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. JAEGER ■ Bruno A. BOLEY

Vo l . 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 Materialprüfung (BAM), Berlin

United States Nuclear Regulatory Commission, Washington, D. C.

NORTH­HOLLAND PUBLISHING COMPANY

for

THE COMMISSION OF THE EUROPEAN COMMUNITIES

PATRONAGE The 5th SMiRT Conference and its associated Pre- and Post-Conference 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

EXECUTIVE COMMITTEE Thomas A. JAEGER, General Chairman, Scientific Chairman

and Organization Chairman Direktor und Professor, Bundesanstalt für Materialprüfung D-1000 Berlin (West) 45. Germany

Bruno A. BOLEY, Scientific Chairman and Deputy General Chairman

Dean. The Technological Institute. Northwestern University Evanston. Illinois 60201, U S A . Raymond K. APPLEYARD, C.E.C. Representative Director General. Directorate-General 'Scientific and Technical Information and Information Management' (O.G. XIII) Commission of the European Communities. Brussels, Belgium

F. CACCIA-DOMINIONI, C.E.C. Representative Director, Research. Development and Nuclear Policy Directorate, Directorate-General 'Research. Science and Education' (D.G. XII) Commission of the European Communities, Brussels. Belgium

John M. GIBB, Secretary of Executive Committee Head. Department for Dissemination of Research Results. Luxembourg, Directorate-General 'Scientific and Technical Information and Information Management' (DG. XIII) Commission of the European Communities. Brussels. Belgium Robert AVERY Director. Reactor Analysis and Safety Division, Argonne National Laboratory. Argonne, Illinois 60439. U.S.A.

Franklin E. COFFMAN Acting Director. Division of Development and Technology. Office of Fusion Energy. United States Department of Energy. Washington. D.C. 20545, U.S.A. Lawrence C. SHAO. U.S.N.R.C. Representative Director, Division of Reactor Safety Research. United States Nuclear Regulatory Commission. Washington. DC. 20555. U S A .

Jean RASTOIN, SMiRT-6 General Chairman Chef Département des Études Mécaniques et Thermiques. Commissariat à l'Énergie Atomique. Centre d'Études Nucléaires de Saclay. Gif-sur-Yvette. France

PUBLICATION MANAGEMENT Mme. J. STALPAERT, Commission of the European Communities, Directorate-General 'Scientific and Technical Information and Information Management' (D.G. XIII) Department for Dissemination of Research Results. Luxembourg

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. JAEGER ■ Bruno A. BOLEY

Conference organization by:

International Association for Structural Mechanics in Reactor Technology

Commission of the European Communities, Brussels

¡n cooperation with: Bundesanstalt für Materialprüfung (BAM), Berlin

United States Nuclear Regulatory Commission, Washington, D. C.

General Chairman: Thomas A. JAEGER

Bundesanstalt für Material­

prüfung, Berlin, Germany

Dep. Gen. Chairman: Bruno A. BOLEY

Scientific Chairmen:

Tilomas A. JAEGER

Bruno A. BOLEY

Northwestern University,

Evanston, Illinois, U.SA

Organization Chairman:

Thomas A. JAEGER

NORTH­HOLLAND PUBLISHING COMPANY

for

THE COMMISSION OF THE EUROPEAN COMMUNITIES

Published by

NORTH-HOLLAND PUBLISHING COMPANY — AMSTERDAM NORTH-HOLLAND PUBLISHING COMPANY — OXFORD

for

THE COMMISSION OF THE EUROPEAN COMMUNITIES, DIRECTORATE GENERAL SCIENTIFIC AND TECHNICAL INFORMATION AND INFORMATION MANAGEMENT

Sole distributors for the U.SA and Canada:

ELSEVIER NORTH-HOLLAND INC. 52 Vanderbilt Avenue New York, N.Y. 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.

© Copyright CECA, CEE, CEEA Luxembourg, 1979 All rights reserved. No part of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying, recording or otherwise, without the prior permission of the copyright owner.

CONTENTS

Foreword 7

Guido BRUNNER — Member of the Commission of the European Communities

Welcome Address 9 Dietrich STOBBE — Regierender Bürgermeister von Berlin

Preface 11 Thomas A. JAEGER — General Chairman Bruno Α. BOLEY — Scientific Chairman

Topical Scope of the Conference 15

Topical Grouping of the Conference Sessions 17

Table of Contents 21

Authors Index 103

FOREWORD

This International Conference on Structural Mechanics in Reactor Tech­

nology is the fifth of a series which started in 1971 in Berlin. Thus, with

SMiRT­5 the series is as it were, coming home again, and I should like

to thank the Senate of the City of Berlin for acting as host once

more.

The Conferences have throughout been truly international bringing togeth­

er participants from some 30 countries. This is a reflection of the

world­wide significance of the problems on which they have focussed;

many of these problems are not just technological, they are also of

direct relevance to nuclear safety. I am particularly glad that such issues

are being discussed both thoroughly and openly.

SMiRT­5 will include in its program for the first time a division on the

structural mechanics problems of fusion reactor plants. This is a sign of

the times, 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.

Quite generally, 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; 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.

H ^ - c t ô ^ {_^Τ\ΑΛΛΛΛ&^~

Guido Brunner

Member of the Commission of the European Communities

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. Our efforts are also aimed to make Berlin even more a focus of research. 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. It is, consequently, concerned with problems which are of particular interest to the indus­trialised countries and which, moreover, affect all of us. From production of energy to the economic essentials of our well-being — I wish the Conference every success. 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, 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.

Dietrich Stobbe Regierender Bürgermeister von Berlin

Bruno A. BOLEY Scientific Chairman

and Thomas A. JAEGER General Chairman

10

PREFACE

Reactor Technology and Structural Mechanics

Reactor Technology requires a synthesis of many skills. The ability to solve the structural mechanics problems encountered is of vital importance for achieving economic, reliable and safe exploitation of nuclear power.

The rapid development of reactor technology has given rise to a multitude of problems in the area of structural mechanics, problems which arise from a diversity of new materials used for the different reactor system components operating under severe environmental conditions and postulated loading. Fur­ther impetus for improved technology stems from the great emphasis that must be placed on considerations of reactor safety; here again the role of structural mechanics is paramount.

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. Structural mechanics has thus been forced to develop rapidly, not only in the area of analysis coupled with complex laws of materials, but also in the related disciplines of computer methods and quality control. Great advances have been made during the past decade, but severe problems still lie ahead.

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. We have already noted that the answer to many considerations of reactor safety undoubtedly lies within the realm of structural mechanics. The words of Dr. Altiero Spinelli, of the Commission of the European Communities, in the Foreword to the Proceedings of the First SMiRT Conference, are valid today with undiminished force: "Structural mechanics are at the very centre of nuclear technology, because it is the safe, reliable structure that counts. The major problems in building today's reactors and developing tomorrow's are mechanical and structural."

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. Thus, 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.

Since the basic concept of the SMiRT-Conferences did prove its vitality and adaptability to the changing needs of the field, we should like to restate it

11

from the Opening Address of the 1st SMiRT Conference (Proceedings of the 1st SMiRT-Conference, Vol. 1, Part A):

The SMiRT-Conferences have been designed for a type of multi-dimensional communication.

First of all, the specialist can communicate with experts in his own field. This is the usual linear dimension of topical meetings.

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 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.

Due to the truly international character of this meeting there is also a fourth dimension of communication across the boundaries of countries.

The 1st and 2nd SMiRT Conferences, held in Berlin in 1971 and 1973, the 3rd SMiRT Conference, held in London in 1975, and the 4th SMiRT Conference, held in San Francisco in 1977, provided a most useful meeting ground for reactor technologists, mechanical and civil structural engineers, and engineer­ing mechanics scientists from all over the world. The 5th SMiRT Conference maintains the high level of contribution from engineers and researchers from all over the world, and is instrumental in increasing the interaction among fundamental and applied workers in this vital field.

The broad field of structural mechanics in reactor technology has been subdi­vided, as in the previous SMiRT Conferences, into topical divisions. In this Conference, each of these has been organized by two Division Coordinators, whose individual and collective efforts have played an essential part in the shaping of the Conference programs. Each Division contains a Principal Lectu­re, highlighting the present state of the field and pointing the way to possible future developments.

SMiRT-5 includes a new division dealing with foreseeable thermal, materials engineering and structural mechanics problems of future fusion reactor power plants.

Acknowledgements

Many persons who have worked so hard in the planning and organization to make this Conference a success would deserve acknowledgement. But it is not possible here to mention all of these persons by name. There are, how­ever, a few people who should be mentioned individually for their outstanding work.

The Transactions of the Conference have once again been produced by the Directorate-General for Scientific and Technical Information and Information

12

Management of the Commission of the European Communities. Special

thanks go to Mme. J. Stalpaert of this Directorate­General, who acted in the

capacity of Publication Manager and has accomplished the monumental task

of assembling, printing and distributing in time the SMiRT­5 Transactions.

We are grateful to the several co­sponsoring and cooperating organizations

and societies for their extremely important cooperation.

In addition, the Conference organizers are grateful to Mrs. G. Gill of the

Bundesanstalt für Materialprüfung, Berlin, who served as Secretary to the

General Chairman and Scientific Chairman, to Mrs. E. Warren Secretary to the

Deputy General Chairman and to Mrs. E. Kleversaat of the Department of

Organization and Operation, International Congress Center Berlin, for their

capable and devoted efforts at all stages of the Conference organization.

We are sure that the present Conference will form a memorable link in the

chain of SMiRT Conferences, and wish to extend our thanks to all authors

and participants, and to all those who have helped so much in the long

months of planning, for their unflagging support and assistance.

h S¿J\tuu> *Γ

Thomas A. JAEGER Bruno A. BOLEY

General Chairman Scientific Chairman

13

REACTOR TECHNOLOGY Solutions for Special Problems

I REACTOR COMPONENTS

REACTOR CORE: NUCLEAR COMPONENTS

GEOMETRICAL

IDEALIZATION

MATHEMATICAL MODELS

OF MATERIALS BEHAVIOR

IECHANICAL/THERMAL

BOUNDARY & SOURCE

¡ CONDITIONS

Basic Components of Fui

■¡os REACTOR CORE: STRUCTURAL COMPONENTS

Fuel Element Assemblies.

PRIMARY COOLANT CIRCUIT STRUCTURES

Piping, Junctions. Bellows;

PRACTICAL EXPERIENCE

REACTOR MATERIALS

NUCLEAR MATERIALS

Metals

Ceram ί α Cermeti

STRUCTURAL MATERIALS Metals Ceramics Concrete

8

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.

The Conference contains presentations on all aspects of engineering mechan­ics and nuclear (fission and fusion) reactor engineering having direct bearing on the analysis, design, reliability and generally on the safety of power reactor mechanical and structural components and systems.

The papers may be theoretical or experimental, applied or fundamental in scope, or a combination of these indeed; 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.

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, deformation, stability, and limit load of all kinds

of nuclear reactor components and associated equipment (e.g., reactor fuel elements, solid moderators, reactor core support structures, reactor vessels and piping, reactor containment shells) on the basis of the theories of (thermotelasticity, (thermo)plasticity, (thermo)visco-elasticity, and limit load;

• for the analysis of stress and strain under mechanical and thermal cycling conditions (shake down and low-cycle fatigue);

• for the analysis of crack propagation and fracture in reactor fuel elements and reactor pressure vessels;

• for the dynamic structural analysis of vibrational and shock response behav­ior of fuel element assemblies and other reactor structures, induced by internal conditions (hydraulic flow, pressure pulses, neutron pulses, thermal shock) and general loads encountered in accident conditions, and by exter­nal conditions such as seismic forces and ship motion;

• for the analysis of interactions of thermodynamic and fluid dynamics phenomena with mechanical behavior of reactor components;

• for the analysis of the influence of structural characteristics on the perfor­mance and selection of major dynamic components in reactors;

• for the structural mechanics analysis of first wall structures and magnet structures for future fusion reactor power plants.

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.

15

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. Special topics are (e.g.): microstructure and mechanical properties; continuum models for nuclear fuel materials; rheological behavior laws of structural metals at high temperatures; and fracture mechanics of pressure vessel steels.

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; and fluid dynamics phenome­na with interactive coupling with mechanical behavior of reactor compo­nents.

Computer Methods in Solid and Structural Mechanics

Besides the application of analytic and numerical techniques to special problems of structural analysis of reactor components, 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. Special emphasis will be on modern computer methods in solid and structural mechanics.

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. (This is closely related to the topic of reliability analysis of mechanical reactor components and systems.)

Design Conditions; Reliability of Mechanical Systems

Probabilistic methods and statistics as applied to structural analysis and safety assessment of mechanical and structural reactor components and systems. This includes reactor internals, reactor vessels and primary circuit, and engi­neered safeguards including containment. Within-the scope of the topic is the specification of reasonable ways of defining, arriving at, and specifying design load conditions (operational and failure) on mechanical and structural reactor components.

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.

16

SMiRT-5 SCIENTIFIC PROGRAM

Division Β. Β 1 . Β 2. Β 3. Β 4. Β 5. Β 6. Β 7. Β 8.

Division C. C1 | . C1| | . C 2. C3|. C3||. C 4,. C4„.

Division D.

D 1 . D 2. D 3. D 4. D 5. D 6.

D 7.

Division E.

E 1. E 2. E 3. E 4. E 5. E 6.

TOPICAL GROUPING OF THE CONFERENCE SESSIONS

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

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

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

Division F.

F 1 . F 2. F 3. F 4. F 5. F 6. F 7. F 8. F 9.

Division G.

G 1. G 2. G 3. G 4. G 5. G 6. G 7. G 8. G 9. G 10

Division H.

H 1 . H 2. H 3. H 4. H 5. H 6.

H 7. H 8.

Structural Analysis of Reactor Core and Coolant Circuit Structures

Reactor Core Structures Special Problems Piping: Structural Analysis Piping: Dynamic Analysis Fracture Mechanics Pipe Rupture Pipe Rupture: Methodology Components and Support Systems Heat Exchangers

Structural Analysis of Steel Reactor Pressure Vessels

Overviews of Integrity Assessment Fracture Toughness Measurements Fracture Mechanics: "Èlasto-Plastic Fracture Mechanics: Special Aspects Fracture Mechanics: Stable Crack Growth Fracture Mechanics: Materials Modeling Fracture Mechanics: Computation Fatigue Fracture Mechanics: Thermal Effects Stress Analysis

Structural Engineering of Prestressed Reactor Pressure Vessels

Materials Behavior ι Materials Behavior II Design, Research and Surveillance of PCVs Structural Analysis of PCVs and Components Liner and Thermal Barrier Systems Concept and Research for a PCV with Hot Liner Concept and Research for a PCIV Concept and Research for a PCV for the LMFBR

18

J 2. J 3. J 4. J 5. J 6.

J 7. J 8. J 9. J 10.

Division K.

Division J. Loading Conditions and Structural Analysis of Reactor Containment

J 1. General Design Criteria and Containment Selection BWR Containment Design Concrete Containment Design and Analysis Concrete Containment: Testing Behavior Design and Analysis of Slabs and Structures Structural and Leak Testing and Design of Containment Components Impact Load Analysis and Design I Impact Load Analysis and Desiqn II Aircraft Impact Load Impulsive Load Analysis and Design

Seismic Response Analysis of Nuclear Power Plant Systems

K 1. Ground Motion K 2. Risk Analysis I K 3. Risk Analysis II K 4. Design Concepts K 5. Soil-Structure Interaction K 6. Soil-Structure Interaction II K 7. Underground Structures K 8. Response of Structures K 9. Floor Response Analysis K 10. Response of Piping and Equipment I K 11. Response of Piping and Equipment II K 12|. Reactor Core and Fluid Related Structures I K 12||. Reactor Core and Fluid Related Structures II K 13|. Dynamic Testing and Qualification I K 13ii. Dynamic Testing and Qualification II

Panel Session JK-P Status of Research in Structural and

Mechanical Engineering for Nuclear Power Plants

Division L. Materials Modeling and Inelastic Analysis of Metal Structures

L 1. Advanced Theories I L 2. Advanced Theories II L 3. Methods I L4. Methods II L 5. Fracture, Rupture L 6. Codes and Criteria L 7. Materials Behavior L 8. Applications I L 9. Applications II L 10. Simplified Methods L11. Damage L 12. Experiments I L 13. Experiments II

Division M. Methods for Structural Analysis M 1. Integrated Methods of Structural Analysis M 2. Numerical Implementation of Inelastic Material

Models M 3. Design and Simplified Methods of Analysis M 4. Computational Techniques for Plate and Shell

Analysis I M 5. Computational Techniques for Plate and Shell

Analysis II M 6. Computational Techniques within Finite Element

Analysis I M 7. Computational Techniques within Finite Element

Analysis II M 8. Probabilistic Methods in Structural Analysis M 9. Numerical Procedures for Fracture Mechanics M 10. Dynamic Modeling in Seismic Analysis M 11. Advances in Linear Boundary and Initial Value

Problems

Division N. Thermal, Materials Engineering, and Structural Mechanics Problems of Future Fusion Reactor Power Plants

N. Part I.Engineering Concepts and Thermo-Fluid-

Dynamics of Future Fusion Reactor Power Plants N 1.1 Engineering Concepts of Magnetic Confinement

Fusion Reactor Systems N 1.2 Engineering Concepts of Inertial Confinement and

Hybrid Fusion Reactor Systems and Safety Considerations

N 1.3 Thermal-Fluid Dynamics of Fusion Power Reactor Systems

N. Part2.Structural Mechanics Problems of Fusion Power

Reactors N 2.1 Structural Analysis of Magnets N 2.2 Magnet Technology N 2.3 First Wall Performance in Fusion Reactors N 2.4 Fusion Blanket Structural Analysis N 2.5 Materials and Plasma-Fluid Wall Interaction

20

TABLE OF CONTENTS

Division Β. THERMAL AND FLUID/STRUCTURE DYNAMICS ANALYSIS

Session Β 1. Computational Methods I

Β 1/1* Evaluation of Lagrangian, Eulerian, Arbitrary Lagrangian-Eulerian Methods for Fluid-Structure Interaction Problems in HCDA Analy­sis Y.W. Chang, H.Y. Chu, J. Gvildys, C.Y. Wang, Argonne National La­

boratory, Argonne, Illinois, U.S.A. Β 1/2 Arbitrary Lagrangian-Eulerian Finite-Element Descriptions with

Particular Reference to Incompressible Viscous Flows T.J.R. Hughes, W.K. Liu, T.K. Zimmermann, California Institute of

Technology, Pasadena, California, U.SA. Β 1/3 An Arbitrary Lagrangian Eulerian Finite Element Procedure for

Transient Dynamic Fluid-Structure Interaction Problems J. Donea, P. Fasoli-Stella, S. Giuliani, J.P. Halleux, A.V. Jones,

Commission of the European Communities, J.R.C. Ispra Esta­blishment, Ispra, Italy

Β 1/4 Quasi-Eulerian Finite Element Formulation for Fluid-Structure T.B. Belytschko, Northwestern University, Evanston, Illinois J.M. Kennedy, Argonne National Laboratory, Argonne, Illinois D.F. Schoeberle, University of Illinois at Chicago Circle, Chicago,

Illinois, U.SA.

Β 1 /5 Coupled Fluid-Structure Method for Pressure Suppression Anal­ysis W.H. McMaster, D.M. Norris, Jr., G.L. Goudreau, Lawrence Liver­

more Laboratory, Livermore, California, U.S.A. Β 1/6 Dynamic Fluid-Structure Analysis of Shells Using the PISCES 2

DELK Computer Code M.S. Cowler, S.L. Hancock, Physics International Company, San

Leandro, Califcrnia, U.S.A. Β 1/7 Calculation of Fluid-Structure Interaction for Reactor Safety with

the Cassiopee Code J.L. Graveleau, C.E.A./DRNR-SEDC, St. Paul-lez-Durance, P. Louvet, CISI, St. Paul-lez-Durance, France

Β 1/8 An Eulerian Formulation of Fluid-Structure Interaction in Reactor Containment System C.Y. Wang, Argonne National Laboratory, Argonne, Illinois,

USA.

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.

21

Session Β 2. Computational Methods II

Β 2/1 * A Three­Dimensional Finite­Element Formulation for Fluid­Struc­ture Interaction R.F. Kulak, Argonne National Laboratory, Argonne, Illinois, U.S.A.

Β 2/3 Thermo­Mechanical Analysis of Depressurization A. Huber, H. Hofmann, SDK Ingenieurunternehmen GmbH, Lör­

rach, Fed. Rep. Germany

Β 2/4 Formation of LOCA Jets and Induced Flows During Water Clearing CK Chu, TT. Lee, Burns St Roe, Inc., Woodbury, Ν. Y., H.C. Lui, Columbia University, New York, N.Y., U.S.A.

Β 2/5 Calculation of the Loads Induced by Pressure Wave­Flow in Branched Piping in Interaction to Valve Closing Behavior M. Fautz, Kraftwerk Union AG, Offenbach, Fed. Rep. Germany

Β 2/6 Reflection and Transmission of Fluid Transients at an Elbow R.A. Valentin, Argonne National Laboratory, Argonne, Illinois, J.W. Phillips, J.S. Walker, University of Illinois at Urbana­Cham­

paign. Urbana, Illinois, USA.

Β 2/8 PLEXUS: A General Computer Code for Explicit Lagrangian Com­putation C. Chavant, CISI, Gif­sur­Yvette, A. Hoffmann, P. Verpeaux, CEA/CEN­DEMT, Saclay, Gif­sur­

Yvette, J. Dubois, Engineering Systems International S.A., Rungis­Silic,

France

Session Β 3. Computational Methods III

Β 3/1 * Finite Element Solution to Transient Convective­Conductive Heat Transfer Problems J. Donea, S. Giuliani, Commission of the European Communities,

J.R.C., Ispra Establishment, Ispra, L. Quartapelle, Politecnico di Milano, Milano, Italy

Β 3/2 Thermal Analysis of the Penetrations of a LMFBR

S. Goldstein, J. Joly, CEA/CEN­DEMT, Saclay, Gif­sur­Yvette, M. Vidard, C.EA.­C.E.N. Cadarache, St.­Paul­lez­Durance,

France

Β 3/2a Thermal Analysis of Guarded Penetration Assemblies in a Reactor Containment and Cooling Coil Requirements D.T. Ramani, A. Dimopoulos, Y.A. Patel, R.D. Raheja, Sargent and

Lundy Engineers, Chicago, Illinois, U.S.A.

Β 3/3 Numerical Analysis of Heat Transfer in a Fluid/Solid Coupled System C. Taylor, University College of Swansea, Swansea, U.K.,

Β 3/4 Spectral Decomposition in Nonlinear Transient Heat Transfer Ana­lysis M.A. Hogge, Université de Liège, Liège, Belgium

22

Β 3/5 A General Formulation of the Isotherm Migration Method for Reac­tor Accident Analysis B.D. Turland, U.K.A.E.A., Culham Laboratory, Abingdon, Oxon,

U.K.

Β 3/7 Effectiveness of Simple Computational Schemes for Transient Temperature Distributions in Structural Components K.­R. Leimbach, Consultant, Bochum­Linden, V.H. Engelke, Kraftwerk Union AG, Offenbach, Fed. Rep. Germany

Β 3/8 A Finite Element Model for Fluid­Structure Interaction Studies A.N. Nahavandi, Columbia University, New York, N.Y., U.S.A.

