 1.C. O.A. M P. J. Kitade E 6/3* F 4/3 R. K. Kollmann 1/6 W. M 5/1 Konter A. Kosinski Kot L W.P.K. N K 12/6. Koplik 13/1 K 8/3. J 4/8. Κ 2/1*. H 2/6 Knowles Ko N.M. L Kennedy R. G 1/7* N 2. K 9/4. K. M 2/8. C 4/8.J. J Kiciman Kiedrzynski Kikuchi Kim C 3/12 Kircher Kirmser CA.J. K 13/5 P.3/6 G 10/2 Kozeki Kramer G 4/1* K 7/1* B.4/9 Krakowski R.J. Knauf f M. Koori Y. J 9/1.S. A. K Koziol J. Y. Kennedy Keskinen T.A.P. H 1/5 L 2/6 G. Kottas R. M. D 1/5 M. M 11/2 F 6/2. Kowalske D. Khatua E 2/2. Β 1/4. Kratochvil Krätzig K 12/1.W. Kivity Κ 4/3 M 4/4 A. H 1/2 L 7/8 M. H 1/6.L. Kneuss R. Kordina Kost K 13/10 F 9/4 Kobayashi Koch F 9/2 10/5 Kleiber Klemm K 13/8 G 1/6 H . K 5/4. J 10/4. J 10/7 B 3/10 Kondo S. L Kleiser K. E 4/7 König M. Kitagawa F 9/1. 13/5 8/6 D 7/2 J. Kowalczuk G. L 2/4* K 8/2 119 .B. Kitagawa Kleist M 6/6 10/6 G 7/2 M. V. J Y.M.G. CA. G 4/5 W. Kennedy N. W. L 13/5 J 9/1. Kuzelka Ν 2.B. Kurotobi M. A.F. K 13/4 K. J 1/9 Langhans Langui lie Lanning Lannoy 120 A. Kuroda J 9/8. CS. J. G. Krause G 10/6. Kubota Β 8/4* G 10/7 Krishnasamy Krutzik Β 8/2*.M. E 6/6 Kuczera Kulak M 2/7 J 9/6 N. H 8/5 Kuperman K. Krautwasser Krempl P. J 9/6 S.L.M.B. C 1/8 R. B. Krishnan A. K 12/2. Kukkola T. C 2/1* E. Kumar V. F 9/5* J 7/4 E 2/5. L 4/2 Lafore P. Laflen J. W. D. H 6/2 Kunick A. F 1/3 H.M. A. M 9/7 P.2/4. F 6/4 Β 2/1*. G 5/2 Kumpf H.D. Kwee T. Kulcinski Kuroiwa J 10/2. Ν 1.F. T. Krieg L 7/1 R. Krings Β 6/5. D 7/4 V. M 8/8 S. H 4/3 Kurosaki Kushida K 5/3. Lamarre Lambert Landes K 5/6 G.G. C 3/3 Kuntze W. G 2/3a Kuwabara Υ. S.Kraus S. M. G.J.C. L 8/2 J.D. Lardenoye K 9/4 F 3/8 Laboudigue Lam K 12/3 F 5/7 H.K. K 5/5.5/4 K 8/6 Kussmaul Kuzay E 1/2*. J. E 6/2 K 6/8 . J 1/6. G 3/4 J.H. M 7/6 Krishnamoorthy Krivy K 12/4 K 10/4 C 1/11 D 6/3 J 10/1* L. L.5/3 7/3 2/8 Lin C-W.H. L 7/2 L 1/1* E 1/7 Leimbach Leis K.2/4 Lasker L. K 12/6 Lassmann Lavake K. B 1/2 121 K 11/11 .H. C 4/2 B 5/13. L K 7/8 Lin Linder 7/4 K 9/2.W. B. F L. K 11/6 Lin H.A.H. L Lee J. Liu M. F. Lee L. H M 1/2 L 8/4 B 3/10 N 2. Lebey J.J. Leoni R. K 10/2 M 4/6 K 12/9 L 9/8 G 6/2* J Litton F 4/6.J. Lemaïtre J. D 3/1* J.C L 9/3 Lin T. Liebowitz Lievens B 3/7. 1/6 Lee K. Lazzeri D 2/5 F 3/6. K 11/4. G 6/2* Lee J. J. B W. Lethert Levy E. Leonard J.M.H.W.N.T.J. F Lestingi H. N 1. A. F 5/10. 