Β 3/9 Difference Analysis for Fluid­Structure Interaction E. Giencke, M. Forkel, Technische Universität Berlin, Berlin, Ger­

many

Β 3/10 Theoretical and Experimental Study of the Unsteady Flow Through Perforated Structures J.J. Smolderen, G. Liebecq, W. Kollmann, Von Karman Institute for

Fluid Dynamics, Rhode­St­Genèse, Belgium, H. Holtbecker, Commission of the European Communities, J.R.C.

Ispra Establishment, Ispra, Italy

Session Β 4. Acoustic Methods

Β 4/1 * Description of a General Method to Compute the Fluid­Structure Interaction F. Jeanpierre, R.J. Gibert, A. Hoffmann, M. Livolant. CEA/CEAV­

DEMT, Saclay, Gif­sur­Yvette, France

Β 4/2 Finite Element Analysis of Fluid­Structure Interaction Problems B. Osterie, W.Ch. Muller, Gesellschaft für Reaktorsicherheit, Gar­

ching, Fed. Rep. Germany

Β 4/3 Analyses of the Dynamic Behavior of Nuclear Power Reactor Com­ponents Containing Fluid

F. Descleve, NOVATOME Industries, Le Plessis Robinson, J. Dubois, Engineering System International, Rungis­Silic, France

Β 4/4 Development and Verification of Fluid Finite Elements for the Eva­luation of Structure Fluid Interaction Effects A.N. Gantayat, Engineering Decision Analysis Company, Palo Alto,

California, U.S.A.

Β 4/5 Fluid Element in SAP IV

C. Yilmaz, N. Akkas, Middle East Technical University, Ankara, Tur­key

Β 4/6 Application of ANSYS Fluid Elements in Fluid­Structural Inter­action Problems J.W. Leonard, Illinois Institute of Technology, Chicago, Illinois, H.U. Ahmed, Argonne National Laboratory, Argonne, Illinois, J.A. Swanson, Swanson Analysis Systems Corporation, Houston,

Pennsylvania, U.S.A.

23

Β 4/8 Vibration of Liquid­Filled Thin Shells

A. Kalnins, Lehigh University, Bethlehem, Pennsylvania, U.S.A.

Β 4/9 A New Method for Analyzing Fluid­Structure Interaction Using MSC/NASTRAN R.H. MacNeal, The MacNeal­Schwendler Corporation, Los Ange­

les, California, R. Citerley, ANAMET Laboratories, San Carlos, California, M. Chargin, NASA Ames Research Center, Moffett Field, California,

U.S.A.

Session Β 5. Flow Induced Vibrations

Β 5/1 A Comprehensive Analytical Approach to the Free and Forced Vi­bration Analysis of Large Steam Generator U­Tubes D.J. Gorman, University of Ottawa, Ottawa, Canada

Β 5/2 Three­Dimensional Calculation of the Coupled Vibrations of a Group of Circular Tubes in an Unconfined Liquid H. Weppelink, D.H. van Campen, Twente University of Technolo­

gy, Enschede, P.J.M. van der Hoogt, Koninklijke Machinefabriek Stork B.V.,

Hengelo (O), The Netherlands

Β 5/3 Dynamics of Fuel­Element Bundles in Axial Flow MP. Paidoussis, McGill University, Montreal, Quebec, Canada

Β 5/4 Fluid­Structure Interaction of Submerged Structures H.T.Tang, Electric Power Research Institute, Palo Alto, California, E.B. Becker, L.M. Taylor, University of Texas at Austin, Austin, Te­

xas, U.S.A.

Β 5/5 Calculation and Tests on Fluid­Elastic Interaction between a Cylin­drical Shell and a Liquid Sheet with Parallel Flow F. Axisa, R.J. Gibert, CEA/CEN­DEMT, Saclay, Gif­sur­Yvette,

France withdrawn

Β 5/6 Flow­Induced Vibration and Instability of an Elastic Pipe Structure E.C. Ting, J.L. Känning, Purdue University, West­Lafayette, In­

diana, U.S.A.

B 5/7 Vibration Study of a Tube Bank in Liquid Cross Flow

F.N. Remy, Electricité de France, Direction des Etudes et Recher­ches, Chatou, France

B 5/9 A Theoretical Analysis of Two­Phase Flow/Fuel Pin Structural Dynamical Interactions F. Hara, Tokyo University of Science, Tokyo, Japan

B 5/10 Effective Mass and Damping of Submerged Structures R.G. Dong, Lawrence Livermore Laboratory, Livermore, California,

USA.

24

Β 5/11 Experimental Investigation of Pressure Field Characteristics Ar­ound Rods and Pipes in Parallel Flow R. Jiyavan, B. Sahay, K.S. Ram, Indian Institute of Technology,

Kanpur, India

Β 5/13 An Experimental Vibration Study of In­Air and Fluid Coupled Co­Axial Cylinders

M. Chu, J.F. Lestingi, University of Akron, Akron, Ohio, S.J. Brown, Babcock & Wilcox Co., Nuclear Equipment Division,

Barberton, Ohio, U.S.A.

Session Β 6. PWR Problems

Β 6/1* Fluid­Structure Interactions in PWR Vessels during Blowdown ­Code Development at Karlsruhe and Results U. Schumann, G. Enderle, F. Katz, Α. Ludwig, H. Mösinger, E.G.

Schlechtendahl, Kernforschungszentrum Karlsruhe, Karlsruhe, Fed. Rep. Germany

Β 6/2 Hydroelastic Effects of a Loss of Coolant in a Pressurized Water Reactor J.K. Dienes, C.W. Hirt, W.C. Rivard, L.R. Stein, M.D. Torrey, Los Ala­

mos Scientific Laboratory, Los Alamos, New Mexico, U.S.A.

Β 6/3 MEL Finite Element Analysis of Water­Shell Interactions in the Context of a PWR­LOCA S. Verbiese, Brussels University, Brussels, Belgium, G. van Goethem, Commission of the European Communities,

J.R.C. Ispra Establishment, Ispra, Italy

Β 6/4 Analysis of the RS16B Experiment on Fluid­Structure Interactions During PWR Blowdown

U. Schumann, Kernforschungszentrum Karlsruhe, Karlsruhe, Fed. Rep. Germany

Β 6/5 Dynamic Behavior of a PWR­Core Barrel. Analytical Integration of the Cylindrical Shell Equations

A. Ludwig, R. Krieg, Kernforschungszentrum Karlsruhe, Karlsruhe, Fed. Rep. Germany

Β 6/6 Coupled Fluid­Structure Analysis of the Core Barrel Behaviour Dur­ing Blowdown F. Katz, E.G. Schlechtendahl, Kernforschungszentrum Karlsruhe,

Karlsruhe, Fed. Rep. Germany Β 6/7 Calculations on the H DR Core Barrel Response During Snap­

back Tests

A. Ludwig, U. Schumann, Kernforschungszentrum Karlsruhe, Karlsruhe, Fed. Rep. Germany

25

Session Β 7. BWR Problems I

Β 7/1* Pressure Distribution due to Steam Bubble Collapse in a BWR Suppression Chamber

E. Giencke, Technische Universität Berlin, Berlin, Germany

Β 7/2 Hydroelastic Phenomena in Boiling Water Reactor Suppression

Pools B.D. Nichols, C.W. Hirt, Los Alamos Scientific Laboratory, Los Ala­

mos, New Mexico, U.S.A.

Β 7/3 Fluid Structure Interaction in the Pool of Pressure Suppression Systems Containing Oscillating Bubbles P. Antony­Spies, Kraftwerk Union AG, Offenbach, Fed. Rep. Ger­

many Β 7/4 Suppression Pool Transients in BWRs Under LOCA and SRV Con­

ditions CK Chu, J.M. Ray mont. Burns & Roe, Inc., Woodbury, New

York, USA.

26

Session Β 8. BWR Problems li

Β 8/1 * Analytical and Experimental Mark I Boiling Water Reactor Containment Safety Research at the Lawrence Livermore Labo­ratory E.W. McCauley, Lawrence Livermore Laboratory, Livermore, Cali­

fornia, USA.

Β 8/2* Description of Internal Flow Problems by a Boundary Integral Me­thod with Dipole Panels R. Krieg, G. Hailfinger, Kernforschungszentrum Karlsruhe, Karls­

ruhe, Fed. Rep. Germany

Β 8/3 Unconventional Dynamic Behaviour of Thin Spherical Contain­ment Shells. A Semi­analytical Description B. Gol 1er, Kernforschungszentrum Karlsruhe, Karlsruhe, Fed. Rep.

Germany

Β 8/4 Coupled Fluid Structural Analysis for a Spherical BWR Contain­ment with Pressure Suppression System R. Krieg, Β. Göller, G. Hailfinger, Kernforschungszentrum Karls­

ruhe, Karlsruhe, Fed. Rep. Germany

Β 8/5 Coupled Vibrations of a Structure and Fluid Excited by Pressure Shocks J. Arros, Technical Research Centre of Finland, Helsinki, Finland

Β 8/6 Structural Analysis Study of Fluid­Structure Interaction Effects in BWR Mark II Reinforced Concrete Containment M. Michail, G. Shah, Bechtel Power Corporation, San Francisco,

California, U.S.A. withdrawn

Β 8/7 Practical Application of Current Fluid/Structure Interaction Technology to the Design and Analysis to BWR Containment Vessels

N.W. Edwards, NUTECH, Inc., San Jose, California, U.S.A. Β 8/8 Applicability of Flat Plate Methods in Determining Fluid/Struc­

ture Interaction Effects in BWR Pressure Suppression Sys­tems G.S. Holman, E.W. McCauley, S.C.H. Lu, Lawrence Livermore La­

boratory, Livermore, California, U.S.A.

27

TABLE OF CONTENTS

Division C. ANALYSIS OF REACTOR FUEL AND CLADDING MATERIALS

Session C 1,. Fuel and Fission Product Behavior I

C 1 /1 * Behaviour of Fission Products in PWR Primary Coolant and Defec­ted Fuel Rods Evaluation P. Bourgeois, J.P. Stora, Electricité de France, Tour EDF-GDF, Pa­

ris, France C 1/2 A Model for the Dynamic Intragranular Fission Gas Swelling and

Release J.M.Griesmeyer.N.M.Ghoniem.D.Okrent, University of California,

Los Angeles, California, U.S.A. C 1/3 Prediction of Fission Gas Release from High Burnup Oxide Fuel

I.J. Hastings, M.J.F. Notley, Atomic Energy of Canada Ltd., Chalk River Nuclear Laboratories, Chalk River, Ontario, Canada

C 1/4 Intragranular Fission Gas Behavior During a Slow Thermal Tran­sient W. Steele, D. Okrent, A.R. Wazzan, University of California, Los

Angeles, California, C 1/5 Three-Dimensional Unsteady Thermal Stresses in a Finite Circular

Cylinder N. Noda, Shizuoka University, Hamamatsu Y. Takeuti, University of Osaka Prefecture, Sakai, Osaka, Japan

Session C 1„. Fuel and Fission Product Behavior II

C 1/6 The Mechanistic Prediction of Fission-Gas Behavior During In­celi Transient Heating Tests on LWR Fuel Using the Grass-SST and Fastgrass Computer Codes J. Rest, S.M. Gehl, Argonne National Laboratory, Argonne, Illinois,

U.S.A. C Ml Unsteady Thermal Stresses in an Orthotropic Composite Disk Due

to Asymmetrical Heating Y. Takeuti, Y. Tanigawa, University of Osaka Prefecture, Sakai,

Osaka, Japan C 1 /8 Modelling of Transient Pre-Failure Fuel Relocation for LMFBR Ac­

cident Analysis B. Kuczera, Kernforschungszentrum Karlsruhe, Karlsruhe, Fed.

Rep. Germany M. Billaux, Belgonucléaire, Brussels, Belgium

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 oaper

was not available at the time of finishing of the book. — A pc per number missing in the numeral order means that the paper was cancelled or withdrawn.

28

C 1/9 UO5 Pore Migration and Grain Growth Kinetics C.S^ Olsen, EG.&G. Idaho, Inc., Idaho Falls, Idaho, U.S.A.

C 1/10 Prediction of Thermal, Mechanical, and Fission Gas Behavior of Carbide Fuel Element During Fast Thermal Transients Using the UNCLE-TUBE Code Y.D. Ting, A.R. Wazzan, D. Okrent, University of California, Los An­

geles, California, U.S.A. C 1/11 Behaviour of Fast Fuel Bundles under Irradiation

G. Marbach, P. Millet, J. Robert, A. Languille, CEA/CEN-Cadara-che, Saint-Paul-lez-Durance, France

Session C 2. Graphite Fuels Analysis

C 2/1* Experimental Verification of Stress Model Calculations for HTR Fuel Particles M. Herren, P. Krautwasser, Kernforschungsanlage Jülich, Jülich, A.-W. Mehner, HOBEG mbH, Hanau, Fed. Rep. Germany

C 2/2 Statistical Methods for Predicting Failure Probability of Coated Particles H.-L. Gehr, INTERATOM, Bergisch Gladbach, K. Bongartz, Kernforschungsanlage Jülich, Jülich, Fed. Rep. Ger­

many C 2/3 Stress Performance Calculations as a Guide for Layout and

Testing of Coated Fuel Particles for HTRs K. Bongartz, Kernforschungsanlage Jülich, Jülich, Fed. Rep. Ger­

many C 2/4 Residual Stress, Strain, and Strength Measurements in Peach Bot­

tom Fuel Test Elements CF. Wallroth, C.M. Miller, J.J. Saurwein, General Atomic Company,

San Diego, California, U.S.A. C 2/5 Irradiation Experiment with a Large Graphite Block

H. Cords, M. O'Connor, G. Kleist, Kernforschungsanlage Jülich, Jülich, Fed. Rep. Germany

P. Zeisser, Commission of the European Communities, Research Center Petten, Petten, The Netherlands

C 2/6 A 3-D Inelastic Analysis of HTR Graphite Structures and a Compari­son with a 2-D Approach J. Willaschek, INJERATOM, Bergisch Gladbach, Fed. Rep. Ger­

many

Session C 3,. Cladding Materials Behavior I

C 3/3 A Phenomenological Thermal and Irradiation Creep Model for Zir-caloy G. Senski, A. Kunick, Kraftwerk Union AG, Erlangen, Fed. Rep. Ger­

many

29

C 3/5 First Results of Cladding Tube Creep Experiments in FRG­2 M. Gartner, G. Kaspar, G. Senski, Kraftwerk Union AG, Erlangen, Α. Reymann, Η. Wilhelm, Gesellschaft für Kernenergieverwertung

in Schiffbau und Schiffahrt, Geesthacht­Tesperhude, Fed. Rep. Germany

C 3/6 Prediction of Creep Transients in Zircaloy Fuel Cladding Using Anelastic Strain Model

K.L. Murty, K.K. Yoon, Babcock & Wilcox Company, Lynchburg, Virginia, U.S.A.

Session C 3„. Cladding Materials Behavior II

C 3/8 Analysis of Reactor Fuel: Failure Criteria J.H. Gittus, UKAEA, Springfields Nuclear Power Development

Laboratories, Springfields, Sa/wick, Preston, UK.

C 3/9 A Relationship Between Swelling and the Shear Modulus of Irra­diated Metal J.F. Bates, Hanford Engineering Development Laboratory, Rich­

land, Washington, U.S.A.

C 3/10 CDA­A Computer Code for Analysis of BWR Fuel Channel Deflec­tion S.S. Sawhney, S. Basu, A.K. Anand, S.K. Mehta, Bhabha Atomic

Research Centre, Trombay, Bombay, India

C 3/11 COMTA­A Computer Code for Fuel Mechanical and Thermal Ana­lysis S. Basu, S.S. Sawhney, A.K. Anand, K. Anantharaman, S.K. Mehta,

Bhabha Atomic Research Centre, Trombay, Bombay, India

C 3/12 On Slow Crack Growth in Fuel Cladding by Finite Element Analysis T.R. Hsu, Y.J. Kim, University of Manitoba, Winnipeg, Manitoba,

Canada

C 3/13 Tensile Properties of Zircaloy­4 and 304 Stainless Steel at Constant True Strain­Rates OS. Hartley, D.A. Jenkins, J.J. Lee, University of Florida, Gaines­

ville, Florida, U.S.A.

Session C 4,. Failure Criteria I

C 4/2 Plastic Instability of Zircaloy Cladding Submitted to LOCA Condi­tions A. Leridon, O Pauwels, CEA­CEN Cadarache, Saint­Paul­lez­Dur­

ance, France

C 4/3 A Cumulative Damage Fraction Design Approach for LMFBR Me­tallic Fuel Elements D.L. Johnson, Argonne National Laboratory, Argonne, Illinois R.E. Einziger, G.D. Hudman, Argonne National Laboratory, Idaho

Falls, Idaho, U.S.A.

30

C 4/4 The Stress for the Formation of a Cladding Crack During a Power Ramp E. Smith, Joint Manchester University/UMIST Metallurgy Depart­

ment, Manchester, U.K. C 4/5 PCI Optimized Reactor Operation by Application of the Fuel

Failure Code POSHO E. Rolstad, Scandpower, Halden, Norway

C 4/7 Failure Criteria for the Probabilistic Fuel Performance Code FRP lb. Misfeldt, Risø National Laboratory, Roskilde, Denmark

C 4/8 Crack Propagation in a Fuel Cladding with a Local Bulging Caused by Internal Pressure A.F. Emery, A.S. Kobayashi, W.J. Love, V.J. Luthra, University of

Washington, Seattle, Washington, U.S.A.

Session C 4„. Failure Criteria II

C 4/11 The Effects of Defects on the Failure of Tubes M.C. Coleman, J.A. Williams, CEGB, Marchwood Engineering La­

boratories, Marchwood, Southampton, U.K. withdrawn C 4/12 Modelling the Thermal Mechanical Behaviour of a Fuel Pin due to

Oxidation Effects J.J.M. Too, Atomic Energy of Canada Ltd., Whiteshell Nuclear Re­

search Establishment, Pinawa, Manitoba, Canada

31

TABLE OF CONTENTS

Division D. STRUCTURAL ANALYSIS OF REACTOR FUEL ELEMENTS AND ASSEMBLIES

Session D 1. Fuel Performance Analysis

D 1 /1 * Interaction between Thermal and Structural Behavior in FBR Fuel Pins B.L. Harbourne, M.R. Patel, J.D. Stephen, General Electric Co.,

Advanced Reactor Systems Department, Sunnyvale, California, USA.

D 1/2 The BACO Fuel Rod Analysis Computer Program S. Harriague, G. Coroli, E.J. Savino, Comisión Nacional de Energia

Atòmica, Buenos Aires, Argentina D 1/4 The FROST Code for Predicting In-Reactor Behaviours of LWR

Fuel Rod H. Nuno, Y. Irisa, M. Mizuta, Mitsubishi Atomic Power Industries,

Inc., Omiya, Saitama, Japan D 1/5 WAFER-3. An Extended Version for High-speed Analysis of Rods

with an Axial Power Profile N. Kjaer-Pedersen, Risø National Laboratory, Roskilde, Denmark

D 1/7 Heat Transfer Analysis of an Eccentric Fuel/Sheath Geometry Using the Finite Element Method G.L. Rigby, M.H. Schankula, Atomic Energy of Canada Limited,

Whiteshell Nuclear Research Establishment, Pinawa, Manitoba, Canada

D 1/8 Fuel Pins In-Pile Reliability and End-of-Life Failure Probability Estimate J. Truffert, CEA/CEN-Cadarache, Saint-Paul-lez-Durance, France

D 1/9 VERDON - Fuel Pin Mechanical and Thermal Behaviour Code C. Courtois, J. Truffert, CEA/CEN-Cadarache, Saint-Paul-lez-Dur­

ance, France

Session D 2. Pellet-Clad Interaction Effects on Clad Behavior

D 2/1 Influence of Pellet-Clad-Gap-Size on LWR Fuel Rod Performance B. Brzoska, H.P. Fuchs, F. Garzarolli, R. Manzel, Kraftwerk Union

AG, Erlangen, Fed. Rep. Germany D 2/2 Post Irradiation Examination and Analysis of 13 (U, Pu)C-Fuel Pins

Irradiated in the Thermal Flux of FR 2 P. Weimar, H. Steiner, Kernforschungszentrum Karlsruhe, Karls­

ruhe, 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 lhe time of finishing of the book. — A paper number missing in the numeral order means that the paper was cancelled or withdrawn.

32

D 2/3 Pellet-Cladding Mechanical Operating Failure Limits and Inferred Strain Thresholds C L Mohr, P.J. Pankaskie, CM. Heeb, Batteile Pacific Northwest

Laboratories, Richland, Washington, USA. withdrawn D 2/4 Sensitivity of Power Ramp Induced Cladding Stress and Strain

Concentrations to Modelling Assumptions W. Hering, Kraftwerk Union AG, Erlangen, Fed. Rep. Germany, IB. Fiero, RS. Darling, Combustion Engineering Inc., Windsor,

Connecticut, U.S.A. D 2/5 Analysis of Mechanical and Chemical Pellet-Clad Interaction Dur­

ing Power Ramps W. Vogl, W. Hering, M. Peehs, Kraftwerk Union AG, Erlangen, Fed.

Rep. Germany, J. LaVake, Combustion Engineering Inc., Windsor, Connecticut,

U.S.A. D 2/6 The Fuel-Cladding Interfacial Friction Coefficient in Water-

Cooled Reactor Fuel Rods E. Smith, Joint Manchester University/UMIST Metallurgy Depart­

ment, Manchester, U.K. D 2/7 Transient Pellet-Cladding Interaction of LWR Fuel Rod

B.M. Ma, Iowa State University, Department of Nuclear Engineer­ing, Ames, Iowa, U.S.A.

D2/8 Stress Distributions in Fuel Element Cladding During Pellet-Clad Interaction R.S. Darling, I.B. Fiero, M.E. Scott, Combustion Engineering, Inc.,

Windsor, Connecticut, U.S.A.

Session D 3. Methods for Analysis for Pellet-Clad Interaction

D 3/1 * The Structure of Fuel Element Codes K. Lassmann, Kernforschungszentrum Karlsruhe, Karlsruhe, Fed.

Rep. Germany D 3/2 Theoretical and Experimental Analyses of Cladding Strain Produ­

ced by Expansion of Cracked Fuel Pellets M. Nakatsuka, Toshiba Research and Development Center, Ka­

wasaki-City, Kanagawa, T. Sakuyama, Nuclear Engineering Department, Toshiba Corpora­

tion, Tokyo, Japan D 3/3 Stresses and Strains at Zircaloy Cladding Ridges

G.V. Ranjan, G.N. Brooks, Failure Analysis Associates, Palo Alto, California,

A.K. Miller, Stanford University, Stanford, California, U.S.A. D 3/4 Finite Element Pellet-Clad Interaction Model

A. Alujevic, P. Skerget, Institut Jozef Stefan, University of Ljublja­na,

B. Cernej, University of Maribor, Maribor, Yugoslavia

33

D 3/5 A Formulation for the Analysis of Pellet-Cladding Mechanical In­teraction Y.Y. Liu, Argonne National Laboratory, Argonne, Illinois, J.E. Meyer, A.S. Argon, Massachusetts Institute of Technology,

Cambridge, Massachusetts, U.S.A. D 3/6 A Model for the Description of the Fuel-Cladding Mechanical Inter­

action in Fast Breeder Reactor Fuel Pins I. Müller-Lyda, Kernforschungszentrum Karlsruhe, Karlsruhe, Fed.

Rep. Germany D 3/7 Effect of Material Properties on Pellet-Clad Interaction Pressure

S. Bir Singh, S.B. Bhoje, S.R. Paranjpe, Reactor Research Centre, Kalpakkam, India

D 3/8 Fracture Mechanics Method of Evaluating Failures in Pellet-Cladding Interaction Analysis D.T. Ramani, Sargent & Lundy Engineers, Inc., Chicago, Illinois,

U.S.A.

Session D 4. Thermal Reactor Subassembly Analysis

D 4/1 A Model for Creep and Relaxation Consideration in a Fuel Rod As­sembly H.T.Tang, Electric Power Research Institute, Palo Alto, Calif. U.S.A.

D 4/3 Nonlinear Asymmetric Load Deflection Characteristics of a Reac­tor Fuel Bundle H.D. Fisher, Combustion Engineering, Inc., Windsor, Connecticut,

U.S. A. D 4/4 Effects of Gap Sizes on Stresses and Deflections of a Fuel Element

T.S. Wu, Argonne National Laboratory, Argonne, Illinois, U.S.A. D 4/5 A Model for Fuel Rod and Tie Rod Elongations in Boiling Water Re­

actor Fuel Bundles K.R. Merckx, Exxon Nuclear Company, Inc., Richland, Washington,

U.S.A. D 4/6 Fuel Bundle End Plate Analysis by Code SPACE

A.G. Chhatre, M. Das, S.A. Bhardwaj, R.S. Rustagi, Department of Atomic Energy, Power Projects Engineering Division, Colaba, Bombay, India

D 4/7 Analysis of Colliding Vibration of Two Cylinders A.K. Ghosh, R.K. Grover, A. Kakodkar, Bhabha Atomic Research

Centre, Trombay, Bombay, India D 4/8 An Assessment of Loading Effects on Magnox Fuel Elements in

Transport Accidents H.J. Dowler, J.P. Whitehead, CEGB Berkeley Nuclear Laboratories,

Berkeley, Gloucestershire, U.K. withdrawn

34

Session D 5. Fast Reactor Subassembly Analysis

D 5/1* Structural Evaluation of Fast Reactor Core Restraint with Irra­diation Creep-Swelling Opposition Effects J.E. Kalinowski, Westinghouse Advanced Reactors Division, Madi­

son, Pennsylvania, D.V. Swenson, Sandia Laboratories, Albuquerque, New Mexico,

USA. D 5/2 Rules for Structural Design of LMFBR Core Subassemblies

H. Meyer zur Capeilen, H. Többe, INTERATOM, Bergisch Gladbach, Fed. Rep. Germany,

B. Kazimierzak, Belgonuc/éaire, Bruxelles, Belgium D 5/3 An Analytical Study of the Dilation of Fast Reactor Fuel Assembly

Ducts D.P. Chan, R.J. Jackson, Westinghouse Hanford Company, Rich­

land, Washington, U.S.A.

D 5/5 The Restrained Core Modelling Program CRAMP R.C. Perrin, AERE Harwell, Didcot, UK.

D 5/6 Bowing and Interaction Model for Sub-Assemblies in a Fast Reac­tor Core S. Bir Singh, S. Govindarajan, S.B. Bhoje, Reactor Research

Centre, Kalpakkam, Tami/nadu, India D 5/7 Calculation of Equilibrium Configurations of a Hexagonal Array of

Deformed Subassemblies A. Bernard, CEA/CEN-Cadarache DRNR, St.-Paul-lez-Durance,

France D 5/8 Elastic Plastic Analysis of Fuel Element Assemblies-Hexagonal

Claddings and Fuel Rods: Effects of Thermal Bowing of Fuel Rods, External Pressure of Coolant, and Elevated Tempera­tures M.M. Mamoun, Institute of Gas Technology, Chicago, Illinois, T.S. Wu, P.S. Chopra, D.C Rardin, Argonne National Laboratory,

Argonne, Illinois, USA. D 5/9 BEACON: A Three-Dimensional Structural Analysis Code for

Bowing History of Fast Breeder Reactor Cores K. Miki, Energy Research Laboratory, Hitachi Ltd., Ibaragi, Japan

D 5/10 Some Fundamental Principles of Voidage Induced Bowing of Fuel Pins in Subassemblies R.G. Anderson, U.K.A.E.A., Risley Nuclear Power Development

Establishment, Risley, Warrington, Cheshire, U.K.

Session D 6. Accident and Overpower Transient Analysis of Thermal Reactors

D 6/1 * Strain-Rate Dependent Plasticity in Thermo-Mechanical Trans­ient Analysis Y.R. Rashid, M.N. Sharabi, ANATECH International Corp., La Jolla,

California, U.S.A.

35

D 6/2 Characterization of Transient Deformation of Zircaloy Fuel Clad­ding for LOCA Conditions OL. Mohr, Battelle Pacific Northwest Laboratories, Richland, Wa­

shington, U.S.A. D 6/3 GAPCON - Thermal-3: A Technique for Evaluating Transient

Gap Conductance and Stored Energy O L Mohr, D.D. Lanning, F.E. Panisko, Battelle Pacific Northwest

Laboratories, Richland, Washington, U.S.A. D 6/4 A Simplified Method of Computing Clad and Fuel, Stress and Strain

During an Overpower Transient M.V. Frank, W.E. Kastenberg, University of California, Los Angeles,

California, U.S.A. D 6/5 Analytical Model for Transient Gas Flow in Nuclear Fuel Rods

R. Oehlberg, Electric Power Research Institute, Palo Alto.Califor-nia,

D.S. Rowe, Rowe and Associates, Bellevue, Washington, U.S.A. D 6/6 Sensitivity of Fuel Rods Material Properties to Hypothetical PWR

LOCA R. Oehlberg, Electric Power Research Institute, Palo Alto, Califor­

nia, USA.

Session D 7. Accident and Overpower Transient Analysis of Fast Reactors

D 7/1 * Bridging the Gap between Whole Core Accident and Fuel Behav­iour Codes J.R. Matthews, A.E.R.E. Harwell, Didcot, U.K.

D 7/2 Modeling of Fast Reactor Cladding Failure for Hypothetical Acci­dent Transient Analysis J.M. Kramer, R.J. DiMelfi, T.H. Hughes, L.W. Deitrich, Argonne Na­

tional Laboratory, Argonne Illinois, U.S.A. D 7/3 Fuel Deformation in a Loss-of-Flow Accident in the Gas-Cooled

Fast Breeder Reactor T.R. Wehner, D.T. Eggen, Northwestern University, Evanston, Illi­

nois, U.S.A. current address — Wehner: Energy Division. Los Alamos Scientific Laboratory, Los Alamos. N.M. 87545,

U.SA. Eggen: DSN/SES, C.E.N. Cadarache, F-I3115 St Paul-lez-Durance, France

D 7/4 Thermohydraulic and Thermal Stress Aspects of a Porous Block­age in an LMFBR Fuel Assembly T.M. Kuzay, W.W. Marr, W.H. Hellenberg, R.E. Wilson, D.R.

Pedersen, Argonne National Laboratory, Argonne, Illinois, T. Ariman, University of Notre Dame, Notre Dame, Indiana,

USA. D 7/6 Fuel Pin Response to an Overpower Transient in an LMFBR

A.J. Grosberg, J.L. Head, Imperial College of Science and Techno­logy, London, U.K.

36

TABLE OF CONTENTS

Division E. ENERGETICS AND STRUCTURAL DYNAMICS

IN FAST REACTOR ACCIDENT ANALYSIS

Session E 1. HCDA Containment

E 1/1* The Computer Code SEURBNUK­2: Recent Developments

R. Staniforth, UKAEA, AEE Winfrith, Dorchester, Dorset, U.K., A. Yerkess, Commission of the European Communities, J.R.C.

Ispra Establishment, Ispra, Italy

E 1/2* Three­Dimensional Fluid­Structure Interaction Dynamics of a Pool­Reactor In­Tank Component R.F. Kulak, Argonne National Laboratory, Argonne. Illinois. U.S.A.

E 1/3 Potential Missiles from LMFBR Vessels During an HCDA. Some Bounding Analyses CM. Romander, D.J. Cagliostro, SRI International, Menlo Park,

California, USA. E 1 /4 ALICE ­ An Arbitrary Lagrangian­Eulerian Code for Analyzing FBR

Containment Response to HCDA H.Y. Chu, Argonne National Laboratory, Argonne, Illinois. U.S.A.

E 1/5 A Comparison of Rezoning Techniques for Lagrangian LMFBR Containment Codes

M. Delaval, Commission of the European Communities, J.R.C. Ispra Establishment, Ispra, Italy

E 1 /6 Behaviour of Pressure Wavesand Fragments after Vessel Rupture Calculated with the PISCES™­2 DELK­Code H. Schürkamp, Brown, Boverie & Cie, Mannheim, W. Pohl, Control Data GmbH, Frankfurt/Main, Fed. Rep. Germany

E 1Π Experimental and Associated Theoretical Studies of the Response of Reactor Structures to Hypothetical Core Disruptive Accident Loadings K.M. Leigh, V. Washby, U.K.A.E.A., Northern Division, Risley,

Warrington, Cheshire, R. Pottinger, MOD(PE), Atomic Weapons Research Establishment,

Southend­on­Sea, Essex, U.K.

Notes: — The sign (·) designates Invited Lectures. — 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. — A paper number missing in the numeral order means that the paper was cancelled or withdrawn.

37

Session E 2. Upper Core Structures and Cover Response

E 2/1* Energetics of LMFBR Core Disruptive Accidents J.F. Marchaterre, Argonne National Laboratory, Argonne, Illinois,

U.S.A. E 2/2 Structural and Coupling Formulation for Upper Internals for

LMFBR J.M. Kennedy, C.Y.Wang, Argonne National Laboratory, Argonne,

Illinois, IB. Belytschko, Northwestern University, Evanston, Illinois, U.S.A.

E 2/3 Analysis of a Bubble Growth (HCDA) in a Fluid Inside a Primary Containment with Internals J.F. Chedmail, J.L. Gregis, J. Dubois, A. de Rouvray, Engineering

System International, Rungis-Silic, France E 2/4 Characterization of Dynamic Loads on the LMFBR Rotating Shield

E. Morris, Nuclear Installations Inspectorate, London, U.K. E 2/5 Fluid-Structure Interaction Analysis of a Deck Structure During a

HCDA R.F. Kulak, Argonne National Laboratory, Argonne, Illinois, U.S.A.

E 2/6 Validation of a Cavitation Model and its Appi ¡cation to Containment Loading Experiments A.V. Jones, Commission of the European Communities, J.R.C.

Ispra Establishment, Ispra, Italy

Session E 3. Coolant System and Materials Response

E 3/1 * Dynamic Uniaxial and Biaxial Stress-Strain Relationships for Aus-tenitic Stainless Steels C. Albertini, M. Montagnani, Commission of the European Com­

munities, J.R.C. Ispra Establishment, Ispra, Italy E 3/3 Three-Dimensional Response of Piping Systems to Internally Pro­

pagating Pressure Pulses M.T.A-Moneim, Y.W. Chang, Argonne National Laboratory, Ar­

gonne, Illinois T.B. Belytschko, Northwestern University, Evanston, Illinois, U.S.A.

E 3/4 Coupled Hydrodynamic-Structural Analysis of an Integral Flowing Sodium Test Loop in the TREAT Reactor W.R. Zeuch, M.T.A-Moneim, Argonne National Laboratory, Ar­

gonne, Illinois, U.SA. E 3/5 Thermal-Hydraulic and Structural Safety Analysis of SLSF P3 Ex­

periment W.A. Ragland, J.H. Tessier, Argonne National Laboratory,

Argonne, Illinois, T. Ariman, University of Notre Dame, Notre Dame,

Indiana, USA. E 3/7 Evaluation of DNB Induced Fatigue in Heat Transfer Tubes

S.A. Kamal, D.H. Pai, J.M. Chern, Foster Wheeler Energy Corpora­tion, Livingston, New Jersey, U.S.A.

38

Session E 4. Experiments and Code Verification I

E 4/1 * Experimental Validation of the Containment Codes ASTARTE and SEURBNUK K.C. Kendall, L. Arnold, B.J. Broadhouse, UKAEA, AEE Winfrith,

Dorchester, Dorset, U.K.. A. Benuzzi, A.V. Jones, A. Yerkess, Commission of the European

Communities, J.R.C. Ispra Establishment, Ispra, Italy E 4/2 Energetics of Simulated HCDA Bubble Expansions: Some Poten­

tial Attenuation Mechanisms R.J.Tobin, D.J. Cagliostro, D.W. Ploeger, SRI International, Menlo

Park, California, U.S.A. E 4/4 Recent Results on PEC Reactor HCDA Containment Investiga­

tions R. Cenerini, Università di Bologna, Bologna, A. Palamidessi, CNEN Dipartimento Reattori Veloci, Bologna, G. Verzelletti, Commission of the European Communities, J.R.C.

Ispra Establishment, Ispra, Italy E 4/5 The Development and Validation of Thin Shell Models in Computer

Codes for Fast Reactor Containment Analysis K.C. Kendall, UKAEA, Atomic Energy Establishment, Winfrith, Dor­

chester, Dorset, P.H.West, MOD(PE)AWREAldermaston, Reading, Berkshire, U.K.

E 4/6 Comparison Between Calculations and Tests for a Support Structure of a LMFBR Tank Under the HCDA V. Giuliano, M. Scala, AMN S.p.A., Genova, Italy

E 4/7 Experiment and Analysis on Pressure Pulse Propagation in a Pla­stically Deforming Pipe Y. Ando, S. Kondo, University of Tokyo, Tokyo, Japan

Session E 5. Experiments and Code Verification II

E 5/1 Analysis of the HCDA-Simulation of the 1/6-scaled SNR-300 Fast Breeder Reactor with the PISCES™-2DELK-Code W. Pohl, Control Data GmbH. Frankfurt/Main, Fed. Rep. Germany, M.J. v. d. Hoek, Physics International Co., Gouda, The Netherlands, M.S. Cowler, Physics International Co., San Leandro, California,

U.S.A. E 5/2 Fracture Experiments with Cracked and Embrittled Hexcan Sec­

tions H.J. Petroski, H. Yamada, Argonne National Laboratory, Argonne,

Illinois, U.S.A. E 5/3* ICECO Simulation of the COVA Experiment

C.Y. Wang, Y.W. Chang, Argonne National Laboratory, Argonne, Il­linois, U.S.A.

39

E 5/4 Structural Response of a 1 /20­Scale Model of the CRBR to a Simu­lated HCDA CM. Romander, D.J. Cagliostro, SRI International, Menlo Park,

California, USA.

E 5/5 Comparison of REXCO Code Predictions with SRI SM­2 Experi­mental Results Y.W. Chang, J. Gvildys, Argonne National Laboratory, Argonne,

Illinois, USA.

E 5/6 The Simulation of Small Scale Explosion Tests with the German Fluid­Structure Interaction Code ARES B. Baltes, W. Salz, Gesellschaft für Reaktorsicherheit, Köln, Y.S. Hoang, T. Malmberg, Kernforschungszentrum Karlsruhe,

Karlsruhe, Fed. Rep. Germany

Session E 6. Core Components Response

E 6/1* Effects of Cracks on the Response of Shell Structures H.J. Petroski, Argonne National Laboratory, Argonne, Illinois,

U.S. A.

E 6/2 Three­Dimensional Finite­Element Computations of the Trans­ient Response of Components Typical of a Reactor Structure J.E. Ash, R.F. Kulak, A.H. Marchertas, Argonne National Labora­

tory, Argonne, Illinois, U.S.A.

E 6/3* Quasi­Eulerian Formulation for Fluid­Structure Interaction J.M. Kennedy, Argonne National Laboratory, Argonne, Illinois, T.B. Belytschko, Northwestern University, Evanston, Illinois, D.F. Schoeberle, University of Illinois at Chicago Circle, Chicago,

Illinois, U.S.A.

E 6/4* Prediction of Energy Absorption Capability and Damage Distribu­tion of a Complete LMFBR Subassembly Under Pressure Pulses H. Zehlein, Kernforschungszentrum Karlsruhe, Karlsruhe, Fed.

Rep. Germany

E 6/5 The Dynamic Response of Cracked Hexagonal Subassembly Ducts J.L. Glazik, Jr., H.J. Petroski, Argonne National Laboratory, Ar­

gonne, Illinois, U.S.A.

E 6/6 Flow Splits and Bowing Performances of Fuel Pins in Wire Wrap­ped FBR Fuel Assemblies K. Itoh, S. Seino, T. Kubota, Mitsubishi Atomic Power Industries,

Inc., Omiya City, Saitama, Japan

E 6/7 Flow Induced Vibrations of LMFBR Structures

F. Axisa, R.J. Gibert, Β. Villard, CEA/CEN­Saclay DEMT, Gif­sur­Yvette, France

40

TABLE OF CONTENTS

Division F. STRUCTURAL ANALYSIS OF REACTOR CORE

AND COOLANT CIRCUIT STRUCTURES

Session F 1. Reactor Core Structures

F 1/1 Stress Relaxation Analysis for Irradiation Creep and Swelling in Pressure Tubes J.M. Beeston, T.K. Burr, EG.<SG. Idaho, Inc., Idaho Falls, Idaho,

U.S.A. F 1/2 Analysis of Pressure Tube Elongation and End Shield Interac­

tions in the CAN DU Reactors A.R. Causey, S.R. MacEwen, Atomic Energy of Canada Ltd.,

Chalk River, Ontario, H.O Jamieson, A.B. Mitchell, Ontario Hydro, Toronto, Ontario, Ca­

nada

F 1 /3 Vibration of PWR Internals Considering Their Edge Conditions and Holes V. Kuzelka, National Research Institute for Machine Design, Pra­

gue, Czecholovakia

F 1/4 Plastic Analysis of the Core Barrel Flange Deformations According to Non­Symmetric Bending Loadings U. Berkner, Kraftwerk Union AG, Erlangen, Fed. Rep. Germany

F 1/5 Stressand Displacement Analysis of a Core Plate, i. e. Grid­perfo­rated Plate Compound, Modelled as an Equivalent Beam System R. Frank, R. Engel, Kraftwerk Union AG, Erlangen, Fed. Rep. Ger­

many

F 1/6 Pump Induced Fluctuating Pressure in a Reactor Coolant Pipe L. Lee, S. Chandra, Combustion Engineering, Inc., C­Ε Power Sy­

stems, Windsor, Connecticut, U.S.A.

Session F 2. Special Problems

F 2/1 Vibration Studies on a Three Loop PWR Internals Model R. Assedo, G. Castello, FRAMATOME, Paris La Défense, A. Epstein, R.J. Gibert, CEA./CEN­Saclay DEMT, Gif­sur­

Yvette G. Baylac, Electricité de France, SEPTEN, Paris La Défense, France

F 2/2 Nuclear Reactor Surveillance ­ Neutron Noise Measurements and Vibration Analysis on French PWR Internal Structures R. Assedo, G. Hugot, FRAMATOME, Paris La Défense, A. Epstein, RJ. Gibert, CEA./CEN­Saclay DEMT, Gif­sur­Yvette,

France

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.

41

F 2/3 Application of Acoustic Emission as a Monitoring System During Hydrostatic Tests of Nuclear Reactor Components E.J. Votava, Kraftwerk Union AG, Erlangen, Fed. Rep. Germany

F 2/4 Prediction of the Vibratory Behaviour of a Multistage Gaseous Dif­fusion Plant P. Descleve, C. Bertaut, NOVATOME, Le Plessis Robinson, P. Briot, USSI, Bagneux, France

F 2/6* Stress Corrosion Cracking Experiments in Piping of Light Water Reactor Power Plants L.C Shao, Division of Reactor Safety Research, Office of Nuclear

Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, D.C., U.S.A.

F 2/8 Theoretical and Experimental Study on Induction Heating Stress Improvement (IHSI) of Nuclear Primary Piping Y. Ando, G. Yagawa, University of Tokyo, Tokyo, Y. Hayase, The Tokyo Electric Power Co., Inc., Tokyo, T. Umemoto, Ishikawajima Harima Heavy Industries Co., Ltd., Yo­

kohama, K. Enomoto, Mechanical Engineering Research Laboratory, Hitachi

Ltd, Hitachishi, S. Nakayama, Toshiba Corporation, Tokyo, T. Watanabe, Century Research Center Corporation, Tokyo, Japan

Session F 3. Piping: Structural Analysis

F 3/1 Experimental and Elastic-Plastic Numerical Analysis of a PWR Piping Elbow Subjected to Pressure Cycling J.P. Prost, J.J. Doyen, FRAMATOME, Paris la Défense, T. Foult, SOCOTEC, Département Génie Industriel et Nucléaire,

Paris, H. Jakubowicz, CEA./CEN-Saclay DEMT, Gif-sur-Yvette,

France F 3/2 In-Plane and Out-of-Plane Bending Tests on Carbon Steel Pipe

Bends D. Brouard, A. Tremblais, B. Vrillon, CEA./CEN-Saclay DEMT,

Gif-sur-Yvette, France F 3/3 Stesses in a Curved Pipe Subject to an In-plane Bending Moment

E. Hofmann, U. Heeschen, Kraftwerk Union AG, Erlangen, Fed. Rep. Germany

F 3/4 Theoretical and Experimental Analysis on Tee Piping Components F. Cesari, S. Curioni, S. McLoughlin, A. Meneghini, C.N.E.N., Dipar­

timento Reattori Veloci, Bologna, Italy F 3/5 Simplified Creep Buckling Analysis of Elbows under In-Plane

Bending A. Imazu, O-arai Engineering Center, Power Reactor and Nuclear

Fuel Development Corporation, Ibaraki, K. Nakamura, Takasago Technical Institute, Mitsubishi Heavy In­

dustries, Ltd., Takasago, Japan

42

F 3/6 An Elastoplastic Elbow Element: Theory and Applications L. Lazzeri, AMN S.p.A., Genova, Italy

F 3/1 Detailed Analyses of Three Elbow-Pipe Assemblies for Typical Load Cases T. Kano, K. Iwata, Y. Wada, Power Reactor and Nuclear Fuel Devel­

opment Corporation, Tokyo, H. Takeda, S. Asai, S. Uesugi, Century Research Center Corpora­

tion, Tokyo, Japan F 3/8 Stress Distribution and Flexibility of the Suction Bend of the Pri­

mary Sodium/Pump LMFBR - SNR 300 H.K. Kwee, Stork Boilers, Hengelo, The Netherlands

Session F 4. Piping: Dynamic Analysis

F 4/1 * Structural Behaviour of Piping Systems under Accident Conditions L. Issler, Staatliche Materialprüfungsanstalt (MPA), Universität

Stuttgart, Stuttgart, G. Katzenmeier, Kernforschungszentrum Karlsruhe, Karlsruhe,

Fed. Rep. Germany F 4/2 Acoustic Pressure Pulsations in Pressurized Water Reactors

MM. Cepkauskas, Combustion Engineering, Inc., Windsor, Con­necticut, U.S.A.