2/4 Lee Th. J 2/9 Larsen E. R.-R. K 12/10. L 4/2 L 5/1b* B 4/6. T. F.K. Liebecq G. J 5/4 J 9/8 L 12/9 M 2/6 L 7/1 K 11/9. CJ. 7/3 J Litewka 12/5 11/10. A. Liu W.C. Lewinski P. Leridon A.M.S.K. L 7/6 Lin T. Liu T. Limberger E.Y. 5/3 8/6 Lee Leigh L G 10/3 Lee Lehmann J 5/6. Lecarpentier F D.M.A. H 3/3 Lin Y.F. L K 1/9. F 7/1 Lee Y.Larder R.N. C 3/13. L 9/5 Larkin P. Marchertas K.R.W.J.M.C Luthra Β 6/5. Marr W. 3/3 F 1/2 S. MacGregor 122 G 4/1* B.J. Li volant Lo Β 4/1». H 8/2 M 8/7 Marrujo Maruyama H 8/1*.Y. Manzel G. J. K 13/2.H. 7/7 D 7/4 D. Marbach K 13/3 D 5/8 M.F.E. Manfredi J 4/2 B 4/9 Mager Malmberg Β 6/7 2/4 Η 8/6. F 8/1 Marston T. G 1/4. Macchi L Μ 8/5 A. Locci J. Κ 11/9.U. Martin 12/4 E 2/1* K Marriott L C 1/11 J. Μ 1/3 F. Loceff Long C. Mamoun J. Ν 2.3/7 D. R. R. F. Κ T.M.P. E 6/2. Β 6/1*. Ludwig Lui Κ 13/1* Β 8/8 S. Α. K Masao T. M. Κ 7/4. MacNeal J 3/4. Β 1/7 Louvet Love Lu C 4/8. T. L 1/7 G 6/1* Masao T.M.Liu D 3/5 Y.H.G. A. T.L. K 7/1* Masuda M. L 3/1* Malcher L. Ν 2. D 2/7. 3/7 N 1/4 2. G 2/7 . F 9/5* Ma Ma Β H. Ludwig P. 1/2 D 2/1 Marchaterre Mark 5/6 L 9/4. M 6/1* Man E T. Malkus D. W.4/3 G 2/6.H. G E.C. G 1/7* Maier G. A.W.C.G.R. Lucia Κ 9/5. F 6/3 Martynenko M.2/4 P. G 9/4.S. MacEwen 9/8 C 4/8 V. Κ 12/5 J G.H.J.Y. 2/3 12/6 M 10/3a W.I. A. N 2. G 1/3 N 2. Misfeldt Ib. N 2 H 7/2 K Mohr N 2. P. Meier J S. Meyer J.H. Mehner Ν 2.4/4 F P. R. D 4/5 N G.Matera L 12/4.R.W. Mizuta M.2/2 K 10/6 Mehta Me l i g i A. E. Meneghini Α. Mazzarella C L 3/4 McCarville T.M. 7/6 B 1/5 C 2/1* A.K. D 5/2 J B. C 2/4 Millel P. C.R. Mi ki 7/6 M 3/1 J.W.E.J.E. K 10/5. McHenry N H. Maxwell D. C 4/7 Ν. G 10/3. F. McLoughlin McMahon McMaster W. Miller Mi Ine Α. J 8/9 13/4 K 10/9 1/4 D 6/2. D 3/3 Miller CM. N 1. D 5/9 K. D CL. Matthews Maurer L S. Meskouris C 3/11 F 3/4 Mercier Meschkat B 8/8 2.1/9.R.K. R. W.2/4 H 6/6 K.5/4 McCauley B 8/1*. Α. Messemer Meyers J 8/5. Matteazzi Matthees D 7/1* J.1/6 L 13/3 N 1.E. Mizuno S. G 8/2 Merckx K. Meyer z u r 2. Mayr N 2.L. Minato 8/6* M 10/4 Meyer Millard J K 8/2 K.B. 1/2 G 7/2. Mizuno L 4/7. C 1/11 I. Maynard CU.5/7 F 3/4 S. C 3/10.1/4 D 3/5 Capellen Middleton H. W. Mitterbacher Miyamoto Η. D 6/3 123 . Mitchell A. · L 4/3 Mukherjee S. 7/7 M 11/6 L L 10/5 13/10 Nakayama Nashiro 12/1 H 5/3 