F 4/3 Vibrationof Three-Dimensional Piping Subject to Pump Pulsation R. Keskinen, Institute of Radition Protection, Helsinki, Finland

F 4/4 Study and Measurement of Impact Damping in PWR Reactor Coo­lant System Seismic and Accident Restraints J.C Hennart, Westinghouse Nuclear Europe, Bruxelles, Belgium

F 4/5 Nonlinear Dynamic Analysis of Piping Systems Using the Pseudo Force Method S. Prachuktam, P. Bezler, Brookhaven National Laboratory, Upton,

New York, M. Hartzman, U.S. Nuclear Regulatory Commission, Bethesda,

Maryland, USA. F 4/6 Real-Time Numerical Evaluation of Dynamic Tests with Sudden

Closing of Valves in Piping Systems K.-R. Leimbach, Consultant, Bochum-Linden, W. Geidel, Kraftwerk Union AG, Offenbach, Fed. Rep. Germany

Session F 5. Fracture Mechanics

F 5/1* Opening and Extension of Circumferential Cracks in a Pipe Subject to Dynamic Loads D.J. Ayres, T.J. Griesbach, Combustion Engineering Inc., Windsor,

Connecticut, U.S.A. F 5/2 Elastic-Plastic Response of PWR Coolant Pipes Containing Postu­

lated Circumferential Flaws S.S. Palusamy, J.N. Chirigos, T.E. Campbell, Westinghouse Elect­

ric Corporation, PWR Systems Division, Pittsburgh, Pennsylvan­ia, USA.

43

F 5/3 Numerical Study of Dynamic Crack Growth Including Fluid Inter­action

D.R.J. Owen, E. Hinton, E.S. Caidis, C. Taylor, University of Wales, Swansea, U.K.

F 5/4 Problems Identified in Quantifying Leak before Break in Pressure Containing Structures

B.J.L. Darlaston, D.C. Connors, R.A.J. Hellen, CEGB Berkeley Nu­clear Laboratories, Berkeley, Gloucestershire, U.K.

F 5/5 The Failure of Ductile Plates Containing Thin Ligaments I.W. Goodall, J.E. Griffiths, CEGB Berkeley Nuclear Labaratories,

Berkeley, Goucestershiere, U.K.

F 5/6 On the Behavior of Reinforced Mitre Bends Containing Defects B.J.L. Darlaston, D.C. Connors, R.A.J. Hellen, CEGB Berkeley Nu­

clear Laboratories, Berkeley, Gloucestershire, U.K.

F 5/7 Ductile Failure of Cracked Member under Combined Loading of Membrane and Bending Stresses H. Okamura, M. Kurotobi, University of Tokyo, Tokyo, Japan

F 5/8 Estimating Structural Integrity of Type 304 Stainless Steel Plates and Pipes Containing Small Defects W.G. Reuter, F.W. Smith, EG. & G. Idaho, Inc., Idaho Falls, Idaho, T.A. Place, University of Idaho, Moscow, Idaho, U.S.A.

F 5/9 Elastic Plastic Fracture Toughness Values for a Hastelloy Sample Submitted to Static Load

P. Morgand, H. Churier, C.E.A./CEN­DMG/SEM, Grenoble, France

F 5/10 Crack Growth Rate of PWR Piping

M. Bethmont, J.J. Doyen, FRAMATOME, Paris la Défense,

J. Lebey, CEA./CEN­Saclay DEMT, Gif­sur­Yvette, France

F 5/11 Determination of Vibration Strain Limits of A106B Piping Steel B. Mukherjee, M.L Vanderglas, Ontario Hydro Research, Toronto,

Ontario, Canada F 5/12 Characterizing Fatigue Crack Propagation in 2

1Λ Cr­1 Mo

Steel for Steam Generator Applications W.R. Corwin, Μ.Κ. Booker, B.L.P. Booker, CR. Brinkman, Oak

Ridge National Laboratory, Oak Ridge, Tennessee, U.S.A.

F 5/13 Experimental J and COD Analysis of Crack Initiation in Through­Thickness Cracked Pipes C. Carmignani, S. Reale, Istituto di Impianti Nucleari, Facoltà di

Ingegneria, Pisa, G. Tomassetti, Comitato Nazionale per l'Energia Nucleare, Casac­

cia, Roma, Italy

Session F 6. Pipe Rupture

F. 6/1 * Experimental Studies of PWR Primary Piping under LOCA Conditions C. Cauquelin, FRAMATOME, Courbevoie, P. Caumette, J.L. Garcia, E. Sermet, CEA./CEN­Cadarache,

Saint­Paul­lez­Durance, France

44

F 6/2 Experimental Study of Pipe Reaction Force and Jet Impingement Load at the Pipe Break K. Kitade, T. Nagatogawa, MAPI Engineering Center, Mitsubishi

Atomic Power Industries, Tokyo, H. Nishikawa, K. Kawanishi, C. Tsúruto, Takasago Technical Insti­

tute, Mitsubishi Heavy Industries, Takasago-City, Japan F 6/3 Experimental Studies of PWR Secondary Piping in Case of Steam

Break A. Martin, FRAMATOME, Courbevoie, J.L. Cheissoux, J.L. Garcia, C.E.A./CEN-Cadarache, Saint-Paul-

lez-Durance, France F 6/4 Local Crush Rigidity of Pipes; Experiments and Application to Pipe

Whip Restraint Design K. Ikonen, Technical Research Center of Finland, Helsinki, T. Kukkola, M. K. Kangas, Imatran Voima Osakeyhtiö, Helsinki, Fin­

land F 6/5 Pneumatic Rupture of Pipes: The Development of the Breach

M.R. Baum, CEGB Berkeley Nuclear Laboratories, Berkeley, U.K. F 6/6 Transient Pressure Reductions and Flow Areas Resulting from the

Ductile Fracture of Pressurised Cylindrical Vessels G.B. Eke, CEGB Scientific Services Centre, Gravesend, Kent, U.K.

Session F 7. Pipe Rupture: Methodology

F 7/1 Design Considerations for Application of Metallic Honeycomb as an Energy Absorber W.H. Lee, Tennessee Valley Authority, Knoxville, Tennessee, R.E. Roemer, Stone & Webster Engineering Corporation, Boston,

Massachusetts, U.S.A. F 7/3 DIAPRS - A Computer Program for Dynamic Inelastic Analysis of

Ruptured Piping D.P. Mondkar, University of California, Berkeley, California, U.S.A.

F1/4 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. Theuer, M. Heller, Kraftwerk Union AG, Erlangen, Fed. Rep. Ger­

many F1/5 Comparative Study of Models for Pipe-Whip Analysis

M.A.G. Silva, L. Bevilacqua, Promon Engenharia S.A., Rio de Ja­neiro, Brazil

F 7/6 Safety of Pipe Whip Restraints C Burducea, J. Jedlicka, G. Habedank, Kraftwerk Union AG, Offen­

bach, Fed. Rep. Germany F 111 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. Chevallard, M. Famiglietti, A. Parmeggiani, G. Possa, CISE, Cen­

tro Informazioni Studi Esperienze, Milano, Italy

45

F 7/8 Numerical and Experimental Results on the Consequences of a Bursting Pressure Tube in a D20 Power Reactor R. Ciacci, M. Famiglietti, R. Leoni, C/SE, Centro Informazioni Studi

Esperienze, Milano, Italy

Session F 8. Components and Support Systems

F 8/1 Minimizing Unbalance Response of the CRBRP Sodium Pumps V. Gupta, F.G. Marrujo, Byron Jackson Pump Division, Carson, Ca­

lifornia, U.S.A. F 8/2 Experimental and Analytical Results of HDR Blowdown Tests Con­

cerning Dynamic Valve Behaviour T. Grillenberger, Gesellschaft für Reaktorsicherheit, Garching, K.-H. Scholl, Kernforschungszentrum Karlsruhe, Karlsruhe, Fed.

Rep. Germany F 8/3 Tests on a 1,75 m O.D. Bolted Flange Assembly with Spiral-Wound

Gaskets A. Bazergui, Ecole Polytechnique, Montreal, Quebec, Canada

F 8/4 Optimisation of Pipe Restraint Spacing in the Neighbourhood of Metal Containment, Pressure Vessels or Other Equipment L. Baraf, Motor-Columbus Consulting Engineers, Baden, Switzer­

land F 8/5 An Economical Produre for Small Pipe Support Design

G.C.K. Yeh, Bechtel Power Corporation, Los Angeles, California, U.S.A.

Session F 9. Heat Exchangers

F 9/1 A New Design Code for 1.5 Mwt Helium Heat Exchanger M. Kitagawa, J. Hamanaka, T. Umeda, T. Goto, Y. Saiga, Ishika-

wajima-Harima Heavy Industries Co., Ltd., Tokyo, M. Ohnami, Ritsumeikan University Kyoto, Kyoto, T. Udoguchi, Chiba University, Chiba, Japan

F 9/2 Development of Analytical Procedure for the Design of 1.5 Mwt Helium Gas Intermediate Heat Exchanger J. Hamanaka, M. Kitagawa, T. Goto, Y. Saiga, Ishikawajima-

Harima Heavy Industries Co., Ltd., Tokyo, T. Udoguchi, Chiba University, Chiba, Y. Yamada, University of Tokyo, Tokyo, Japan

F 9/3 Design of Heat Exchangers for High-Temperature Reactors J. Rautenberg, H. Spilker, Hochtemperatur-Reaktorbau GmbH,

Mannheim, Red. Rep. Germany F 9/4 Analytical and Experimental Studies of Tube/Support Interactions

in Multi-Span Heat Exchanger Tubes P.L. Ko, Atomic Energy of Canada Ltd., Chalk River, Ontario, R.J. Rogers, University of New Brunswick, Fredericton, New

Brunswick, Canada F 9/5* Some Advanced Methods in Stress Analysis of Sodium-Heat

Transfer Components P.W.P.H. Ludwig, L.M. Lardenoye, Neratoom B.V., The Hague, The

Netherlands

46

TABLE OF CONTENTS

Division G. STRUCTURAL ANALYSIS OF STEEL

REACTOR PRESSURE VESSELS

Session G 1. Overviews of Integrity Assessment

G 1/1* Fracture Testing in Support of RPV Failure Prevention in Switzer­land T. Varga, Technische Universität Wien, Vienna, Austria, D.H. Njo, Swiss Federal Office of Energy, Nuclear Safety Division,

Würenlingen, G. Prantl, Swiss Federal Institute for Reactor Research, Würenlin­

gen, Switzerland

G 1/2 Comments on Brittle Fracture Control and Structural Integrity in Nuclear Power Plant Components M. Holzmann, J. Man, Z. Bilek, Institute of Physical Metallurgy,

Brno, Czechoslovakia

G 1/3 Evaluation of the Defect Tolerance of Pressure Vessels under Combined Thermal and Pressure Loads

I. Milne, CEGB, CERL, Leatherhead, Surrey, U.K.

G 1/4 Radiation Embrittlement Saturation Effect in Commercial Light

water Reactors

K.E. Stahlkopf, T.U. Marston, EPRI, Palo Alto, California, U.SA.

G 1/5 Fracture Mechanics Evaluation of a Boiling Water Reactor

Vessel Following a Postuladed Loss of Coolant Accident S. Ranganath, General Electric Co., Nuclear Energy Engineering

Dept, San Jose, California, U.SA.

G 1/6 Fracture and Break­Through due to Surface Crack in Reactor Environment under Earthquake Conditions H. Kitagawa, S. Nakagiri, R. Yuuki, K. Ogura, Institute of Industrial

Science, University of Tokyo, Tokyo, Japan G 1 Π* U.S. Metal Properties Council Activities Pertinent to Reactor Vessel

Integrity T.R. Mager, Westinghouse Electric Corporation. Pittsburgh, Penn­

sylvania, J.J. Koziol, Combustion Engineering, Inc., Windsor, Connecticut, LE. Steele, Naval Research Laboratory, Washington, D.C, A.O. Schaefer, The Metal Properties Council, Inc., New York, N.Y.,

U.S.A.

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.

47

Session G 2. Fracture Toughness Measurements

G 2/1* Fracture Toughness of Pressure Vessel Steels from Small Speci­mens R.A. Wullaert, W.L. Server, Fracture Control Corporation, Goleta,

California, U.S.A. G 2/2 The Determination of Critical Fracture Criteria Parameters from

Small Specimen Testing F.J. Witt, Westinghouse Electric Corporation, PWR Systems Divi­

sion, Pittsburgh, Pennsylvania, U.S.A. G 2/3 The Influence of the Stress State on Fracture Toughness -

Further Results D. Aurich, H.H. Erbe, R. Helms, H. Veith, J. Ziebs, Bundesanstalt für

Materialprüfung (BAM), Berlin, Germany G 2/3a Biaxial Nominal State of Stress at the Crack Front

H. Dietmann, K. Kussmaul, Staatliche Materialprüfungsanstalt (MPA), Universität Stuttgart, Stuttgart, Fed. Rep. Germany

G 2/4 The Philosophy, Design, and Testing of a Uniform Applied Load Flat Plate Testing Machine A. Quirk, UKAEA, Safety and Reliability Directorate, Culcheth,

Warrington, Lancashire, C.E.Crook, British Nuclear Fuels Ltd., Windscale Works, Sellafield,

Cumberland, U.K. G 2/5 A2-and3-Dimensional Elasto-Plastic Finite Element Analysis of an

SENB Fracture Specimen N.J.I. Adams, The British Petroleum Company Ltd., London, U.K.

G 2/6 An Overview of Crack Arrest as it Applies to ReactorVessel Integrity T.U. Marston, K.E. Stahlkopf, EPRI, Palo A/to, California, U.SA.. E. Smith, University of Manchester/'UMIST, Manchester, U.K.

G 2/7 Revised Fracture Toughness Reference Curves W. Oldfield, Materials Research & Computer Simulation. Goleta,

California, T.U. Marston, Electric Power Research Institute, Palo Alto, Califor­

nia, USA.

Session G 3. Fracture Mechanics: Elasto-Plastic

G 3/1* Elasto-Plastic Fracture Mechanics Applied to the Safety Assess­ment of Nuclear Power Stations N.J.I. Adams, The British Petroleum Company Ltd., London, S.J. Garwood, The Welding Institute, Abington. Cambridge, U.K. J.N. Robinson, Khonkaen University, Khonkaen, Thailand

G 3/2 Absorbed Specific Energy of Fracture, a Failure Criteria for Neutron Irradiated Materials F.Gillemot, Hungarian Academy of Sciences, Central Research In­

stitute for Physics, Budapest, Hungary

48

G 3/3 Energy Based Methods for Determining Elastic Plastic Fracture F.J. Witt, Westinghouse Electric Corporation, PWR Systems Divi­

sion, Pittsburgh, Pennsylvania, U.S.A. G 3/4 The Application of Post Yield Fracture Methodology to the Evalua­

tion of Large Structures J.D. Landes, Westinghouse Electric Corporation, Research and

Development Center, Pittsburgh, Pennsylvania, U.S.A.

Session G 4. Fracture Mechanics: Special Aspects

G 4/1* Further Studies on Stress Intensity Factors of Semi-Elliptical Cracks in Pressurized Cylinders A.S. Kobayashi, A.F. Emery, W.J. Love, A. Jain, University of Wash­

ington, Seattle, Washington, U.S.A. G 4/2 The Effect of Transverse Shear and Material Orthotropy in

Cracked Cylindrical and Spherical Shells F. Erdogan, F. Delale, Lehigh University, Bethlehem, Pennsylvania,

USA. G 4/3 Stress Intensity Factor Solutions for Arbitrarily Shaped Surface

Flaws in Reactor Pressure Vessel Nozzle Corners S.N. Atluri, K. Kathiresan, Georgia Institute of Technology, Atlanta,

Georgia, U.S.A.

G 4/4 Stress Intensity Distributions in Nozzle Corner Cracks of Complex Geometry C.W. Smith, W.H. Peters, W.T. Hardrath, T.S. Fleischman, Virginia

Polytechnic Institute, Blacksburg, Virginia, U.SA. G 4/5 On the Validity of Kj .-Measurements in Instrumented Impact Tests

J.F. Kalthoff, S. Winkler, W. Klemm, J. Beinert, Institut für Festkör­permechanik der Fraunhofer Gesellschaft, Freiburg, Fed. Rep. Germany

G 4/6 The Response of Pressure Vessel Steel Specimens on Drop Weight Loading S. Winkler, J.F. Kalthoff, Institut für Festkörpermechanik der

Fraunhofer Gesellschaft, Freiburg, A. Gerscha, Kraftwerk Union AG, Erlangen, Fed. Rep. Germany

Session G 5. Fracture Mechanics: Stable Crack Growth

G 5/1* The Use of CT-and Bend Specimens for Tearing Modulus Determi­nations A.J. Carlsson, Royal Institute of Technology, Stockholm. Sweden, C. Wüthrich, Brown Boveri Research Center, Baden, Switzerland

G 5/1 a* The Status of Tearing Instability Analysis withdrawn P.C. Paris, M.P. Gomez, Washington University, St. Louis, Missouri,

U.S.A.

49

G 5/2 Crack Initiation and Growth under Fully Plastic Conditions with Applications to Pressure Vessel Steels CF. Shih, W.R. Andrews, J.P.D. Wilkinson, V. Kumar, General

Electric Corporate Research Et Development Center, Schenecta­dy, New York, USA.

G 5/4 Stable Ductile Crack Growth in Reactor Pressure Vessel Steels E. Smith, Joint Manchester University/'UMIST Metallurgy Depart­

ment, Manchester, U.K. G 5/5 Consideration of Nonsteady State Crack Growth in Materials

Evaluation and Design S.J. Hudak, Jr., Westinghouse Electric Corporation, Research and

Development Center, Pittsburgh, Pennsylvania, R.P. Wei, Lehigh University, Bethlehem, Pennsylvania, U.S.A.

Session G 6. Fracture Mechanics: Materials Modeling

G 6/1 * Evidence for the Relative Importance of Dynamic Fracture Tough­ness D.R. Ireland, Effects Technology, Inc., Santa Barbara, California,

U.S.A., S. Tominaga. T. Maruyama, Babcock-Hitachi, Ltd., Kure-City, Hi­

roshima Prefecture, Japan G 6/2* Effects of Plasticity and Crack Geometry on Fracture

H. Liebowitz, J. Lee, N. Subramonian, The George Washington University, Washington, D.C, U.S.A.

G 6/3 The Effect of Microstructure on the Fracture Toughness of Struc­tural Steels M. Holzmann, Β. Vlach, Ζ. Bilek, Institute of Physical Metallurgy,

CAS, Brno, Czechoslovakia G 6/4 Computational Modeling of Microstructural Ductile Fracture

Processes in A 533 Β Pressure Vessel Steel D.R. Curran, L. Seaman, D.A. Shockey, K.C. Dao, R.L. Burback, SRI

International, Menlo Park, California, U.S.A. G 6/5 Characterizations of Continuing Fracture in Elastic-Plastic Solids

CF. Shih. General Electric Corporate Research and Development Center, Schenectady, New York, U.S.A.

Session G 7. Fracture Mechanics: Computation

G 7/2 Evaluation of Three-Dimensional J-lntegral of Semi-Elliptical Surface Crack in Pressure Vessel M. Kikuchi, H. Miyamoto, Science University of Tokyo, Noda-City,

Chiba, Y. Sakaguchi, Kure Works, Babcock-Hitachi K.K., Kure-Shi, Hiro­

shima-Ken, Japan G 7/3 Stress Analysis and Fracture of Surface Cracks in Cylindrical

Pressure Vessels J.C Newman, Jr., I.S. Raju, NASA Langley Research Center, Hamp­

ton, Virginia, U.S.A.

50

Session G 8. Fatigue

G 8/1 * A Criterion for Analysing Fatigue Crack Initation in Geometrical Singularities J.C. Devaux, FRAMATOME, Etablissement de Saint Marcel, Saint

Marcel, Y. D'Escatha, Service de l'Industrie et des Mines, Bureau de Con­

trôle de la Construction Nucléaire, Dijon, P. Rabbe, Creusot-Loire, Centre de Recherche d'Unieux, Unieux, A. Pellissier-Tanon, FRAMATOME, Tour Fiat, Paris, France

G 8/2 Verification of the Resistance of PWR Thermal Sleeves to Ther­mal Fatigue M. Bosser, F. Mercier, FRAMATOME, Etablissement de Saint

Marcel, Saint Marcel, C. Amzallag, Creusot-Loire, Centre de Recherche d'Unieux, Uni­

eux, J. Ponsot, Creusot-Loire, Laboratoire du Creusot, Le Creusot,

France

Session G 9. Fracture Mechanics: Thermal Effects

G 9/2 Dynamic Fracture Analysis of Thermal Shock Loading in Nuclear Pressure Vessels P.C. Gehlen, M.F. Kanninen, GT. Hahn, Battelle Columbus Labora­

tories, Columbus, Ohio, CH. Popelar, Ohio State University, Columbus, Ohio, U.S.A.

G 9/4 Cyclic Elastic Analysis of a PWR Nozzle Subjected to a Repeated Thermal Shock J.M. Locci, Engineering System International, Rungis-Silic, J.P. Prost, FRAMATOME. Paris, France

G 9/6 A Fracture Mechanics Approach to Predicting the Effects of Warm Prestressing and its Applications to Pressure Vessels G.G. Cheli, CEGB, Research Laboratories, Leatherhead, Surrey,

U.K.

51

Session G 10. Stress Analysis

G 10/1* Interpretation of Strain Measurements on Nuclear Pressure Ves­sels S.I. Andersen, P. Engbaek, Risø National Laboratory, Roskilde,

Denmark G 10/2 Bolted Joints as a Problem of Elastically Supported Slabs

D. Kowalske, Technischer Überwachungsverein Norddeutschland, Hamburg, Fed. Rep. Germany

G 10/3 Structural Analysis of a PWR Vessel Nozzle-to-Hemisphere P. Lecarpentier, EDF/SEPTEN, Paris, P. Bourrier, SOCOTEC/GIN-AME, Paris, A. Millard, CEA./CEN-Saclay DEMT, Gif-sur-Yvette, France

G 10/5 A Semi-Analytical Technique for the Design of Rolled Joints R.K. Sinha, A. Kakodkar, Bhabha Atomic Research Centre, Trom­

bay, Bombay, India

G10/6 Thermal and Structural Anaysis of the Support Region of an LMFBR Reactor Vessel A. Hunsbedt, S. Kraus, General Electric Co., Advanced Reactor Sy­

stems Department, Sunnyvale, California, U.S.A. G 10/7 Finite Element Analysis of Inclined Nozzle-Plate Junctions

KB. Dixit, V.K. Seth, A. Krishnan, Government of India, Power Pro­jects Engineering Division, Colaba, Bombay,

TS. Ramamurthy, B. Dattaguru, A.K. Rao, Indian Institute of Science, Bangalore, India

52

TABLE OF CONTENTS

Division H. STRUCTURAL ENGINEERING OF PRESTRESSED REACTOR PRESSURE VESSELS

Session H 1. Materials Behavior I

H 1/1* Properties of Concrete at Elevated Temperatures L. Weissbacher, J. Német, Reaktorbau Forschungs- und Bauge­

sellschaft, Seibersdorf, H. Zemann, Österreichische Studiengesellschaft für Atomenergie.

Seibersdorf, Austria H 112 Strength Characteristics of Concrete in the Temperature Range of

20° to 200° C R. Kottas, J. Seeberger. H.K. Hilsdorf. Universität Karlsruhe. Karls­

ruhe, Fed. Rep. Germany H 1/3 Heat and Moisture Transfer in Concrete Under the Influence of

Temperature J.C Hundt, Bundesanstalt für Materialprüfung, Berlin (West), Ger­

many H 1/4 Concrete for PCRVs: Mechanical Properties at Elevated Tem­

peratures and Residual Mechanical Behaviour after Triaxial Prel­oading H. AschI, Ingenieurbüro Alois Aschl, München, W. Moosecker, Technische Universität München, München, Fed.

Rep. Germany H 1/5 Moisture Transport and Vapor Release of Concrete Structures at

Temperatures > 100° C K. Kordina, U. Schneider, Technische Universität Braunschweig,

Braunschweig, Fed. Rep. Germany H 1/6 Moisture Transfer in a Concrete Slab

C.L.D. Huang, H.H. Siang, P.G. Kirmser, Kansas State University, Manhattan. Kansas, U.S.A.

H 1/7 Creep, Strength and Thermal Expansion of Concrete at Elevated Temperatures M. Sakuta, H. Kasami, Y. Yoshioka, Takenaka Technical Research

Laboratory, Tokyo, Japan

Session H 2. Materials Behavior II

H 2/1 Thermal Expansion of Concrete for Nuclear Structures S. Ziegeldorf, K. Kleiser, HK. Hilsdorf. Universität Karlsruhe, Karls­

ruhe, Fed. Rep. Germany

— The sign ("I 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 ava lable at the time of finishing of the book. — A paper number missing in the numeral order means that the paper was cancelled or withdrawn.

53

H 2/2 Measurements Inside the Structural Concrete of a PCPV at Eleva­ted Temperatures H. Zemann, Österreichische Studiengesellschaft für Atomenergie,

Seibersdorf, L. Weissbacher. Reaktorbau Forschungs- und BaugeseHschaft,

Seibersdorf, Austria H 2/3 Effect of Nuclear Radiation on Mechanical Properties of Concrete

J. Seeberger, HK. Hilsdorf, Universität Karlsruhe, Karlsruhe, Fed. Rep. Germany

H 2/4 Ultimate Strength Criteria of Concrete Under Bi-axial and Tri­axial Loading G. Valente, Università di Roma, Roma, Italy

H 2/5 Failure Strength and Elastic Limit for Concrete: A Comparative Study G. Robutti, E. Ronzoni, ISMES, Bergamo, Italy, N. S. Ottosen, National Laboratory Risø, Roskilde, Denmark

H 2/6 Model Based on the Intrinsic Behaviour of the Concrete Under Cyclical Loads for the Dynamic Analysis of Three-Dimensional Structures J.-D. Favrod, R. Kneuss, B. Rebora, C. Rodriguez, IPEN, Ecole Po­

lytechnique Fédérale de Lausanne, Lausanne, Switzerland H 2/7 Some Notes on the Dynamic Properties of Unsaturated Con­

crete ST. Wu, Ebasco Services, New York, N.Y., U.S.A.

withdrawn

Session H 3. Design, Research, and Surveillance of PCVs

H 3/1* Latest Developments in Prestressed Concrete Vessels for Gas-Cooled Reactors F.S. Ople, Jr., General Atomic Company, San Diego, California,

U.S.A. H 3/2 Feasibility Study of Prestressed Concrete Pressure Vessels for

Coal Gasifiers C.B. Oland, W.L. Greenstreet, J.P. Callahan, Oak Ridge National

Laboratory, Oak Ridge, Tennessee, U.S.A. H 3/3 Innovations in Prestressed Concrete Pressure Vessel Design

P.Y. Chow, De Ngo, T.Y. Lin, T.Y. Lin International, San Francisco, California, U.SA.

H 3/4 Surveillance of Prestressed Concrete Pressure Vessels Under Commissioning and Operational Conditions at Hunterston ,B' Pow­er Station H.M. Aird, South of Scotland Electricity Board, Glasgow, U.K. S.H. Forgie, James Williamson & Partners, Glasgow, J.A. Holland, Rendei Palmer 8- Tritton, Glasgow, Scotland, U.K.

H 3/5 The Strain Behaviour of a Prestressed Concrete Reactor Pressure Vessel after 12 Years Operation I.W. Hornby, CEGB, Leatherhead, Surrey, U.K.

54

H 3/6 Grouted and Nongrouted Tendons for Prestressed Concrete Pres­sure Vessels D.J. Naus, Oak Ridge National Laboratory, Oak Ridge, Tennessee,

U.S.A. H 3/7 Research and Development in Support of the Design of a Prestres­

sed Concrete Pressure Vessel for a Working Pressure of 69 N/mm2

(10,000 p.s.i.) F.K Garas, Taylor Woodrow Construction Ltd., Southall, Middle­

sex, U.K. H 3/8 Aspects of the Design of Modern PCRV with Respect to the

H HT-Vessel G. Schnellenbach, K. Schimmelpfennig, Ingenieurbüro Prof. Zerna

St Dr. Schnellenbach, Bochum, Fed. Rep. Germany

Session H 4. Structural Analysis of PCVs and Components

H 4/1 * Experimental and Analytical Studies of Shear Behaviour of Slabs Subjected to Multiaxial Stress Conditions F.K. Garas, CC. Fleischer, B.R. Waine, Taylor Woodrow Construc­

tion Ltd., Southall, Middlesex, U.K. H 4/2 An Exploration of the Design fora PCCV Head Slab with Very Large

Penetrations Using a Dynamic Relaxation Computer Program F.K. Garas, I. LI. Davies, C C Fleischer, B.R. Waine, Taylor Woo­

drow Construction Ltd., Southall, Middlesex, P.L.T. Morgan, Sir Robert McAlpine & Sons, Ltd., c./o. Nuclear Po­

wer Co. (Risley) Ltd., Risley, Warrington, Cheshire, U.K. H 4/3 Failure Criterion of Concrete Type Material and Punching Failure

Analysis of Thick Mortar Plate T. Ohno, Kansai Electric Power Co., Kita-ku, Nakanoshima, M. Kuroiwa, Technical Research Center, Kansai Electric Power Co.,

Amagasakishi, Wakaogi, M. Irobe, Nihon University, Nakamachi, Japan

H 4/4 Parametric Study on Ligament Stresses in Multi-Cavity Prestressed Concrete Reactor Vessels (PCRVs) S.R. Speidel, Bilfinger & Berger Bau-AG, Mannheim, Fed. Rep.

Germany H 4/5 Test of the Second Model of the GCFR Steam Generator Cavitiy

Closure Plug J.P.Callahan, G.C Robinson, W.G. Dodge, Oak Ridge National La­

boratory, Oak Ridge, Tennessee, U.S.A. H 4/6 Verification of the Non-Linear Finite Element Code .ADINA Appli­

cable to the Analysis of Heated Concrete Structures I.G. Smith, National Engineering Laboratory, East Kilbride, Glas­

gow, Scotland, U.K. H 4/7 Methods for Calculating Inelastic Response of Prestressed Con­

crete Pressure Vessels and Vessel Closures D.N. Fanning, W.G. Dodge, Oak Ridge National Laboratory, Oak

Ridge, Tennessee, U.S.A.

55

H 4/8 Model - Including Thermal Creep Effects - for the Analysis of Three-Dimensional Concrete Structures; Comparison with Tests C. Rodriguez, B. Rebora, J.-D. Favrod, IPEN, Ecole Polytechnique

Fédérale de Lausanne, Lausanne, Switzerland H 4/9 Creep Behavior Under Sustained Temperature Gradient in a Model

of Prestressed Concrete Reactor Vessels H.Ohnuma.Y. Aoyagi, H.Abe, Central Research Institute of Electric

Power Industry, Abiko. Chiba, Japan

Session H 5. Liner and Thermal Barrier Systems

H 5/1 Lateral Deflection of PCRV Liners in the Plastic Range W. Gorholt, General Atomic Company, San Diego, California.

U.S.A. H 5/2 Liner Leak Simulation Tests on Prestressed Concrete Reactor

Pressure Vessels I.W. Hornby, B.N. Grainger, CEGB Research Laboratories, Leather-

head, Surrey, U.K. H 5/3 The Elastic Hot Liner-Design, Stress and Fatigue Analysis, Opera­

tion, Inspection and Repair J. Mutzl, VÖEST-Alpine Montan AG, Wien, H. Hinterleitner, Reaktorbau Forschungs- und Baugesellschaft,

Seibersdorf, Austria H 5/4 Concept, Analysis and Construction of the Liner for Hot-Working

Prestressed Cast Iron Pressure Vessels J. Güldenpfennig, L.&C Steinmüller GmbH, Gummersbach, Fed.

Rep. Germany H 5/5 Testing and Analysis of a High Temperature Thermal Barrier for

Gas-Cooled Reactors W.E. Black, W.S. Betts, General Atomic Company, San Diego, Cali­

fornia, U.S.A., P. Felten, CEA./CEN-Saclay, DEMT, Gif-sur-Yvette, France

H 5/6 Testing and Analyses of a High Temperature Duct for Gas-Cooled Reactors W.E. Black, A. Roberge, General Atomic Company, San Diego. Ca­

lifornia, U.S.A. P. Felten, R. Bastien, CEA/CEN-Saclay, DEMT, Gif-sur-Yvette,

France H 5/7 Design of Steel-Liners and Their Anchorage with Regard to

Non-Linear Behaviour of Liner-Material and Anchorage R. Oberpichler, Ingenieurbüro Prof. Zerna - Dr. Schnellenbach,

Bochum, Fed. Rep. Germany

56

Session H 6. Concept and Research for a PCV with Hot Liner

H 6/1 " Concept, Construction, Testing and Operational Safety of a PCPV with Elastic Hot Liner and Adjustable Wall Temperature J. Német, Reaktorbau Forschungs­ und Baugesellschaft, Seibers­

dorf, K. Fritz Österreichische Studiengesellschaft für Atomenergie, Sei­

bersdorf, Austria

H 6/2 Advanced Prestressed Concrete Pressure Vessels for Gas­Cooled Fast Breeder Reactors H. Kumpf, P. Rau, Kraftwerk­Union AG, Erlangen, Fed. Rep. Ger­

many. H. Hinterleitner, J. Német, Reaktorbau Forschungs­ und Bauge­

sellschaft. Seibersdorf, Austria

Η 6/3 Feasibility of a Multicavity PCPV with Elastic Hot Liner for HTR HG. Schwiers, Hochtemperatur­Reaktorbau GmbH, Mannheim,

Fed. Rep. Germany, H. Hinterleitner, W. Walluschek, Reaktorbau Forschungs­ und

Baugesellschaft, Seibersdorf, Austria

Η 6/4 The Characteristics of the PCRV of the HHT Demonstration Plant J. Scheming, H.­G. Schwiers, Hochtemperatur­Reaktorbau GmbH,

Mannheim, Red. Rep. Germany

Η 6/5 Assessment and Structural Analysis of a PCPV with Hot Liner and Adjustable Wall Temperature A. Nesitka, E. Ettel, M. Gangl, H. Hinterleitner, Reaktorbau For­

schungs­ und Baugesellschaft, Seibersdorf, Austria

Η 6/6 Thermal Behaviour of a PCPV with Adjustable Wall Temperature A. Witt, Österreichische Studiengesellschaft für Atomenergie, Sei­

bersdorf, M. Gangl, Reaktorbau Forschungs­ und Baugesellschaft, Seibers­

dorf, K. Mayr, Simmering­Graz­Pauker AG, Wien, Austria

Session H 7. Concepts and Research for a PCIV

H 7/1 The Particular Features of PCIVs for HTR and other Applications in Nuclear Stations

L. Guelicher, B. Beine, Siempelkamp, Krefeld, W. Albrecht, L.&C Steinmüller GmbH, Gummersbach, W. Jahns, Gesellschaft für Hochtemperaturreaktor­Technik, Ber­

gisch Gladbach, J. Scheming, Hochtemperatur­Reaktorbau GmbH, Mannheim, Fed.

Rep. Germany

H 7/2 Criteria of Design and Analysis for Cold­ and Hot­Working Pre­stressed Cast Iron Pressure Vessels (PCIV) D. Bounin, E.P. Warnke, Siempelkamp, Krefeld, H.G. Schwiers, P. Mitterbacher, Hochtemperatur­Reaktorbau

GmbH, Mannheim, Fed. Rep. Germany

57

H 7/3 Design, Construction and Pressure Test of a PCIV Gas Storage Vessel for the THTR-300 E.K. Lethert, H.J. Wester, Siempelkamp, Krefeld, H.G. Schwiers, Hochtemperatur-Reaktorbau GmbH, Mannheim,

Fed. Rep. Germany H 7/4 Structural Analysis of Cellular Blocks for a Prestressed Cast Iron

Reactor Pressure Vessel R.G. Thomas, U.KA.EA., Culcheth, Warrington, J.L. Head, Imperial College, London, UK.

H 7/5 Ultrasonic Testing of Large Blocks for Prestressed Cast Iron Pres­sure Vessels H.-A. Stelling, Staatliches Materialprüfungsamt NW, Dortmund,

Fed. Rep. Germany

Session H 8. Concept and Research for a PCV for the LMFBR

H 8/1* Transient Analysis of LMFBR Reinforced/Prestressed Concrete Containment A.H. Marchertas, Argonne National Laboratory, Argonne, Illinois, T.B. Belytschko, Z.P. Bazant, Northwestern University, Evanston,

Illinois, U.S.A. H 8/2 Comparison of Transient PCRV Model Test Results with Analysis

A.H. Marchertas, Argonne National Laboratory, Argonne, Illinois, T.B. Belytschko, Northwestern University, Evanston, Illinois,

USA. H 8/4 Local Thermal and Structural Behavior of Concrete at Elevated

Temperatures E.L. Gluekler, General Electric Co., Advanced Reactor Systems De­

partment, Sunnyvale, California, U.S.A. H 8/5 Design and Development of a High Thermal Conductivity Concrete

for the Sodium Cooled Fast Reactor R. Blundell, S. Kupermann, Taylor Woodrow Construction Ltd.,

Southall, Middlesex, K. Albeson, W. Blair, Nuclear Power Co. (Risley) Ltd., Risley,

Warrington, U.K. H 8/6 Thermal and Thermal Stress Analysis of a Pool Type LMFBR Deck

Structure M. Stephenson, H. Ahmed, D. Ma, Argonne National Laboratory,

Argonne, Illinois, U.S.A. H 8/7 Speculations on the Design of a Containment Vessel with a Hot Li­

ner for Use with Fast Reactor Systems I.LI. Davies, Taylor Woodrow Construction Ltd., Southall, Midd­

lesex, P.H.H. Wolff, Nuclear Power Co. (Whetstone) Ltd., Whetstone, Lei­

cester, U.K.

58

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* 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. J 1/2 Evaluation of Load Combination Equations for ASME Section III

Division 1 Components S.W. Tagart, Jr., Nuclear Services Corporation, Campbell, Califor­

nia, U.S.A. J 1/4 A Probabilistic Approach to the Design of Nuclear Containment

Structures P. Petrinä, Sargenta LundyEngineers, Chicago, Illinois, U.S.A.

J 1/5 Risks of Nuclear Containment Structures due to Aircraft Crashes and Earthquake Loadings J. Bauer, Technische Universität München, München Fed. Rep.

Germany withdrawn J 1/6 Design and Construction of the Prestressed Concrete Contain­

ments of the French Standard 900 MWe PWR R. Bordet, J.L. Costaz, J.F. Laboudigue, Electricité de France, SEP-

TEN, Paris, France J 1/9 Experience in the Safety Assessment of the SNR-300-Contain-

ment 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 Hy-drodynamic Loads M. Michail. G. Shah, L.-O Hua, Bechtel Power Corporation, San

Francisco, California, U.S.A. withdrawn J 2/7 Response of a BWR MARK II Containment Structure to Chugging

Loads B. Bedrosian, M. Ettouney, Burns & Roe, Inc., Woodbury, New

York, USA. J 2/8 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. J 2/9 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 Cor­

poration. Gaithersburg, Maryland, U.S.A.

Session J 3. Concrete Containment Design and Analysis

J 3/1 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. J 3/2 Behaviour of Concrete Containment under Over-Pressure Condi­

tions R.J. Atchison, G.J.K. Asmis, F.R. Campbell, Atomic Energy Control

Board, Ottawa, Ontario, Canada J 3/3 Effect of Crack Formation Process and Tension Stiffening on Ther­

mal 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 J 3/4 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

J 3/5 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

60

J 3/7 Analysis of Concrete Containments for Non-Linear Strain Gra­dients A. Walser, D.J. Carreira, Sargenta Lundy Engineers, Chicago, Illi­

nois, U.S.A. J 3/8 Computer Plotting and Calculation of Containment Prestressing

Cables .. Benamou, Electricité de France, SEPTEN, Paris, .. Picaut, P. Pouyet, Coyne & Bellier, Paris, France

J 3/9 Lateral Rigidity of Cracked Concrete Structures A. Castellani, C. Chesi, Politecnico di Milano, Milano, Italy

J 3/10 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 J3/11 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 * 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

J 4/2 A Test of a Model of a Thin-Walled Prestressed Concrete Second­ary Containment Structure S. Rizkalla, S.H. Simmonds, J.G. MacGregor, University of Alber­

ta, Edmonton, Alberta, Canada J 4/4 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 In­

dustry, Abiko-shi, Chiba, Japan J 4/5 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 La­

boratory, Tokyo, Japan

61

J 4/6 Design Method of Shell Wall End of Reinforced Concrete Contain­ment Vessel (RCCV) Against Radial Shear Y. Aoyagi, Central Research Institute of Electric Power Industry,

Abiko City, Chiba, O Isobata, N. Tanaka, Shimizu Construction Co., Ltd., Tokyo, Ja­

pan J 4/7 An Experimental Approach to the Design of Network Reinforce­

ment Against In-plane Shear in Reinforced Concrete Containments Y. Aoyagi, Central Research Institute of Electric Power Industry,

Abiko City, Chiba, K. Yamada, Technical Research Laboratory of Maeda Construction

Company, Tokyo, Japan J 4/8 Results of Strength Tests on a 1:10 Model of Reactor Containment

K. Donten, M. Knauff, A. Sadowski, W. Scibak, Po/itechnika Warszawska, Warsaw, Poland

J 4/9 Ductility and Failure of Net-Reinforced Concrete Shell Walls Z.P. Bazant, P. Gambarova, Northwestern University, Evanston, Il­

linois, U.S.A.

Session J 5. 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. Yamakawa, Research Laboratory of Shimizu Construction Co.,

Ltd., Tokyo, Japan J 5/4 Plate on Elastic Foundation Subject to Thermal Loading

H.D.Tabakman, Y.J. Lin, Bechtel Power Corporation, Los Angeles, California, U.S.A.

J 5/6 Self Limiting Loads for Concrete Structures L. Lazzeri, F. Bozzo, AMN S.p.A., Genova, A. Berro, G.A. Righetti, Università di Genova, Genova, Italy

J 5/7 Analysis of Drywell Floor Slab for Random Lateral LOCA Loads on Downcomers M.P. Singh, Virginia Polytechnic Institute and State University,

Blacksburg, Virginia, S. Singh, M. Valathur, Sargent & Lundy, Engineers, Inc. Chicago,

Illinois, U.S.A. J 5/8 Inelastic Analysis and Design of Ductile Structures Submitted to

Induced Vibrations of Extreme Events R. Danisch, U. Graubner, Kraftwerk Union AG, Erlangen, Fed. Rep.

Germany

62

Session J 6. Structural and Leak Testing and Design of Containment Components

J 6/1 A Containment Wall with Integrated Venting D. Costes, CE.A./Département de Sûreté Nucléaire, Fontenay-

aux-Roses, France J 6/3 A Realistic Structural Analysis of the Integrity of the Liner of Rein­

forced and Prestressed Concrete Containments F. Buchhardt, P. Brandi, Bundesanstalt für Materialprüfung (BAM),

Berlin (West), Germany J 6/5* Performance of Scandinavian BWR-Containrnents During Pres­

sure Tests A. Engelbrektson, VBB Vattenbyggnadsbyran, Stockholm, K. Boye-Møller, Swedish State Power Board, Vällingby, Sweden

J 6/6 Stability Investigations of Spherical Steel Shell Containment A. Andersen, S. Bantle, L.M. Habip, Kraftwerk Union AG, Frank­

furt am Main, Fed. Rep. Germany J 6/7 Experimental Study of a Spherical PWR-Containment with

Geometrical Imperfections at the Welds F.W. Bornscheuer, Universität Stuttgart, Stuttgart, Fed. Rep. Ger­

many J 6/8 Optimization of the Containment Nozzles

A. Andersen, S. Bantle, Kraftwerk Union AG, Frankfurt am Main, Fed. Rep. Germany

J 6/9 Elasto-Plastic Analysis of Nozzle Intersections in Reactor Contain­ments J.M. Sättele, E. Ramm, F.W. Bornscheuer, Universität Stuttgart,

Stuttgart, Fed. Rep. Germany

Session J 7. Impact Load Analysis and Design I

J 7/1 * Test and Calculation of the Local Behaviour of Concrete Structures under Missile Impact C. Berriaud, P. Verpeaux, A. Hoffmann, CEA /CEN-Saclay DEMT,

Gif-sur-Yvette, P. Jamet, CEA./CEN-Saclay STA, Gif-sur-Yvette R. Avet-Flancard, CEA. ICEN, DSR, Fontenay-aux-Roses,

France J 7/2 Impact and Impulsive Loading on Thin Shell Structures

Y. Crutzen, Commission of the European Communities, J.R.C. Ispra Establishment, Ispra, Italy

J 7/3 Experimental Investigation of Reinforced Concrete Behaviour due to Impact Load K. Brandes, E. Limberger, J. Herter, Bundesanstalt für Materialprü­

fung (BAM), Berlin (West), Germany J 7/4 Inelastic Behavior of Reinforced Concrete Slabs Subjected to Im­

pact Loads - Experimental and Numerical Analysis J.L. Costaz, J. Dulac, J.F. Laboudigue, Electricité de France, SEP-

TEN, Paris, France

63

J 7/5 Impact Testing of Steel Fibre Reinforced Concrete Slabs with Liner F. Stanqenberg, Ingenieurbüro Prof. Zerna - Dr. Schellenbach,

Bochum, P. Buttmann, Brown Boveri & Cie AG, Mannheim, Fed. Rep.

Germany

J 7/6 Behavior of Reinforced Concrete Barriers Subject to the Impact of Turbine Missiles P.M. McMahon, S.K. Sen, B.L. Meyers, Bechtel Power Corporation,

Gaithersburg, Maryland, U.S.A. J 7/9 Analysis of the Overall Structural Behavior due to the Impact of De-

formable Missiles M.M. Ettouney, R.R. Radini, P.S. Hsueh, Burns & Roe, Inc., Wood­

bury, New York, U.S.A. J 7/11 Energy Absorbing Missile Barrier Systems

A. Danay, J.H.K. Tang, J.J. Deans, Ontario Hydro, Toronto, Ontar­io, Canada

Session J 8. Impact Load Analysis and Design II

J 8/1 Scaling Laws Applied to Impact Testing and Computer Assess­ments Made to Compare Tests at Two Scales I.LI. Davies, D. Carlton, Taylor Woodrow Construction Ltd., Sou­

thall, Middlesex, T.P. O'Brien, Atomic Weapons Research Establishment, Foulness,

Essex, U.K. J 8/2 Function Behavior of a Gas-Operated Accelerator for Kinetic

Energy Projectiles H. Heine, Meppen, Fed. Rep. Germany

J 8/3 Dynamic Measurements During the Test Series with the Gas-Operated Accelerator at Meppen H.J. Weithäuser, Meppen, Fed. Rep. Germany

J 8/4 Response of Reinforced Concrete Targets to Impacting Soft Missiles. An FRGMRT-UKAEA Co-operation in Tests to Vali­date Computer Codes and Scaling Laws F. Sage, UKAEA, Safety and Reliability Directorate, Culcheth, War­

rington, Lancashire, U.K., A. Pfeiffer, Ges. für Reaktorsicherheit, Köln, Fed. Rep. Germany

J 8/5 Experimental Investigations to Determine the Kinetic Ultimate Bearing Capacity of Reinforced Concrete Slabs Subject to Defor-mable Missiles W. Jonas, R. Meschkat, H. Riech, E. Rüdiger, Hochtief AG, Frank­

furt/Main, Fed. Rep. Germany J 8/6* Approximate Calculation of the Impact of Missiles onto Rein­

forced Concrete Structures and Comparison of Test Results W. Jonas, R. Meschkat, H. Riech, E. Rüdiger, Hochtief AG,

Frankfurt IMain, F.R. Germany

64

J 8/7 Local Failure of Reinforced Concrete under Missile Impact Load­ing M.L. Brown, N. Curtress, J. Jowett, UKAEA, Safety and Reliability

Directorate, Culcheth, Warrington, Cheshire, U.K. J 8/8 Experimental Validation of the EURDYN and CADROS Finite Ele­

ment Codes for the Calculation of Metal Target Response to Low-Velocity Missiles A.J. Neilson, P.G. Carter, UKAEA, Atomic Energy Establishment,

Winfrith, Dorchester, Dorset, U.K. J 8/9 Experimental Study on Strength of Steel Plates Subjected to

Missile Impact H. Miyamoto, Science University of Tokyo, Noda-shi, Chiba, S. Shida, N. Chiba, Hitachi Research Laboratory, Hitachi Ltd.,

Ibaraki, S. Ohte, H. Yoshizawa, Toshiba R Et D Center, Toshiba Corpora­

tion, Kawasaki-shi, Japan J 8/11 Fall of a 75 ton Fuel Element Container in a Storage Pool and the

Subsequent Loading of the Pool Walls C.J.L. Florie, Physics International, Gouda, H. v.d. Ree, Bredero's Bouwbedrijf Nederland B.V., Utrecht, M.J. v.d. Hoek, Physics International, Gouda, The Netherlands

J 8/12 Full Scale Turbine-Missile Casing Exit Tests withdrawn H.R. Yoshimura, J.T. Schamaun, Sandia Laboratories, Albuquer­

que, New Mexico, G.E. Sliter, Electric Power Research Institute, Palo Alto, California,

U.SA.