Nahavandi Nash L J 3/5. L W. M 2/4 C 3/6 K. Morris 9/8 H H 4/2 P. Morgan M 1/4 1.A.E. L Müller W. F 5/11 Muk h e r j e e S.Ch. K 6/9 Muki R. Moses G. Motohashi Mroz K 12/2 Z.D.N. D 3/2 S. D.A. Nakatogawa M.Moir N R. Nakamura K. J. K 8/5. M. Mutzl 8/3 L 3/1* Murakami Muto I. Nakatsuka L 8/1 B 3/8 G 1/6 F 3/5. Murty K 3/5 1. L C 2/2* K 6/5 Mukherjee Β. B 4/2 Muller­Lyda Munro Murray S. K. L K 12/2. A.P. 1/4 I. Morgand Moribe L M 3/7.1/3* F 7/3. E. F 6/2.P. Nagato D 3/6 L 1/4*. K Mortgat C.W.2/4 B 6/1* S. 2/6 K 11/3 K 12/3 . M 10/1 Müller G. T. K. J. N Mondkar Monsler Montagnani Moore Moosecker W.T. Nakagiri S. K 3/4. K 13/4 L 4/3 E 2/4 8/8 Morrone A. Morjaria M.N. J 3/4. Nakanishi T. D. Morel 1.W. W.2/2 E 3/1* M. Mösinger N H .L. F 2/8 Narayana A. Mueller M 3/8 F 5/9 P.J. T. Α.L. Nishikawa Njo G 7/3 L 12/5 L 3/3 B 7/2 K 11/3 M 9/8 F 6/2 H. K 1/4 M. Ohte S. D.C.H. Ohkawa Ohnami H 6/1*. Noda C 1/5 N. D 1/4 3 Obernhuber . Newman J.R. H 4/9. Ogiwara J 8/1 C 2/5 M 10/5 G. N 2. H 5/7 Oberpichler O'Brien T. Needleman Neef Α. Odar E. K 1/4 N.J. B. Nerli G. 10/3 D 6/6 Ohmori Ohno L D 6/5. T. W. Nishiguchi I.J. Oehlberg R. Odette W.H. No r r i s D. K 5/1* R. H 6/2 13/7 Okabe M.Α. C 1/3 1/5 Nova R. O'Donnell Ogura Y.P. Ng Jr. K 7/8 J 8/9 Ohsawa Ohta T. H 1/1«.Naus H 3/6 D. Nemat-Nasser S.5/2 Nemet J. K. L 1/3* N 1. K 1/7 Nuno H. B Notley M. K 9/4 G 1/6 I.S. G 1/1* D.M. L H 6/5 Nesitka A. L 12/8. T.D. J 4/4 M.Y.1/3* J 8/8 K 3/10 N 2. A. F 9/1 H 4/3 Ohnuma H. Nguyen Dang N i c ho l s Ni i n o H. J J 4/5 L 13/9 4/5 125 .F. 0'Connor M.. Nelson T. K 5/5. M 9/8 Okada K.3/3 L 6/1*.J.J. Ohsaki Y. Nei I s o n Jr. F. Owen Pagay F 5/3 E.H.R.S. D 6/3 Panzeca T. Olsen Ople 1/10 C 1/9 CS. A. Pandarinathan Paranjpe L 5/3 Κ 4/6. Pabisek 1. Ρ G 8/1* N 2. C 1/4.H. Pecherski 8/6 D 1/1* Pauwels Peano L F 7/7 G.T a n o n Perla M 6/6 Α.A.F 5/7. N Osterie Otter B.N. Ottosen M. Pattanayak N C. D 2/5 Pe l l i s s i e r .P.2/5* . 7/3 D 7/4 M.V.2/4 B 4/2 N. Oliver K R. C 1/2. E 3/7. Pendergrass 126 M 5/2 R.E.B.R. J. M 2/7 Panisko Paris 8/5 F 5/2 S.S. Oland C.S. M 7/7 L D. K 2/6 Okrent D.S. Paidoussis Pal 11/5 H 2/5 D. H 3/2 Okamura H.R. Patel 3/4 D 3/7 P. H. F. L.F. Palamidessi A..B. 1. Β N.R. Pedersen 2. L 11/7 Κ 11/11 Κ 7/4 S. M. Parker Κ 10/5.J.R.3/8 H 3/1* Orkisz J.. Paxson