Session J 9. Aircraft Impact Load

J 9/1 Analyses of Critical Structures and Contained Equipment for Aircraft Impact Loadings H. Kamil, G. Kost, R. Sharpe, Engineering Decision Analysis

Company, Inc., Palo Alto, California, U.SA., N.J. Krutzik, Kraftwerk Union AG, Offenbach (Main), S. Shankar, Engineering Decision Company, Inc., Frankfurt (Main),

Fed. Rep. Germany J 9/2 A Critical Reappraisal of Nuclear Power Plant Safety against Acci­

dental Aircraft Impact J.D. Riera, Curso de Pós-Graduacão em Engenharia Civil, Porto

Alegre, RS, Brazil J 9/3 The Effect of Crash Zones in the Design of Nuclear Structures

K.-J. Pittner, Babcock-Brown Boveri Reaktor GmbH, Mannheim, J. Bauer, H. Kappler, G.I. Schuëller, Technische Universität Mün­

chen, München, Fed. Rep. Germany J 9/4 Numerical Analysis of the Local and Global Structural Response

of a Reactor Building Under Airplane Crash Loading J.F. Chedmail, J.C. Bianchini, J. Dubois, Engineering System Inter­

national S.A., Rungis-Silic, France J.D. Renard, Electrobel S.A., Bruxelles, Belgium

65

J 9/5 Analysis of the Behaviour of a Concrete Structure due to an Air­plane Impact and the Effects of the Reinforcements H. v.d. Ree, Bredero's Bouwbedrijf Nederland B.V., Utrecht, M.J. v.d. Hoek, Physics International, Gouda, The Netherlands

J 9/6 Comparison of Response Spectra for Aircraft Impact Calculated by a Beam­Model and a 3D­Shell­Model J. Krivy, W.M. Kuntze, Gesellschaft für Reaktorsicherheit, Köln,

Fed. Rep. Germany

J 9/7 Airplane Crash and External Explosions — Design Standards in the Federal Republic of Germany M. Bork, G. Philip, Kerntechnischer Ausschuß (KTA)­Geschäfts­

stelle bei der GRS, Köln, Fed. Rep. Germany

J 9/8 Nonlinear Behaviour of Reinforced Concrete Shells under Aircraft Impact

F. Linder, Consultant, Lemgo, N.J. Krutzik, G. Winkel, Kraftwerk Union AG, Offenbach (Main), Fed.

Rep. Germany

Session J 10. Impulsive Load Analysis and Design

J 10/1* Evaluation of Hazards from Industrial Activities near Nuclear Power Plants. Deterministic and Probabilistic Studies A. Lannoy, Électricité de France, Direction des Etudes et Recher­

ches, Saint Denis, T. Gobert, Électricité de France, Direction de l'Equipement, Paris,

France

J 10/2 On the Dynamic Analysis of Axisymmetric Structures Considering Non­Axisymmetric Concentrated Masses K.­H. Schrader, Ruhr­Universität Bochum, Bochum, Α. Kaiser, Ingenieurbüro Dynamik spezieller Strukturen, Frank­

furt/Main, N.J. Krutzik, Kraftwerk­Union AG., Offenbach/Main, Fed. Rep. Ger­

many

J 10/4 Response of Containment Structures to Air Blast CA. Kot, P. Turula, Argonne National Laboratory, Argonne, Illinois,

U.S.A.

J 10/5 Response of an Embedded Reactor Containment to Underground Blast Loading Y. Kivity, D. Golan, Sigolev Ltd., Tel Aviv, Israel

J 10/6 Finite Element Analysis of Reactor Containments under Blast Loa­ding O.K. Kiciman, Middle East Technical University, Ankara, Turkey

J 10/7 Pressure Vessel Rupture and Resulting Pressure­Wave­Loading of Surrounding Concrete Structures Calculated with the PISCES ­2 DELK­Code V. Koch, TÜV­Baden, Mannheim, W. Pohl, Control Data GmbH, Frankfurt/Main, Fed. Rep. Germany

66

TABLE OF CONTENTS

Division K. SEISMIC RESPONSE ANALYSIS OF

NUCLEAR POWER PLANT SYSTEMS

K(a) Session K1. Ground Motion

K 1/1* Analyses on Various Parameters for the Simulation of Three­dimensional Earthquake Ground Motions M. Watabe, Building Research Institute, Ibaraki, M. Tohdo, Toda Construction Co., Ltd., Tokyo, Japan

K 1/2 Generation of Simulated Three­dimensional Earthquake Ground Motions M. Watabe, Building Research Institute, Ibaraki, 0. Chiba, M. Tohdo, Toda Construction Co., Ltd., Tokyo, Japan

K 1/3 Primary Variables Influencing Generation of Earthquake Motions by a Deconvolution Process I.M. Idriss, M.R. Akky, Woodward­Clyde Consultants, San Francis­

co, California, U.SA.

K 1/4 Phase Characteristics of Earthquake Accelerogram and Its Appli­cation

Y. Ohsaki, R. Iwasaki, I. Ohkawa, University of Tokyo, Tokyo, T. Masao, Nuclear Power Plant Division, Fujita Corporation, Tokyo,

Japan

K 1/5 Artificial Accelerograms for Multiaxial Earthquake Excitation P. Degen, Motor­Columbus Consulting Engineers, Inc., Baden,

Switzerland withdrawn

K 1/6 Input Criterion for Seismic Analysis of Nuclear Power Plants D.C. Gupta, PK. Agrawal, S. Singh, Sargent & Lundy Engineers,

Chicago, Illinois, U.S.A.

K Ml Hysteresis Behaviour of Soils and Rocks

T. Hueckel, Polish Academy of Sciences, Institute of Fundamental Technological Research, Warsaw, Poland

R. Nova, Politecnico di Milano, Milano, Italy

K 1/8 A Model for Soil Behavior under Monotonie and Cyclic Loading Conditions

Y.F. Dafalias, University of California, Davis, California, U.S.A.

K 1/9 On the Effects of Using Wide Range Earthquakes

S. Cecconi, V. Giuliano, L. Lazzeri, AMN S.pA., Genova, G. Pezzi, Università di Genova, Genova, Italy

K 1/10 A Class of Models for Identification and Simulation of Earthquake Ground Motions R.M. Oliver, K.S. Pister, University of California, Berkeley, Califor­

nia, U.S.A.

■ 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.

67

Session K 2. Risk Analysis I

K 2/1* Probabilistic Seismic Safety Study of an Existing Nuclear Power Plant R.P. Kennedy, R.D. Campbell, Engineering Decision Analysis

Company, Irvine, California, CA. Cornell, Massachusetts Institute of Technology, Cambridge,

Massachusetts, H.F. Perla, Pickard, Lowe and Garrick, Inc., Irvine, California,

USA. K 2/2 Probabilistic Approach of Reference Seismic Ground Motions

D. Costes, CE.A./CEN-DSN, Fontenay-aux-Roses, France K 2/3 Probabilistic Evaluation of the SSE Design Spectrum for a Nuclear

Power Plant Site: A Case Study R. Wheaton, A. Vaish, EDS Nuclear, Inc., San Francisco, California, C.B. Crouse, Fugro, Inc., Long Beach, California, R. Guzman, Consultant, Long Beach, California, U.S.A.

K 2/4 A Method for the Estimation of the Probability of Damage due to Earthquakes M.A.H.G. Alderson, UKAEA Safety and Reliability Directorate, Cul-

cheth, Warrington, U.K. K 2/5 Probability of Failure of Piping Designed to Seismically Induced

Emergency and Faulted Condition Limits M. Gorman, Case Western Reserve University, Cleveland, Ohio, J.D. Stevenson, J.D. Stevenson Consultants, Cleveland, Ohio,

U.S.A. K 2/6 On a Method of Evaluation of Failure Rate of Equipment and Pi­

pings under Excess-Earthquake Loadings H. Shibata, Institute of Industrial Science, University of Tokyo, To­

kyo, H. Okamura, University of Tokyo, Tokyo, Japan

K 2/7 KTA 2201 - Seismic Design Standards in the Federal Republic of Germany G. Philip, M. Bork, Kerntechnischer Ausschuß (KTA)-Geschäfts-

stelle, Köln, Fed. Rep. Germany K 2/8 The MCE (Maximum Credible Earthquake) - An Approach to Re­

duction of Seismic Risk G.J.K. Asmis, R.J. Atchison, Atomic Energy Control Board, Ottawa,

Ontario, Canada

Session K 3. Risk Analysis II

K 3/1 * An Overview of the Seismic Safety Margins Research Program R.D. Smith F.J. Tokarz, Lawrence Livermore Laboratory, Liver­

more, California, U.S.A. K 3/2 Systems Analysis Methods Used in the Seismic Safety Margins

Research Program G.E. Cummings, J.E. Wells, Lawrence Livermore Laboratory, Liver­

more, California, U.S.A.

68

K 3/3 Development of Seismic Input for Use in the Seismic Safety Mar­gins Research Program D.L. Bernreuter, D.H. Chung, Lawrence Livermore Laboratory, Li­

vermore, California, U.S.A. Κ 3/4 Expert Opinion Encoding in Seismic Hazard Analysis

OP. Mortgat, KW. Campbell, TERA Corporation, Berkeley, Cali­fornia,

D.L. Bernreuter, Lawrence Livermore Laboratory, Livermore, Cali­fornia, U.S.A.

Κ 3/5 Attenuation Relationships of Peak Ground Acceleration Versus Magnitude and Distance Considering Magnitude and Distance as Random Variables C. P. Mortgat, TERA Corporation, Berkeley, California, D.L. Bernreuter, Lawrence Livermore Laboratory, Livermore, Cali­

fornia, U.S.A. Κ 3/6 Soil Structure Interaction Analysis for the US NRC Seismic Safety

Margins Research Program J.J. Johnson, Lawrence Livermore Laboratory, Livermore, Califor­

nia, U.S.A. Κ 3/7 Major Structural Response Methods Used in the Seismic Safety

Margins Research Program CK. Chou, T.Y. Lo, V.N. Vagliente, Lawrence Livermore Laborato­

ry, Livermore, California, U.SA. Κ 3/8 Subsystem Response Determination lor the US NRC Seismic Sa­

fety Margins Research Program J.J. Johnson, Lawrence Livermore Laboratory, Livermore, Califor­

nia, U.S.A. Κ 3/9 Definition of Component and Structural Fragility for Use in the

Seismic Safety Margins Research Program R.G. Dong, Lawrence Livermore Laboratory, Livermore, California,

USA. Κ 3/10 Reserve Seismic Capacity Determination of a Nuclear Power Plant

Braced Frame with Piping T.A. Nelson, Lawrence Livermore Laboratory, Livermore, Califor­

nia, U.S.A.

Session Κ 4. Design Concepts

Κ 4/1 * On Fundamental Concept of Anti-Earthquake Design of Equipment and Pipings H. Shibata, Institute of Industrial Science, University of Tokyo, To­

kyo, M. Kato, Japan Atomic Power Company, Tokyo, Japan

K 4/2 Integrated Structural Design of Nuclear Power Plants for High Seismic Areas P.J. Rieck, Gilbert Associates, Inc., Reading, Pennsylvania, U.S.A.

69

K 4/3 Concepts for Seismic Response Attenuation of Nuclear Power Plant Containments R.P. Kennedy, Engineering Decision Analysis Company, Irvine, Ca­

lifornia, P.J. Richter, Fluor Engineers and Constructors, Inc., Irvine, Cali­

fornia, W.A. von Riesemann, Sandia Laboratories, Albuquerque, New Mex­

ico, U.S.A. K 4/4 Alternative Structural Systems for High Density Fuel Storage Racks

in Existing Facilities J.W. Reed, F.A. Webster, Engineering Decision Analysis Co., Inc.,

Palo Alto, California, P.C. Sun, Nuclear Energy Operation, General Electric Co., San

Jose, California, U.SA. K 4/5 Considerations in the Design of Nuclear Power Plants in High Seis­

mic Regions. Part 1: Station Arrangements. Part 2: Component Qualification A.K. Banerjee, M.B. Stetson, CF. Reeves, Sfone & Webster

Engineering Corporation, Boston, Massachusetts, U.S.A. K 4/6 An Investigation into Seismic Design Feasibility of Pool-Type

LMFBR's N. Pal, M. Dostal, General Electric Company, Advanced Reactor

Systems Department, Sunnyvale, California, U.SA. K 4/7 Probabilistic Seismic Fluid-Structure Interaction of Floating

Nuclear Plants Platforms M. Arockiasamy, P.V. Thangam Babu, D.V. Reddy, Memorial Uni­

versity of Newfoundland, St. Johns, Newfoundland, Canada

Session K 5. Soil-Structure Interaction I

K 5/1* Travelling Wave Effects in Soil-Structure Interaction J.P. Wolf, P. Obernhuber, Electrowatt Engineering Services Ltd.,

Zürich, Switzerland K 5/2 Seismic Input for Soil Structure Interaction Analysis

E. Berger, Dames & Moore, Inc., San Francisco, California, H.B. Seed, University of California, Berkeley, California, U.S.A., J.D. Renard, Electrobel S.A., Bruxelles, Belgium

K 5/3 Soil-Structure Interaction: Modeling Effects on Structural Re­sponse P. Arnold, N.J. Krutzik, Kraftwerk Union AG, Offenbach, Fed. Rep.

Germany K 5/4 Investigation of the Treatment of Damping in Soil-Structure Inter­

action Analysis H. Kamil, G. Kost, R. Sharpe, Engineering Decision Analysis Com­

pany, Inc., Palo Alto, California, U.S.A.

70

K 5/5 Comparison of Soil­Structure Interaction by Different Ground Models T. Takemori, Y. Kuwabara, Y. Ogiwara, A. Suwabe, Taisei Corpo­

ration, Tokyo, K. Tanaka, Kyushu Electric Power Company, Kyushu, Japan

Κ 5/6 Torsional Structural Response from Free­Field Ground Motion P.C. Lam, General Motors Institute, Detroit, Michigan, R.J. Scavuzzo, The University of Akron, Akron, Ohio, U.S.A.

Κ 5/7 Seismic Design Method for Arbitrary Propagating Waves M.M. Ettouney, J.A. Brennan, A.A. Agüero, Burns and Roe, Inc.,

Woodbury, New York, U.S.A.

Session Κ 6. Soil-Structure Interaction II

Κ 6/1* Soil Structure Interaction Analyses by Different Methods G. Waas, W. Weber, Hochtief AG, Frankfurt am Main, Fed. Rep.

Germany

Κ 6/3 Dynamic Interaction of Adjacent Structures Founded on Layered Soil G. Waas, Hochtief AG, Frankfurt am Main, Fed. Rep. Germany

Κ 6/4 The Influence of Uplift and Sliding Nonlinearities on Seismic Re­sponse of a Small Test Reactor Building L.J. Cofer, H. Kamil, R.L. Sharpe, Engineering Decision Analysis

Company, Inc.. Palo Alto, California, D. Hoggatt, General Electric Company, Vallecitos Nuclear Center,

Pleasanton, California, U.S.A.

Κ 6/5 Structure­to­Structure Interaction Analysis for a Nuclear Power Plant C. Mueller, H. Furrer, Motor Columbus Consulting Engineers, Inc.,

Baden, Switzerland

Κ 6/6 Building­Soil­Building Interaction in Seismic Analysis of Nuclear Power Plants A. Del Grosso, D. Stura, C. Vardanega, Università di Genova,

Genova, Italy Κ 6/7 The Finite Element Complex Response Method for Solving Prob­

lems of Embedded Multiple Structures

J.V. Parker, K.M. Ahmed, Nuclear Power Company (Risley) Limited, Risley, Warrington, Cheshire, U.K.

Κ 6/8 Investigation of the Influence of Interaction of Two Adjacent Struc­tures on Their Responses A. Gantayat, H. Kamil, G. Kost, Engineering Decision Analysis

Company, Palo A/to, California, U.SA., N. Krutzik, Kraftwerk Union AG, Offenbach, D.H. Rutherford, Engineering Decision Analysis Company, Frank­

furt (Main), Fed. Rep. Germany

Κ 6/9 Nonlinear Analysis of a Deeply Embedded Power Plant Building Subjected to Earthquake Load S.N. Mukherjee, Brown, Boveri & Cie, Baden, Switzerland

71

Session K 7. Underground Structures

K 7/1 * Earthquake Response of Nuclear Reactor Building Deeply Embed­ded in Soil T. Masao, Y. Takasaki, Fujita Corporation, Yokohama, S. Yamamoto. Y. Koori, Chiyoda Chemical Engineering & Con­

struction Corporation, Kawasaki, Japan K 7/2 Seismic Response Comparisons for an Embedded High Tempera­

ture Gas-Cooled Reactor (HTGR) on a High Seismic Site W. Schlafer, III, D. Tow, General Atomic Company, San Diego, Cali­

fornia, J.J. Johnson, Lawrence Livermore Laboratory, Livermore, Califor­

nia, U.S.A. K 7/3 Seismic Stresses in Buried Piping of Arbitrary Configuration

J.J. Deans, J.H.K. Tang, Ontario Hydro, Toronto, Ontario, Canada K 7/4 Seismic Design of Long Underground Structures

S.N. Pagay, F. Loceff, Westinghouse Electric Corporation, PWR System Division, Pittsburgh, Pennsylvania, U.S.A.

K 7/5 Analytical and Experimental Investigation of the Dynamic Re­sponse of Underground Nuclear Power Plants G.E. Howard, P. Ibáñez, ANCO Engineers, Inc., Santa Monica,

California, U.SA. K 7/6 Seismic Response Analysis for a Deeply Embedded Nuclear Power

Plant W.W.H. Chen, Bechtel National, Inc., San Francisco, California, M. Chatterjee, Bechtel Power Corporation, San Francisco, Califor­

nia, S.M. Day, Systems, Science, and Software, La Jolla, California,

U.SA. K 7/7 Inelastic Seismic Analysis of a Deeply Embedded Reinforced Con­

crete Reactor Building M. Celebi, M. Chatterjee, Bechtel Power Corporation, San Fran­

cisco, California, K. Mark, Bechtel National, Inc., San Francisco, California, U.S.A.

K 7/8 Experimental and Analytical Studies of a Deeply Embedded Reactor Building Model Considering Soil-Building Interaction (Part I) H. Tanaka, Tokyo Electric Power Co., Ltd., Tokyo, T. Ohta, S. Uchiyama, Kajima Institute of Construction Technology,

Tokyo, Japan K 7/9 Seismic Response of the ' Cut-and-Cover' Type Reactor Con­

tainments Considering Nonlinear Soil Behavior H. El-Tahan, D.V. Reddy, Memorial University of Newfoundland, St.

John's, Newfoundland, Canada

72

K(b) Session K 8. Response of Structures

K 8/1* The Uncoupling Criteria for Subsystem Seismic Analysis C. Chen, Gilbert/Commonwealth Companies, Reading, Pennsyl­

vania, U.S.A.

K 8/2 Towards Safe and Economic Seismic Design of Cooling Towers of Extreme Height W.E. Krätzig, K. Meskouris, Ruhr­Universität Bochum, Bochum,

Fed. Rep. Germany

K 8/3 Response of a Nonlinear System to Various Spectral Excitation Time Decompositions J. Curreri, P. Bezler, B. Koplik, H. Goradia, Brookhaven National

Laboratory, Upton, New York, U.S.A.

K 8/4 Critical Seismic Response of Nuclear Reactors R.F. Drenick, P.C. Wang, C.B. Yun, A.J. Philippacopoulos, Poly­

technic Institute of New York, Brooklyn, New York, U.S.A.

K 8/5 Nonlinear Analysis of a BWR Reactor Building Subjected to Both Thermal and Earthquake Loadings K. Muto, T. Tsugawa, Muto Institute of Structural Mechanics, Ka­

jima Corp., Tokyo, S. Aihara, K. Ujiie, Kajima Corporation, Tokyo, Japan

K 8/6 Fatigue Analysis Method for Seismic Structural Response A. Kurosaki, M. Kozeki, Mitsui Engineering and Shipbuilding Co.,

Ltd., Tokyo, Japan

K 8/7 Seismic Response of a Structure Subjected to Rotational Base Ex­citation

W.H. Guilinger, V.N. Shah, G.J. Böhm, Westinghouse Electric Cor­poration, PWR Systems Division, Pittsburgh, Pennsylvania, U.S.A.

K 8/8 Combination of Torsional, Rotational and Translational Responses in the Seismic Analysis of a Nuclear Power Plant A. Morrone, Westinghouse Electric Corporation, Advanced Reac­

tors Division, Madison, Pennsylvania, G.B. Sigal, Burns and Roe, Inc., Oradell, New Jersey, U.S.A.

K 8/9 Mutual Pounding of Adjacent Structures During Earthquakes J.P. Wolf, P.E. Skrikerud, Electrowatt Engineering Services Ltd.,

Zürich, Switzerland

Session K 9. Floor Response Analysis

K 9/1* Equipment Response Spectra for Nuclear Power Plant Sys­tems

J.L. Sackman, J.M.Kelly, University of California, Berkeley, Califor­nia, U.S.A.

Κ 9/2 On the Seismic Design Spectra for Heavy Components and Com­parisons with the Usual FRS Techniques S. Cecconi, V. Giuliano, L. Lazzeri, AMN S.pA., Genova, Italy

Κ 9/3 On Upperbound Instructure Response Spectra T.S. Atalik, Bechtel Espana, S.A., Madrid, Spain

73

K 9/4 Floor Response Spectra Considering Elasto-Plastic Behaviour of Nuclear Power Facilities T. Kawakatsu, The Kansai Electric Power Company, K. Kitade, Mitsubishi Atomic Power Industries, Inc., Tokyo, T. Takemori, Y. Kuwabara, Y. Ogiwara, Taisei Corporation, Tokyo,

Japan Κ 9/5 Direct Methods to Calculate Seismic Floor Response Spectra

F. Jeanpierre, M. Livolant, F. Roullier, CEA./CEN-Saclay DEMT, Gif-sur-Yvette, France

Session Κ 10. Response of Piping and Equipment I

Κ 10/1* Effect of Energy Absorbing Supports on Seismic Pipe Stresses G.H. Powell, D.G. Row, University of California, Berkeley, Califor­

nia, USA. Κ 10/2 Comparison of Multiple Support Excitation Solution Techniques

for Piping Systems K.-R. Leimbach, Consultant, Bochum-Linden, Η.P. Sterkel, Kraftwerk Union AG, Offenbach (Main), Fed. Rep.

Germany Κ 10/3 ,.Missing Mass" Correction in Modal Analysis of Piping Systems

G.H. Powell, University of California, Berkeley, California, U.S.A. Κ 10/4 Residual Load Method for Modal Analysis of Piping Systems Sub­

jected to Seismic Excitation G. Krause, Brown, BoveriS Cie. AG, Mannheim, Fed. Rep. Germany

Κ 10/5 Beam Versus Shell Seismic Analysis of Large Diameter Thin Walled LMFBR Piping N. Pal, General Electric Company, Advanced Reactor Systems De­

partment, Sunnyvale, California,U.S.A. S. Mizuno, Hitachi Ltd., Hitachi City, Japan

Κ 10/6 Design of Prequalif ied Support Systems Subjected to Dynamic Lo­ads R.D. Raheja, F.L.Cho, A.E. Meligi, Sargenta Lundy Engineers, Chi­

cago, Illinois, U.S.A. K 10/7 Relation Between Clearance of the Seismic Restraint for Nuclear

Power Piping System and Vibration Characteristics T. Yoshinaga, N. Gotoh, Hitachi Works, Hitachi Ltd., Ibaraki-ken,

Japan K 10/9 A Simplified Aseismic Design Procedure for Piping Systems

N. Pal, General Electric Company, ARSD, Sunnyvale, California, U.S.A.

S. Mizuno, Hitachi Ltd., Hitachi City, Japan

74

Session K 11. Response of Piping and Equipment II

K 11/1 * Structural Damping Values as a Function of Dynamic Response Stress and Deformation Levels J.D. Stevenson, J.D. Stevenson Consultants. Cleveland, Ohio,

U.S.A. K 11/2 Arguments in Favour of Structures, Systems and Equipment

Seismic Qualification by Analysis R.B. Cambien, J.C. Hennart, Westinghouse Nuclear Europe, Bru­

xelles, Belgium K 11/3 Investigation on the Design Damping Values for Seismic Analy­

sis of Nuclear Power Plant Piping Systems H. Shibata, Institute of Industrial Science, University of Tokyo, To­

kyo, T. Ikeda, Tokyo Electric Power Co., Inc., Tokyo, T. Nakatogawa, Mitsubishi Atomic Power Industries, Inc., Tokyo, K. Shiraki, Takasago Technical Institute, Mitsubishi Heavy Indu­

stries, Ltd., Takasago,Hyogo-ken, T. Niino, Hitachi Works, Hitachi, Ltd., Ibaraki-ken, K. Gunyasu, Tokyo Shibaura Electric Co., Ltd., Tokyo, Japan

K 11/4 On Seismically Induced Vibrations of Pressure Vessels with Cu­touts and Cracks H.T. Tezduyar.T. Ariman, L.H.N. Lee, University of Notre Dame, No­

tre Dame, Indiana, U.S.A. K 11/5 Nonlinear Transient Dynamic Response of Pressure Relief Valves

for a Negative Containment System T.S. Aziz, Acres, Inc., Toronto, Ontario, CG. Duff, Atomic Energy of Canada Limited, Sheridan Park Re­

search Community, Mississauga, Ontario, J.H. Tang, Ontario Hydro, Toronto, Ontario. Canada

K 11/6 Seismic Response Analysis of Nuclear Power Plant Auxiliary Me­chanical Equipment C.-W. Lin, Westinghouse Electric Corporation, PWR Systems Divi­

sion, Pittsburgh, Pennsylvania, U.S.A. K 11/7 Seismic Interaction Effects for Steam Generators in CANDU 600

MWe Nuclear Power Plants T.S. Aziz, Acres, Ltd., Toronto, Ontario, CG. Duff, Atomic Energy of Canada Limited, Sheridan Park Re­

search Community, Mississauga, Ontario, Canada K 11/8 Coupled Lateral-Torsional Response of Equipment Mounted in

CANDU Nuclear Power Plants M.F. Ishac, Ontario Hydro, Toronto, Ontario, A.C. Heidebrecht, McMaster University, Hamilton, Ontario, Canada

K 11/9 Seismic Analysis of Category I Crane Structures T.H. Liu, F. Loceff, P.H. Anderson, Westinghouse Electric Corpo­

ration, Nuclear Technology Division, Pittsburgh, Pennsylvania, USA.

K 11/10 Seismic Design of Cableways: A CAD Approach L. Lazzeri, M. Agrone, P.P. Strona, AMN S.pA., Genova, Italy

K 11/11 Seismic and Accident Analysis of Electrical Machinery G. Filippi, L. Lazzeri, AMN S.pA., Genova R. Pagano, E. Vivoda, Ansaldo, Monfalcone, Italy γ§

Session K 12. Reactor Core and Fluid Related Structures

K 12/1 A Three-Dimensional Test Program for the Nonlinear Dynamic Be­havior of an HTGR Core J. Curreri, M. Reich, B. Koplik, P. Bezler, M. Subudhi, Brookhaven

National Laboratory, Upton, New York, U.S.A. withdrawn K 12/2 Two-Dimensional Vibration Test and Its Simulation Analysis for a

Horizontal Slice Model of HTGR Core K. Muto, S. Motohashi, Muto Institute of Structural Mechanics,

Inc., Tokyo, K. Kuroda, Electric Power Development Co., Tokyo, Japan

K 12/3 Forced Vibration Test of 1/5 Scale Model of CANDU Core K. Muto, Muto Institute of Structural Mechanics, Inc., Tokyo, K. Kuroda, Y. Kasai, Electric Power Development Company, Tokyo,

Japan K 12/4 Seismic Analysis of the Reactor Assembly of a 1000 MWe-LMFBR

Pool Reactor C.C. Yang, S. Kraus, General Electric Company, Advanced Reactor

Systems Department, Sunnyvale, California, U.S.A. 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.U. Ahmed, D. Ma, Argonne National Laboratory, Argonne, Illinois,

U.S.A. K 12/6 A Three-Dimensional Computer Code for the Nonlinear Dynamic

Response of an HTGR Core M. Subudhi, L. Lasker, B. Koplik, J. Curreri, H. Goradia, Brookha­

ven National Laboratory, Upton, New York, U.S.A. K 12/7 Evaluation of Seismic Movements of a Pebble Bed Reactor Core as

Basis for Shaking Experiments H.-J. Glöckner, F. Kemter, Hochtemperatur-Reaktorbau GmbH,

Mannheim, G. Schmidt, Hochtemperatur-Reaktorbau GmbH, Jülich, Fed. Rep.

Germany K 12/8 Explicit Evaluation of the Apparent Fluid Mass at the Vibration of

Fluid Filled Cylindrical Tanks D.F. Fischer, VÖEST-Alpine AG, Linz, Austria

K 12/9 Experimental Seismic Test of Fluid Coupled Co-Axial Cylinders M. Chu, J.F. Lestingi, University of Akron, Akron, Ohio S.J. Brown, Babcock Et Wilcox Co., Nuclear Equipment Division,

Barberton, Ohio, U.SA. K 12/10 Evaluation of Fluid Sloshing Effects in Large Suspended Flexible

Tanks J.W. Leonard, Illinois Institute of Technology, Chicago, Illinois, H.U. Ahmed, Argonne National Laboratory, Argonne, Illinois, U.S.A.

76

K 12/11 Dynamic Pressures in Annulus-Shaped Pressure Suppression Pools of Boiling Water Reactors Generated by Earthquake Ground Motions B. Bedrosian.M. Ettouney.J. Brennan, Burns and Roe, Inc., Wood­

bury, New York, U.SA. Κ 12/12 Dynamic Analysis of Storage Racks for Spent Fuel Assemblies

G. Habedank, L.M. Habip, H. Swelim, Kraftwerk Union AG, Frank­furt am Main, Fed. Rep. Germany

Session Κ 1 3 . Dynamic Test ing a n d Qual i f icat ion

Κ 13/1* Tests and Calculation of the Seismic Behaviour of Concrete Structures J. Gauvain, A. Hoffmann, C. Jeandidier, M. Livolant, CEA.I

CEN-Saclay DEMT, Gif-sur-Yvette, France Κ 13/2 Low Level Earthquake Testing of the HDR: Comparisons of

Calculations and Measurements for the Reactor Building P. Jehlicka, L. Malcher. Kernforschungszentrum Karlsruhe, Karls­

ruhe, H. Steinhilber, Battelle-lnstitut e.V., Frankfurt am Main, Fed. Rep.

Germany Κ 13/3 Low Level Earthquake Testing of the HDR: Comparisons of

Calculations and Measurements for Mechanical Equipment P. Jehlicka, L. Malcher, Kernforschungszentrum Karlsruhe, Karls­

ruhe, H. Steinhilber, Battelle-lnstitut e.V., Frankfurt am Main, Fed. Rep.

Germany

Κ 13/4 Forced Vibration Test of BWR Type Nuclear Reactor Buildings Considering Through Soil Coupling between Adjacent Build­ings N. Mizuno, I. Moribe, N. Sugiyama, Chubu Electric Power Com­

pany, Nagoya, Y.Tsushima, H. Kushida, T. Tamaki, Takenaka Technical Research

Laboratory, Tokyo, Japan Κ 13/5 Seismic Qualification of General Electric Test Reactor Safety-Re­

lated Valves CA. Kircher, J.W. Reed, Engineering Decision Analysis Company,

Palo Alto, California, D. Hoggatt, General Electric Company, Vallecitos Nuclear Center,

Pleasanton, California, U.S.A. Κ 13/6 Assessment of Seismic Safety for Components of the THTR-300

M We by Shake Tests G. Neubrech, Hochtemperatur-Reaktorbau GmbH, Mannheim,

Fed. Rep. Germany wi thdrawn Κ 13/7 Field Vibration Test Results and Design for Reactor Coolant Piping

Systems of ATR ,,FUGEN" T. Igarashi, K. Arai, Mitsubishi Atomic Power Industries, Inc., Omiya

City, K. Fujita, Takasago Technical Institute, Mitsubishi Heavy Indu­

stries, Inc., Takasago, Hyogo Prefecture, Japan

11

K 13/8 Vibrational Characteristics of Primary Reactor Coolant System K. Shiraki, K. Fujita, Mitsubishi Heavy Industries, Ltd., Takasago, K. Kitade, Mitsubishi Atomic Power Industries, Ltd., Tokyo, T. Kawakatsu, Kansai Electric Power Company, Osaka, Japan

Κ 13/9 Experimental and Analytical Studies on Aseismic Design of Ven­tilation Ducts

K. Suzuki, H. Hagiwara, H. Tsuchiya, M. Shimizu, Taisei Corpora­tion, Tokyo, Japan

Κ 13/10 The Results of Dynamic Tests on 1:10 Model of Containment for Nuclear Reactor

K. Donten, M. Knauff, A Sadowski, W. Scibak, Politechnika War­szawska, Warsaw, Poland

Κ 13/12 Nonlinear Experimental Response of Semi­Scale Model of Nuclear Power Plant Structures to Simulated Earthquake­Like Ground Mo­tion

C. Chan, Electric Power Research Institute, Palo Alto, California, C.J. Higgins, University of New Mexico, Albuquerque, New Mexico, G.E. Howard, P. Ibáñez, ANCO Engineers, Inc., Santa Monica,

California, U.SA.

78

TABLE OF CONTENTS

Division L. MATERIALS MODELING AND INELASTIC

ANALYSIS OF METAL STRUCTURES

Session L 1. Advanced Theories I

L 1/1* Coupling Phenomena in Thermoplasticity Th. Lehmann, Ruhr­Universität Bochum, 3ochum, Fed. Rep. Ger­

many

L 1/3' Structural Collapse due to Plastic Instability V. Tvergaard, Technical University of Denmark, Lyngby, Den­

mark A. Needleman, Brown University, Providence, Rhode Is/and,

USA.

L 1/4* Tensor Function Approach to Constitutive Equations of Inelasticity S. Murakami, Nagoya University, Chikusa­ku, Nagoya, Japan,

L 1/5 Flow and Fracture of Inelastic Materials ­ Application to Modern Reactor Technology P. Perzyna, Polish Academy of Sciences, Institute of Fundamental

Technological Research, Warsaw, Poland

L 1/6 Order, Heat, Intrinsic Dissipation and Inelastic Analysis J.M. Boisserie, Electricité de France, Service Informatique et

Mathématiques Appliquées, Chatou, P. Guelin, Université de Grenoble, Grenoble, France

L 11l On History Dependence of Stress­Strain Diagrams and Creep Cur­ves under Variable Repeated Loading D.A. Gokhfeld, O.S. Sadakov, M.E. Martynenko, Chelyabinsk Poly­

technical· Institute, Chelyabinsk, U.S.S.R.

Session L 2. Advanced Theories II

L 2/1 * Reliability of Elastic­Plastic Structures

C. Gavarini, Università di Roma, Roma, Italy

L 2/2* Cyclic Loading on Elastic, Viscoplastic Structures Z. Mroz, Polish Academy of Sciences, Institute of Fundamental

Technological Research, Warsaw, Poland

L 2/3* High­Temperature Design of Elastic­Plastic Structures

D.A. Gokhfeld, Chelyabinsk Polytechnical Institute, Chelyabinsk: U.S.S.R.

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,

79

L 2/4* Constitutive Modelling in Plasticity J. Kratochvil, Czechoslovak Academy of Sciences, Institute of Solid

State Physics, Prague, Õ.S.S.R. L 2/6 A Nonlinear Endochronic Theory of Cyclic Plastic Hardening and

Softening W. Kosinski, T. Nashiro, Polish Academy of Sciences, Institute of

Fundamental Technological Research, Warsaw, Poland

Session L 3. Methods I

L3/1* Mathematical Programming Methods in Engineering Plasticity G. Maier, Politecnico di Milano, Milano, Italy, J. Munro, Imperial College of Science and Technology, London,

U.K. L 3/2* Inelastic Analysis of Structures with Applications to Cyclic Load­

ings J. Zarka, J.J. Engel, G. Inglebert, C.N.R.S., Ecole Polytechnique,

Palaiseau, France L 3/3 Shakedown Analysis by Displacement Method and Equilibrium Fi­

nite Element H. Nguyen Dang, Université de Liège, Liège, L. Palgen, F.N.R.S., Bruxelles, Belgium

L 3/4 Local Bounds on Dissipation Energy in Shakedown Theory C. Polizzotto.C. Mazzarella, T. Panzeca, Università di Palermo, Pa­

lermo, Italy L 3/5 Finite Deformation, Elastoplastic Incrementai Finite Element Ana­

lysis of Ductile Metal Structures W.-H. Chen, National Tsing Hua University, Hsinchu, Taiwan, Re­

public of China L 3/6 Viscous Growth of Thin Pressurized Shells Subjected to Thermal

Cycling R.O Hibbeler, University of Southwestern Louisiana, Lafayette,

Louisiana, U.SA.

Session L 4. Methods II

L 4/1* Elastic-Plastic Analysis Methods for Piping Systems J.T. Boyle, J. Spence, University ofStrathclyde, Glasgow, Scotland,

U.K. L 4/2 A Damage Postulate for Nonproportional Cyclic Plasticity

B. Leis, Battelle Columbus Laboratories, Columbus, Ohio, J.H. Laflen, General Electric Company, Cincinnati, Ohio, U.SA.

L4/3 Improved Boundary-Integral Equation Method for Time-Depen­dent Inelastic Deformation in Metals M. Morjaria, S. Mukherjee, Cornell University, Ithaca, New York,

U.S.A.

80

L 4/5 Fundamental Concepts in the Reference Stress Method for Creep Design J.T. Boyle, University of Strathclyde, Glasgow, Scotland, U.K.

L 4/6 A Finite Element Formulation for Large Elastic-Plastic Deforma­tions P.CM. Gortemaker, C. de Pater, Twenfe University of Technology,

Enschede, The Netherlands L4/7 Inelastic Analysis of Piping Systems: A Beam-Type Method for

Creep and Plasticity R.L Roche, A. Hoffmann, A. Millard, CEA./CEN-Saclay DEMT,

Gif-sur-Yvette, France L 4/8 Dynamic Plastic Buckling of Shells: a Reconsideration of the

Vaughan-Florence Analysis G. Horvay, F.D. Stockton, University of Massachusetts, Amherst,

Massachusetts, U.SA. M.A. Veluswami, Indian Institute of Technology, Madras, India,

Session L 5. Fracture, Rupture

L 5/1 Predictions of Creep Behavior of Some Stainless Steels on the Basis of Short-Term Tensile Properties T. Bui-Quoc, A. Biron, Ecole Polytechnique, Montréal, Québec,

Canada L 5/1 a* Approximate Methods of Analysis for Creep Rupture

D.A.Hayhurst, University of Leicester, Leicester, U.K. L5/1b* Damage Modelling for Prediction of Plastic and Creep Fatique

Failure in Structures J. Lemaitre. Université P. and M. Curie (Paris VI), Cachan, France

L 5/2 Stress Intensification and Creep Rupture J. Henderson, F.R. Ferguson, National Engineering Laboratory,

East Kilbride, Glasgow, Scotland, U.K. L 5/3 Experimental Tests on Ratchet of Tubular Specimens (Torsion and

Tension) - Use for Material Characterization J. Lebey, R. L. Roche, P. Cousseran, CEA. I CEN-Saclay DEMT,

Gif-sur- Yvette, France. L 5/4 Strain Analyses of Nonlinear Crack Behavior at Elevated Tempera­

ture by Finite Element Method and Moiré Topographical Method T. Aizawa, G. Yagawa, Y. Ando, University of Tokyo, Japan

L 5/8 A Model of Quasi-Static Crack Growth ina Double Cantilever Beam at Elevated Temperature LS. Fu, Ohio State University, Columbus, Ohio, U.S.A.

81

Session L 6. Codes and Criteria

L 6/1* Development of Inelastic Design Criteria and Codes W.J. O'Donnell, J.S. Porowski, O'Donnell & Associates, Inc., Pitts­

burgh, Pennsylvania, U.S.A. L 6/3 High Temperature Design Evaluations by a Creep Ratchetting

Theory H.U. Ahmed, Argonne National Laboratory, Argonne, Illinois, U.S.A.

L 6/4 Requirements on the Mechanical Design of Reactor Systems Ope­rating at Elevated Temperature H. Schulz, M. Glahn, Gesellschaft für Reaktorsicherheit, Köln, Fed.

Rep. Germany L 6/5 Rules for the Analysis of Mechanical Structures at Elevated Tem­

peratures 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-lez-

Durance, France L 6/6 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 Thermoviscoplasticity Based on Total Strain and Overstress E. Krempl, E.P. Cernocky, M.C.M. Liu, Rensselaer Polytechnic In­

stitute, Troy, New York, U.S.A. L 7/2 Effect of Past Loading on the Current Stress of Rigid Plastic

Materials Y.S. Lee, G.J. Böhm, S.A. Swamy, Westinghouse Electric Corpo­

ration, Pittsburgh, Pennsylvania, U.SA. L7/3 Constitutive Equations of Viscoplasticity for Neutron Irradiated

Mild Steel R.B. Pecherski, Polish Academy of Sciences, Institute of Funda­

mental Technological Research, Warsaw, Poland L 7/4 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, Gaines­

ville, Florida, U.S.A. see C 3 /13 L7/6 Slip Theory of Creep Deformation of Face-Centered-Cubic Poly-

crystalline 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.

L 7/7 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.

82

L 7/8 Low Cycle Fatigue of Steels for Nuclear Pressure Vessels in Hot Water C. Gamier, G. Kowalczuk, R. Roche, CEA./CEN­Saclay DEMT,

Gif­sur­ Yvette, Β. Barrachin, IPSN, Paris, France

Session L 8. Applications I

L 8/1 Creep Collapse of a Cylindrical Shell Subjected to External Pres­sure at High Temperature K. Nagato, N. Takikawa, Kawasaki Heavy Industries, Ltd., Tokyo,

Japan

L 8/2 Creep Deflection Analysis of Fuel Channels in CANDU Nuclear Re­actors M.J. Pettigrew, S.B. Lambert, Atomic Energy of Canada Limited,

Chalk River Nuclear Laboratories, Chalk River, Ontario, Canada

L 8/3 Nonlinear, Dynamic, Plastic Component­Support Analysis W. Elfmann, U. Heeschen, G. Müller, Kraftwerk Union AG, Erlan­

gen, Fed. Rep. Germany

L 8/4 Viscoplastic Axisymmetrical Buckling of Spherical Shell Subjected to Radial Pressure Impulse W. Wojewódski, P. Lewinski, Politechnica Warszawska, Warsaw,

Poland

L 8/5 Some Design Aspects of Duplex Tubing J.M. Chern, D.H. Pai, Foster Wheeler Energy Corporation, Living­

ston, New Jersey, U.S.A.

L 8/6 Creep Collapse of Non­Uniform Circular Tubes Subjected to Exter­nal 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 Applications of Endochronic Plasticity in the Dynamic Finite Ele­ment Analysis of Structures R.A. Valentin, B.J. Hsieh, H.C Lin, Argonne National Laboratory,

Argonne, Illinois, U.S.A.

L 9/4 Influence of Weldments in the High Temperature Low Cycle Fati­gue Resistance of AISI 304 and 316 Stainless Steel Tubular Ele­ments C Carmignani, E. Manfredi, E. Vitale, Università di Pisa, Pisa, Italy

L 9/5 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.