E.G.2/3 B 3/2a.K.B. L S. N Jr. Κ 6/7. Pagano Pai L N. Peehs C 4/2 Jr. Palgen C 1/10. Parmeggiani Pasotti A.F.C. R. O'Neill R. G 5/1*a J. Palusamy Ε 4/4 L 3/3 V. D. Patel Y.3/6 K 2/1* M 10/2 Κ 10/9 N 1. Oldfield G 2/7 W.M. M 7/4 Ortman M. Place T. 8/2 L. G. Pratt Pug h E 5/1. Porowski L G 8/2 J. L 11/6 Phillips J.P. L 6/1*.S. M 1/4. Pouyet Prachuktam Prantl J. B 3/1* G 2/4 127 .J.4/5 G.A. Quartapelle N 2. Prothero L 10/3 K 10/3. Polizzotto K 2/7 3/8 Pietri Pittner E 6/5 8/4 Phillips Piatti E 6/1*. L 3/4 N 2.Pe r r i n D 5/5 R. K 1/10 J 9/3 F 5/8 K. Powell J. Pollard C. CE. B 2/6 L 11/4. Ploeger Pohl E 1/6. .S. J 3/8 Powell GH. Popelar L 12/4. Phi l i p p a c o p o u l o s A. . R. G. F 7/7 Pottinger Potts 12/6 G 9/2 CH. L. Quirk N S. W. Petrequin P. E 5/2. L 6/5 Petrinä P. Pettigrew Pezzi L M. M 3/3 Pister K. E 1/7 N 2.­J. .J. M 2/6 1. R. R.2/3 L 12/3 G 9/4 M 4/3 T H. Ponsot Possa J.3/2 F 4/5 F 3/1.2/3 P. J 1/4 Petroski H . J Pi c a u t P.W. .W. K J.C Perzyna L P. DH. H .R. Philip K 1/9 J 8/4 J 9/7. K 10/1*. 10/7 M 4/2 Prost Pulliam J G 1/1* G. A. Peters 1/5 G 4/4 W.J.W. E 4/2 D. Pfeiffer Α. G. G 8/1* Radini R. C 3/5 M. J.N. D. S.J.D. Reich M. J 9/4.T. Ranganath Ranjan Κ 10/6. Rashid Y.1/1* Remy F.E.1/5 J.2/4 Ragland W. Rieger K 13/5 C 1/6 Reuther Ricci L 13/7 H 2/6.C.R. W.S. J 8/5. K 4/4. N 2. K 4/7.D. Reuter W. 2. N 2. B 5/7 Renard J. N Reymann A. J. K 7/9 J. Redmer Rest M 4/3 G 10/7 Rardin Reddy 6/9 G 1/5 G.3/2 Ragheb M.R. A.W. Rebora Β.Rabbe P. N 2. M 6/3 Reed J.D. H 4/8 D. D 3/3. Righetti Rissone 128 K 5/2 F 5/8 T.P.K.S. Richardson Richter J. G 10/7 J S.A. G 7/3 Ramamurthy Rau Β 3/2a. M 9/5 .S.M. J 9/2 Riesemann von Rigby G. E.L. J 7/9 Raeder J. D 5/8 D 6/1* P.G. Raymont J. Rawls M 9/5 5/11 B 3/2a.V.V.1/2* B 7/4 F 5/13.A. Reale D 3/8. N 1.5/7 K 4/5 Reeves CF. K 4/3 D 1/7 J 5/6 L 13/7 J 8/6* J 3/10. Ramani Rao E 3/5 G.M.J. H 6/2 Rautenberg J.3/3 N 2. F 9/3 N 1.V. N 1. I. P. Raheja R. P. Reed R.A. K 4/2 Riera M. Rieck P.M. Raju Ram K.C. T. Ramm Β D.2/3 L 9/9 K 4/3 Riech H. G 3/1* Robinson Robutti 4/5 H 2/5 G. Romander L 7/8 L 12/9 R.G. J 8/5.1/5 Rüdiger E. M 3/7 Rubinacci G. Sakuta H 4/8 D 6/5 G. Y. D 3/2 E 5/6 Sangalli D. 3/7 F 7/1 E. J 3/3 Sasagawa K. W. J o/9 C 2/4 129 .M.L. Rustagi R. M 1/5 S. L 4/7. Sakuyama T. Sako 9/3 κ 10/1* Rozenblum Sage M C 4/5 CM. Rolstad L 5/3. Sadowski A. Rowe H 2/6.J. Sattele J 8/6* B 5/11 Sakaguchi Salz E 5/4 J 8/4 F. Rogalska E. Rogers J 4/2 M 1/5 J. J. R.L. K 6/8 N 2. S. Y. E 1/3. H 2/5 K 9/5 N 2. Robert 6/2 J 3/4. Rodet E.H. Roche R. Saurwein F 9/2 G 7/2 H 1/7 M. Satoh K 13/10 N 2. J.S.C. M Rodriguez Roemer C. Rouiller Roux Row F.4/4 K. Saiga Y. N. Rizkalla Roberge Α. Ronzoni L 12/2. D 4/6 Rutherford Sacchetti D.M.4/6 D.N.E.S. Sackman J. D.Rivard Β W. F 9/1. N 1.J.S.C H Robinson J. L 12/3 Robinson G.2/3 K 9/1* L 1/7 J 4/8. F 9/4 E. Sadakov O . Sahay B. Η 5/6 C 1/11 D. E 6/3* F 8/2 Schrader Schultz M 8/6 1/5 Schöning Schuëller 6/6 M 11/3 Schnellenbach Schomburg B K 12/7 J 9/3. Seth V. B 6/1*. Senski 4/8. K.N.J. Shaffer Shah 130 H 1/2.H. Schürkamp H. F 6/1* G 2/1* G 10/7 M 9/2 K 8/7 B 6/7 H 7/2.T. H W.K. Schumann U.G.H. H 6/3.E. D 2/8 L. Scala 1/2 C 3/10. U. M 10/6 M 6/3 J. Sermet E. L 6/5 Schamaun J. D. G. Scott M. J K 13/10 H 2/3 J 3/1.F. S. W. Scholl R. V.K.G. Schmitt R. Schulz H. H. K Schaefer A. Schoeberle G. J 7/6 C 3/3. M 8/1*. 5/6 D 1/7 L 12/7 H 3/8 K 7/2 B 6/1*. M. Schneider Schnell U. J 10/2 G. G 1/7* Schaller K. K 5/2 E 6/6 S. Sawhney D S.O.J. Schimmelpfennig Schlafer K. .Savino E.2/3k L 6/4 H 7/1 M 8/1* B 6/4. Scholl K.L. G 6/4 Seaman Seeberger Seed Seino Sen J. N 1.S. Sawruk W. D.E. L Schmitt W.R. E 4/6 Scavuzzo R. 12/7 H 3/8 B 1/4.-H. L Schwiers H. G. K. Server W. W. III Schlechtendahl Schmidt E. E 1/6 13/6 Schuster H. J 8/12 Schankula Scheibe C 3/11 M 3/9 M.B.H. H 6/4. H 6/4. C 3/5 Scibak W..I. M 4/3 G 1/7* Steele L.E. Smolderen K 13/8 1/6 Singh Sliter G 6/5 F 7/5 S. A.Shankar S.5/3 Soran Spence G 2/6. F 2/6* Sharabi Sharpe R.R.H.D. Spcidel D 2/6.4/9 M.R. 3/10 E. K 5/4.H. B M. M. P. F 5/8 Smith I.B. Shockey D. Snyder K D 3/4 G.D. J 5/7. G 4/4 Smith E. Stangenberg Staniforth Steele H 4/4 J. K 3/1* Soenen J.2/3 M 3/8 S. N 1.1/2* M. S. J CF. Stahlkopf F 9/3 K.E.E. J 4/2 5/7 M. N 2.P. Skrikerud K 11/3 K 13/9 Siang Skerget K 4/1*.K.L.E. Spilker F.N. D 2/2 Steiner G 5/4 N 2. D 6/1* Shao L. H Sigal G. L 4/1* H. 8/9 Shimizu Simmonds K 6/4 L 13/5 131 . N 2.G.E.D. J Shannon T. Sherbourne Shibata Shida Shih 9/1 J 9 / 1 .W. P. G 5/2.G. C 4/4. M 2/1* Somma Spadoni 1/6 K 8/9 CO. G 6/4 H. G 10/5 Silva M. Smith F.A.W.R. Shiraki K. C 1/4 Steine L. K 11/3. J Singh S. J G 2/6 7/5 E 1/1* Ch. M. H 4/6 Smith R. J 8/12 M 8/9 Smith C.A.N. B 6/2 H.J. K 2/6. G 1/4. R. H. K 8/8 Sinha R. Smith P. Steele W. M 5/5. Subramonian Subudhi G 6/2* Κ 12/6. Κ 13/4 Κ 4/4 Suwabe Α. Takahashi Takeda 7/2 D 5/1* W. Y.R.D. Stoner K 13/3 Η 7/5 H.N. K 10/2 Stetson M. S.D. Takemori 12/12 L 10/1* J Η.4/7 Strona P. Stephenson Η 8/6 M.D.V. Swamy K 11/1* 2. Κ 11/10 Κ 6/6 D. M 7/2 132 Μ 10/7 Μ 11/4 P. Ν 2. L 8/1 Tamaki T.S t e i n h i Iber Stelling K 13/2. Κ 5/5 Suzuki Α.W.P. L 10/4 Suzuki Κ. M 4/7. M 7/2 M 11/4 . Κ 5/5. Κ 9/4 Y. T. Sugiyama Sun N. L 7/7 B.-A.P. S. Κ 13/9 Svalbonas V. H. Stora R. CM. M. C 1/7.D.C. Takeuti Takikawa 5/4 J 1/2 J 4/4 Κ 7/1* F 3/7.A.T. F. Szczepinski Tagart T. Sugano N. S.2/4 L Κ D. Μ 5/7 SviatosLavsky I.2/4 M Streibl Stura K 2/5. Swanson Swelim J. J. M 4/8 Ν. Tabakman Ν Β 4/6 H.C. K 13/4 Tanabe M. Stoddard W.B. Y.A.P.E. Takasaki 1.C. Sterkel H. Stockton Stoker Stone J 1/1*. Stouffer Ν 1/6 L 13/8 J 2/9 C 1/1* D. L 4/8 J. K 4/5 Stevenson J. Takezono Jr. Swenson C 1/5. H.. Stephen D 1/1* J. L.J.3/8 R.G. Tremblais F 5/13. Turland B. N 2. E 4/2 Tohdo M. M 1/6 Α. Tomassetti Tominaga G. Tezduyar H . JH. F 6/2 Tsushima Y. B 3/3.T.J. K 13/9 Tsugawa T.D. Torrey F 5/3 C 1/10 Η. Taylor L.M. Turula K 11/5 K 4/7 Theuer Tow K 7/3. B 5/4 Taylor R. Taylor C. S.E.D. M 4/8 Α. F ill G. N 2. K Tsuruto C. P. Tang V. K . Ting E. K Taroni Tas J 7/11. H .T. Tatro Too D 4/1 C 1/7 Y. Trbojevic 1/2 C 4/12 M.L. Többe N 1.M. M 4/1* Teasdale R. 6/2 K 7/2 N 2.5/3 N 1. Tsuchiya H .Tanaka E. K 1/1*. K 7/8 Tanaka K.M. K 5/5 Tanaka N. L 12/1 Tanaka H . Truffert J. .C Ting Y. F 7/4 Thomas R.G. Tanigawa Tao B 5/4.V. H 7/4 Thomson S. D 1/9 8/5 K 13/4 B 3/5 J 10/4 L 1/3* 133 . Tokarz F. J 4/6 Tang Η. .W. Thangam Babu P. D 1/8. Tessier JH. Trantina K K 3/1* J.1/8 N 2. Tvergaard L 13/7 G 6/1* B D.4/9 E 3/5 K 11/4 E.D.J.4/8 V.3/5 B 5/6 D 5/2 Tobin R. W.F. M 11/6 Verbiese S.L. Ujiie K. E 4/4 Β 3/2 E 6/7 L 9/4 M 3/5 K 11/11 G 6/3 N D J 9/5 9/5 Β Ν L 9/3 5/2 Ε 5/1. Vi H a r d Β. Uesugi F 3/7 S. K 8/5 F 9/1 Umemoto T. Umeda T. F 5/11 5/2 Β 6/3 Μ C 1. Vlach B.J. E. H. Vanderglas M. van Renterghem van Rij 2/3 J Β M. Valentin R.A. A.M. F 2/8 Uragami K. 1. Β 6/3 Verpeaux P. G 2/3 L 4/8 Veith Veluswami Μ. Valente G. G 1/1* L. Verzelletti Vidard M.A.Uchida J 4/4 T. F 3/2 J 7/1 L 13/10 . Vitiello Vivoda E.M. Vitale E. F 2/3 B.N.2/4 2/5 E. J 4/5 M. Vardanega Vaz 5/7 J P. K 7/8 Uchiyama S. van den Hoek Varga F 9/2. van de Ree van Goethem 3/7 Κ Β 2/6. Udoguchi T. Votava Vrillon 134 Β 2/8. D. G.J. Valathur M. van der Hoogt Η 2/4 G. Vendhan CP. Ueda F 9/1.E.H. L 10/5 Vagliente Vaish Κ V. van Campen H. J. Vogelsang Vogl W.J. Μ 2/2* H.1/5 2/3 Κ 6/6 T. J 3/7 Walter P. R. L P.2/4 4/4 D 2/2 Weissbacher L.A. G 4/6 135 . Wilson W. M 4/2 Warnke E. Wang P. Wallroth 13/3 H 4/1*. Wei F.K.4/8 M 2/2* J. Wester Wiffen K J.Y. Wheaton H 2/2 8/3 Weppelink West C 1/10 G 5/5 P. F. Watanabe Y. N 2. C 1/4. K T.W.H. F 3/7 Wahi K.J. M.R. J T. B 1/8. 1.J. C 2/6 D 7/4 L 13/4 J 9/8 G 4/5.S.C. Z. Wilhelm C 3/5 J. Wilkinson Willam H 7/3 R. B. 8/4 G 5/2. K Ward P. K 3/2 H.5/1* H. F 2/8.L. Washby V.P. H 6/3 Walluschek H 4/2 B 2/6 J.J. S. K. L Waine Walker CF.E. K 6/3 Walser A. K. K 6/1*.2/2 Wang C. Weithäuser We l i e i n H. Wells M 6/4 D 7/3 R.D. B 1 / 1 * . Weimar 1/2 K 6/1* Webster Wehner K 4/4 Watanabe Weber E 5/3* H 7/2 Waszczyszyn Watabe E 2/2. B 5/2 Wesenberg D. Whitehead 13/8 E 4/5 H.R.Waas G.E. N Wazzan A. J M 8/6 J.P. Winkel G- Winkler S.P.R. Watanabe E 1/7 L 11/7 K 1/1*. N 1. H 1/1*. 2/3 D 4/8 N 2. Wada Y.P. W.D. C 2/4 W. J 4/1* Watson R. Willaschek Wilson R. Zimmerman T. 8/12 J 4/5. 2 / 4 .K. Ziebs J.2/4 Yun K 8/4 C. Zolzettich A. Wong C Woo H.CK.R. H 2/1 B H 1/7 3/2* E 6/4*. Witt A. K 10/7 Y. C 2/5 W. N 2. Yuuki R. Zemann M 9/8 5/2 Yoshimura Yoshizawa L 5/4. Wojewodski Wolf W. Witt F. J..Z. K A. J 4/7 Yamada Y. M 10/5 Wu T. J Yerkees G 3/3 8/4 Κ 5/1*. L . Yamada H. 12/4 E 1/1*.C.Wissmann J.A. Zehlein 136 E 4/1* B 4/5 K. M 6/7 H. Β.3/3 Η 8/7 Wu Yilmaz K 8/9 Ν 1 . Zeisser P.T. N 1. G 1/6 Zarka J. G. F 9/2.H.-C. Yamakawa T.K. J 8/9 Youssef M.J.S.K. F 2/8.P. W. Yoon N 2.R. M 7/4 M 5/3 Wu S.W. Wolfer Wrana M 7/3 1/2 M 3/8 N 2. H 1/1*.4/3 . H 6/6 G 2/2. E 5/2 Yamada K. Zeuch W. Yoshioka D 5/8 G 2/1* Yagawa Zeitner M 2/4 M 11/2 S. D 4/4. E 3/4 G 2/3 Ziegeldorf S. F 8/5 C.H. J Yoshinaga T. J Yamamoto S. Wolff P. C 3/6 H.1/4 H 2/2 M 6/4.B. H. L 3/5.H. Yeh G. Wullaert R. K 7/1* Yang C.G. CDNA07047ENC . 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