L 9/6 Plastic Deformation of Steel Shock Absorbing Structures D. Aquaro, G. Forasassi, Università di Pisa, Pisa, Italy

83

L 9/8 Analysis and Design of Containment Liner/Anchorage System T.H. Liu, F. Loceff, W.E. Moore, Westinghouse Electric Corpora­

tion, Pittsburgh, Pennsylvania, U.SA. L 9/9 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 Funda­

mental 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., Pitts­

burgh, 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 Corpora­

tion, Tokyo, Japan L 10/7 Plastic Frames: Reduction of the Kinematical Inequality and Opti­

mization P. Brousse, Université de Paris VI, Paris, France

Session L 11. 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 Aéro­

spatiales, 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

L 11 /5 Life Prediction of Simple Structures Subject to Cyclic Primary and Secondary Loading Resulting in Creep and Plasticity N.R. Otter, R.T. Jones, GEC Power Engineering Limited, Whet­

stone, Leicester, U.K. L 11 /6 The Behaviour of Plates Subjected to Steady Mechanical Load and

Rapid Thermal Transients on Both Surfaces A.M. Goodman, J. Phillips, CEGB, Berkeley Nuclear Laboratories,

Berkeley, Gloucestershire, U.K. L 11/7 Neutral and Shakedown Domains of Circular Plates Subjected to

Cycles of Pressure and Temperature Z. Waszczyszyn, E. Pabisek, Technical University of Cracow, Kra­

kow, Poland L 11/8 Simplified Methods of Inelastic Analysis for Components Operat­

ing within the Creep Range R.A. Ainsworth, I.W. Goodall, CEGB, Berkeley Nuclear Laborato­

ries, Berkeley, Gloucestershire, U.K. L 11/9* Probabilistic Methods in Plastic Structural Analysis

G. Augusti, Università degli Studi di Firenze, Firenze, Italy

Session L 12. Experiments I

L 12/1 Creep Buckling and Instability of Circular Cylindrical Shells in Axial Compression S. Murakami, E. Tanaka, Nagoya University, Chikusa-ku, Nagoya,

Japan L 12/2 Inelastic Buckling Analysis, Experimental Tests on Vessel Heads

M. Alix, R.L. Roche, CEA./CEN-Saclay DEMT, Gif-sur-Yvette, France

L 12/3 Time Dependence in Biaxial Yield of Type 316 Stainless Steel at Room Temperature J.R. Ellis, D.N. Robinson, CE. Pugh, Oak Ridge National Labora­

tory, Oak Ridge, Tennessee, U.S.A. L 12/4 High Temperature Low Cycle Fatigue Damage Analysis of Welded

Stainless Steel Tubular Elements A. del Puglia, Università di Florence, Florence E. Manfredi, Università di Pisa, Pisa, R. Matera, G. Piatti Commission of the European Communities,

J.R.C. Ispra Establishment, Ispra, Italy L12/5 Yielding of 6061-T6 Aluminum Tubings Under Dynamic Biaxial

Loadings D.H.Y. Ng, L.H.N. Lee, University of Notre Dame, Notre Dame, In­

diana, U.S.A. L12/6 Inelastic Stress-Strain Relationships for the AISI 310 Stainless

Steel in the Temperature Range 20°-900°C S. Matteazzi, G. Bernasconi, Politecnico di Milano, Milano, G. Piatti, Commission of the European Communities, J.R.C. Ispra

Establishment, Ispra, Italy

85

L 12/7 Creep-Fatigue Interaction on 1.4948 Austenitic Stainless Steel, In­cluding Irradiation Effects R. Schmitt, W. Scheibe, K. Anderko, Kernforschungszentrum

Karlsruhe, Karlsruhe, Fed. Rep. Germany L 12/8 Low-Cycle Fatigue Behaviours of 304 Stainless Steel Piping El­

bows at Elevated Temperature K. lida, University of Tokyo, Tokyo, Y. Ito, Y. Fukuda, Hitachi Research Laboratory. Hitachi Ltd., Hita-

chi-shi, Ibaragi, M. Ohsawa, Hitachi Ship Building and Engineering Ltd., Sakai-shi,

Osaka, Japan L 12/9 Plastic Flow of the Perforated Materials with Square Penetration

Pattern A. Litewka, E. Rogalska, Technical University of Poznan, Poznan,

Poland

Session L13. Experiments II

L 13/1 Effect ot Biaxial Loading and Geometry on Prediction of Low-Cycle Fatigue Life A.W.A- Konter, G.T.M. Janssen, T.N.O., Institute for Mechanical

Constructions, Delft, W. Husslage, T.N.O., Metal Research Institute, Apeldoorn, The Net­

herlands L13/3 An Analysis of the Relaxation of Residual Stresses by Using

Vibrational Conditioning K.K. Wahi, D.E. Maxwell, Science Applications, Inc., San Leandro,

California, U.S.A. L13/4 Analysis of Notch Strain for Cyclic Loading

N.E. Dowling, W.K. Wilson, Westinghouse Electric Corporation, Research and Development Center, Pittsburgh, Pennsylvania, U.S.A.

L13/5 Structural Beam Shapes under Cyclic Inelastic Loads S.G. Krishnasamy, Ontario Hydro Research Division, Toronto, On­

tario, N.A. Kennedy, A.N. Sherbourne, University of Waterloo, Water­

loo, Ontario, Canada L 13/6 High Temperature Alloys for the Primary Circuit of a Prototype Nu­

clear Process Heat Plant P.J. Ennis, H. Schuster, Kernforschungsanlage Jülich, Jülich, Fed.

Rep. Germany L 13/7 Experimental Analysis on Elasto-Plastic Behaviour of T-Branched

Stainless Steel Pipe P. Cittì, G. Nerli, S. Reale, P. Rissone, Università di Florence,

Florence, G. Tomassetti, CNEN Casaccia, Roma, Italy

L 13/8 The Response of Flat Plates Subjected to a Centrally Distributed Heat Flux D.L. Wesenberg, P.H. Adams, CM. Stone, Sandia Laboratories,

Albuquerque, New Mexico, U.SA.

86

L 13/9 Creep and Relaxation Behaviours of 304 Stainless Steel Piping Elbows K. lida, University of Tokyo, Tokyo, Y. Ito, Y. Fukuda, Hitachi Research Laboratory, Hitachi Ltd, Hita-

chi-shi, Ibaragi, M. Ohsawa, Hitachi Ship Building and Engineering Ltd., Sakai-shi,

Osaka, Japan L 13/10 Structural Behavior of Welded Superalloy Cylinder with Internal

Pressure in High Temperature Environment T. Udoguchi, Chiba University, Chiba, Y. Asada, University of Tokyo, Tokyo, T. Nakanishi, Fuji Electric Co., Ltd., Yokosuka, Japan

87

TABLE OF CONTENTS

Division M. METHODS FOR STRUCTURAL ANALYSIS

Session M 1. Integrated Methods of Structural Analysis

M 1/1* Integrated Computer-Based Systems: Survey and Outlook J.F. Gloudeman, The MacNeal-Schwendler Corporation, Los An­

geles, California, U.S.A. M 1/2 Finite Element Three-Dimensional Elastic-Plastic Creep Analysis

A. Levy, Grumman Aerospace Corporation, Bethpage, New York, U.S.A.

M 1/3 PAM-NL: A General Finite Element Program for the Nonlinear Thermomechanical Analysis of Structures E. Haug, J.M. Locci, Engineering System International, Rungis-

Silic, FC. Arnaudeau, Novatome Industries, Le Plessis Robinson, France

M 1/4 Further Developments of Capabilities in the Program ANSR for Nonlinear Finite Element Analysis DP. Mondkar, G.H. Powell, University of California, Berkeley, Cali­

fornia, U.S.A. M 1/5 The Computer Program System for Structural Design of Nuclear

Power Plant S. Aihara, K. Atsumi, K. Sasagawa, S. Satoh, Kajima Corporation,

Architectural Design Division, Tokyo, Japan M 1/6 Engineering Capabilities of the ASASIN Program

N.O Knowles, V.M. Trbojevic, Atkins Research and Development, Epsom, Surrey,

J.R. Stoker, Engineering Technology Associates, Stokingford, Nu­neaton, Warwickshire, U.K.

M 1/7* Algorithmic and Other Aspects of Large Scale Lagrangian Compu­tation by Finite Element and Finite Difference Techniques GL. Goudreau, Lawrence Livermore Laboratory, Livermore, Cali­

fornia, U.S.A.

Session M 2. Numerical Implementation of Inelastic Material Models

M 2/1* On Constitutive Modelling in Finite Element Analysis K.J. Bathe, M.D. Snyder, M.P. Cleary, Massachusetts Institute of

Technology, Cambridge, Massachusetts, U.S.A. M 2/2* Computational Aspects of Inelastic Analysis

J.H. Argyris, LE. Vaz, K.J. Willam, ISD, Universität Stuttgart, Stuttgart, Fed. Rep. Germany

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.

88

M 2/3 A Finite Element Model for Plane Strain Plasticity with Velocity Dis­continuities H.M. van Rij, The Netherlands Energy Research Foundation, Pet-

ten, The Netherlands M 2/4 Computer Implementation of an Elastic-Plastic Concrete Rela­

tionship D.W. Murray, L. Chitnuyanondh, C Wong, University of Alberta,

Edmonton, Alberta, Canada M 2/5 Coupled Damage Modes (CDM) Plasticity Models for the Simula­

tion of Complex Materials Used in Reactors J.J. Dubois, J.O Bianchini, A. de Rouvray, Engineering System In­

ternational, Rungis-Silic, France M 2/6 Implementation of Endochronic Theory for Concrete with Exten­

sion to Include Cracking G.H. Powell, University of California, Berkeley, California, U.S.A., IP. de Villiers, Bruinette, Kruger & Stoffberg, Capetown, Republic

of South Africa, R.W. Litton, PMB Systems Engineering, Inc., San Francisco, Cali­

fornia, U.S.A. M 2/7 Three Dimensional Finite Element Linear Analysis of Reinforced

Concrete Structures M. Inbasakaran, V.G. Pandahnathan, CS. Krishnamoorthy, Coim-

batore Institute of Technology, Coimbatore, India M 2/8 Nonlinear Finite Element Analysis of RC Structures Subjected to

Thermal Load TP. Khatua, A. Al-Dabbagh, Sargent & Lundy Engineers, Chicago,

Illinois, U.S.A.

Session M 3. Design and Simplified Methods of Analysis M 3/1 Optimal Shapes of Pressure Vessel Heads to Minimize Shearing

Stress J. Middleton, University of Wales, Swansea, UK.

M 3/2 Plastic Analysis of the Core Barrel Flange Deformations According to Non-Symmetric Bending Loadings U. Berkner, Kraftwerk Union AG, Erlangen, Fed. Rep. Germany

see F 1/4 M 3/3 Thermal Shocks in Solar Boiler Tubes and Mechanical Tolerance

to Heating Velocity C Gamby, P. Pietri, Université de Poitiers, Poitiers, France

M 3/4 Membrane versus Shell Type Elements in Finite Element Analysis of Box Type Buildings G. Canetta, Finzi-Nova-Castellani Associated Engineers, Milano,

Italy M 3/5 Methods of Two-Steps Inelastic Analysis of Liners

E. Vitiello, Politecnico di Milano, Milano, Italy M 3/6 Super Element Model Development and Analysis of the Mark I To­

rus Structure L.-C Hua, Bechtel Power Corporation, San Francisco, California,

U.S.A.

89

M 3/7 Study of an Axisymmetric Model for the Parametric Analysis of a 3D Complex Steel Structure A. Morel, E. Rodet, NERSA, Lyon, F. Besnier, G. Rozenblum, Compagnie Internationale de Services

en Informatique, Paris, France M 3/8 Comparison Between a 3D Photoelastic Model and an Axisymme­

tric Finite Element Calculus A. Morel, NERSA-EDF, Lyon, A. Zolzettich, NERSA-ENEL, Lyon, F. Jullien, INSA, Villeurbanne, E. Somma, D. Amir-Mazaheri, Société d'Etudes et d'Equipement d'Entreprises, Paris, France

M 3/9 Safety Investigation of a Spent Fuel Pool for Installation of High Capacity Fuel Racks T.H. Chen, W. Sawi;uk, R. Chang, Gilbert Associates, Inc., Read­

ing, Pennsylvania, U.SA. M 3/10 A Mechanistic Assessment of Structural Failure for Missile Impacts

on Concrete Structures P. Godbout, A. Brais, Université de Montréal, Montréal, Québec,

Canada

Session M 4. Computational Techniques for Plate and Shell Analysis I

M 4/1* Finite Elements for Large Displacement General Shell Analyses R.L. Taylor, University of California, Berkeley, California, U.S.A.

M 4/2 Analysis of Shell Components by Finite Elements R. Pratt, P. Ward, Atkins Research and Development, Epsom, Sur­

rey, U.K. M 4/3 FAST - A Shell Code Using Asymptotic Results

CR. Steele, Stanford University, Stanford, California, G.V. Ranjan. Failure Analysis Associates, Palo Alto, California, C Goto, Shell Technology Associates, Palo Alto, California, T.H. Pulliam, NASA Ames Research Center, Moffett Field, Califor­

nia, U.S.A. M 4/4 Matrix Analysis of the Asymmetrical Bending of Conical Shell-

Beams and Their Singular Assemblies A. Kiedrzynski, L. Coppens, Université Libre de Bruxelles, Bru­

xelles, Belgium M 4/5 A Finite Element Model for Nonlinear Shells of Revolution

W.A. Cook, Los Alamos Scientific Laboratory, Los Alamos, New Mexico, U.S.A.

M 4/6 Large Deflection Elastic-Plastic Analysis of Shells of Revolution with a Quasilinearization Algorithm H.U. Ahmed, Argonne National Laboratory, Argonne, Illinois, J.W. Leonard, Illinois Institute of Technology, Chicago, Illinois,

U.S.A.

90

M 4/7 Elasto/Visco-Plastic Deformations of Thin Shells of Revolution S. Takezono, T. Akashi, Kumamoto University, Kumamoto, Japan

M 4/8 Elasto/Visco-Plastic Analysis of Axisymmetrical Shells under Asymmetrical Loading K. Tao, S. Takezono, Kumamoto University, Kumamoto, Japan

Session M 5. Computational Techniques for Plate and Shell Analysis II

M 5/1 Analysis of the Buckling Behaviour of Structures M. König, ISD, Universität Stuttgart, Stuttgart, Fed. Rep. Germa­

ny M 5/2 A Note on Imperfection Sensitivity of Externally Pressurized Shells

R.L. Citerley, E.B. Paxson, Jr., Anamet Laboratories, Inc., San Carlos, California,

RE. Ball, U.S. Naval Postgraduate School, Monterey, California, U.S.A.

M 5/3 Experience with a New Triangular Doubly-Curved Element for Shell Analysis S.-C Wu, Cornell University, Ithaca, New York, J.F. Abel, McDonnell Doug/as Automation, St.-Louis, Missouri,

USA. M 5/4 The Use of the Semiloof Shell Element in the BERSAFE Finite Ele­

ment System T.K. Hellen, CEGB, Berkeley Nuclear Laboratories, Berkeley, Glou­

cestershire, U.K. M 5/5 A New Finite Element for Structural Analysis of Piping Systems

H. Takeda, S. Asai, Century Research Center Corporation, Tokyo, K. Iwata, Power Reactor and Nuclear Fuel Development Corpora­

tion, Tokyo, Japan M 5/6 Non-Linear Analysis of Shells (Large Displacements); Use of the

Equilibrium Equations Based on the Deformed Body A Combescure, A. Hoffmann, CEA./CEN-Saclay DEMT ISMTS,

Gif-sur-Yvette, France M 5/7 Incorporation of an Eigenvalue Dynamic Buckling Criteria into Di­

rect Integration Procedures V. Svalbonas, Koppers Company, Inc., York, Pennsylvania, U.S.A.

M 5/9 A Thin Shell Dynamic Transient Non-Linear Analysis Program Y. Crutzen, Commission of the European Communities, J.R.C.

Ispra Establishment, Ispra, Italy

91

Session M 6. Computational Techniques within Finite Element Analysis I

M 6/1 * Penalty Methods in Finite Element Analysis of Fluids and Structu­res D.S. Malkus, Illinois Institute of Technology, Chicago, Illinois,

U.S.A. M 6/2 A Boundary Method to Solve Mixed Boundary Value Problems by

Consistent Weighting to the Different Boundary Conditions K. Brandes, Bundesanstalt für Materialprüfung, Berlin (West), Ger­

many M 6/3 Contact Finite Elements

U. Schomburg, J. Redmer, G. Deeken, Rheinisch-Westfälische Technische Hochschule Aachen, Aachen, Fed. Rep. Germany

M 6/4 EPAS-Finite Element Program for Analysis of Nonlinear Behavior of Nuclear Power Piping G. Yagawa, Y. Ando, University of Tokyo, Tokyo, T. Watanabe, S. Ishiwata, Century Research Corporation, Tokyo.

Japan M 6/5 A Procedure to Obtain Unconditionally Stable Explicit Methods for

Structural Problems L. Brusa, R. Ciacci, A. Greco, CISE, Milano, Italy

M 6/6 Dynamic Analysis of Buried Structures Subjected to Shock Loads T.P. Khatua, A.K. Pattanayak, Sargenta Lundy Engineers, Chicago,

Illinois, A.K. Gupta, Illinois Institute of Technology Research Institute, Chi­

cago, Illinois, U.S.A. M 6/7 A Numerical Method for Complex Structural Dynamics in Nuclear

Plant Facilities W. Zeitner, Kraftwerk Union AG, Erlangen, Fed. Rep. Germany

M 6/8 Implicit Treatment of the Large Deformation Response of Inelastic Solids with Slide-Lines J.O. Hallquist, Lawrence Livermore Laboratory, Livermore, Cali­

fornia, U.S.A.

Session M 7. Computational Methods within Finite Element Analysis II

M 7/1* Quasi-Newton Iteration in Non-Linear Structural Dynamics M. Geradin, M. Hogge, Université de Liège, Liège, Belgium

M 7/2 Efficient Solution Procedures of Simultaneous Equations for Large Nonlinear Finite Element Systems M. Tanabe, H. Takeda, Century Research Center Corporation, To­

kyo, K. Iwata, Power Reactor and Nuclear Fuel Development Corpora­

tion, Tokyo, Japan

92

M 7/3 Linear Dynamic Analysis by Hybrid Displacement Finite Element Models K. Brandt, Brown, Boveri & Cie AG, Mannheim J.W. Wissmann, Technische Hochschule Darmstadt, Darmstadt,

Fed. Rep. Germany M 7/4 A Method of Solution of the Eigenproblems of Large Structural Sy­

stems in an Arbitrarily Specified Range J. Orkisz, B. Wrana, University of Cracow, Cracow, Poland

M 7/5 Solutions of Associated Problems in Structural Optimization P. Brousse, Université de Paris VI, Paris, France

M 7/6 Modal Analysis and Estimation of the Calculation Errors W. Krings, Bauunternehmung E. Heitkampf GmbH, Herne, Fed.

Rep. Germany M 7/7 Adaptive versus Standard Finite Element Programs: Data for

Comparison of Costs and Accuracy A. Peano, ISMES, Bergamo, Italy, P. Basu, Washington University, St. Louis, Missouri, U.S.A.

M 7/8 Remesh Algorithms for the Finite Element and Finite Difference Calculation of Solid and Fluid Continuum Mechanics Problems J. Dubois, J.F. Chedmail, Engineering System International, Run-

gis-Silic, C. Chavant, CISI Saclay, Gif-sur-Yvette, A. Hoffmann, CEA.ICEN Saclay DEMT, Gif-sur-Yvette, France

Session M 8. Probabilistic Methods in Structural Analysis

M 8/1 * Some Aspects of the Interaction Between Systems- and Structural Reliability G.I. Schuëller, Technische Universität München, München, P. Kafka. Gesellschaft für Reaktorsicherheit, Garching, W. Schmitt, Kraftwerk Union AG, Erlangen, Fed. Rep. Germany

M 8/3 The Development of Time-History Design Criteria for Uncertain Transient Loads JR. Benjamin, Engineering Decision Analysis Company, Inc., Palo

Alto, California, U.S.A. M 8/5 COVASTOL: A Computer Code for the Estimation of Pressure

Vessel Failure Probability A C Lucia, J. Eibaz R. Brunnhuber, Commission of the European

Communities, J.R.C. Ispra Establishment, Ispra, Italy M 8/6 Methods to Determine the Influence of Quality Assurance on the

Reliability of Primary Components of a PWR W. Schmitt, R. Wellein, Kraftwerk Union AG, Erlangen, Fed. Rep.

Germany M 8/7 Effects of Correlation between Defects and Material Properties on

Component Failure Probability D.L. Marriott, A.R. Churchill, Atomic Energy Board. Licensing

Branch, Pelindaba, Republic of South Africa

93

M 8/8 Reliability of Mechanical Components Subjected to Combined Al­ternating and Mean Stresses with a Nonconstant Stress Ratio D. Kececioglu, University of Arizona, Tucson, Arizona, U.S.A., G.B. Lamarre, Canadian Forces Command and Staff College,

Toronto, Ontario, Canada

M 8/9 Design Stresses in Probabilistic Form for Ellipsoidal and Toroidal Pressure Vessels CO. Smith, University of Nebraska at Omaha, Omaha, Nebraska,

U.S.A.

Session M 9. Numerical Procedures for Fracture Mechanics

M 9/1 A Numerical Comparison of Post Yield Fracture Behaviour in Rotor Steels T.K. Hellen, CEGB, Berkeley Nuclear Laboratories, Berkeley, Glou­

cestershire, U.K. withdrawn M 9/2 Improved Practical Lower Bound for Fracture Toughness Data

G.M. Jouris, D.H. Shaffer, Westinghouse Research and Develop­ment Center, Pittsburgh, Pennsylvania, U.S.A.

M 9/3 Defect Vectors and Path Integrals in Fracture Mechanics R.L. Roche, CEA./CEN-Saclay DEMT, Gif-sur-Yvette, France

M 9/4 On the J-lntegral for Nonhomogeneous Cracked Composites W.-H. Chen, National Tsing Hua University, Hsinchu, Taiwan, Re­

public of China M 9/5 Fracture Mechanics Evaluation of Reactor Vessel Using Stress In­

tensity Factors from Enriched Finite Elements D.T. Ramani, F.L. Cho, R.D. Raheja, Sargent & Lundy Engineers,

Chicago, Illinois, U.S.A. M 9/6 An Investigation of Degenerate Isoparametric Finite Elements

for Stress Intensity Computations H.U. Akay, O. Gürdogan, Middle East Technical University, Ankara,

Turkey M 9/7 A New Mixed Mode Fracture Mechanics Criterion

P. Laf ore, CEA./CEN-Saclay DEMT, Gif-sur-Yvette, France M 9/8 Handy Incorporation of Bond and Singularity Elements in the

Finite Element Solution Routine Y. Yamada, Y. Ezawa, I. Nishiguchi, Institute of Industrial Science,

University of Tokyo, Tokyo, M. Okabe, Mitsui Mining and Smelting Company, Ltd., Tokyo,

Japan M 9/9 The Analysis of Structures Containing Defects Using Isoparametric

Elements B.V. Day P. Brierley, Nuclear Power Company (Risley) Ltd., Risley,

Warrington, Cheshire, U.K.

Session M 10. Dynamic Modelling in Seismic Analysis

M 10/1 Application of Far Field Asymptotic Solutions in Global-Local Fi­nite Elements R. Muki, SB. Dong, University of California, Los Angeles, U.S.A.

M 10/2 An Interior Collocation Method for Vibration of a Rectangular Plate Carrying Attached Mass Y. A. Patel, Sargent & Lundy Engineers, Chicago. Illinois, U.S.A.

M 10/3 The Use of an Equivalent Homogeneous Half-Space in Soil-Struc­ture Interaction Analyses U. Holzlöhner, Bundesanstalt für Materialprüfung, Berlin (West),

Germany M 10/3a Some Considerations on the Dynamic Structure-Soil-Structure In­

teraction Analysis W. Matthees, Bundesanstalt für Materialprüfung, Berlin (West),

Germany M 10/4 Quasi-Nonlinear Dynamic Analysis

C. Meyer, Columbia University, New York, N. Y., U.SA. M 10/5 Approximations for Dynamic Modeling

ST. Wu, K.D. Chiù, E. Odar, Ebasco Services, Inc., New York, N.Y., USA.

M 10/6 Stochastic Finite Element Structural Models H. Contreras, R.E. Scholl, URS/John A. Blume & Associates, Engi­

neers, San Francisco, California, U.S.A. M 10/7 Nonlinear Response to the Multiple Sine Wave Excitation of a Sof­

tening-Hardening System B. Koplik, M. Subudhi, J. Curreri, Brookhaven National Laboratory,

Upton, New York, U.S.A.

Session M 11. Advances in Linear Boundary and Initial Value Problems

M 11 /1 Solution of Plane Stress and Plate Bending Problems by Boundary Integral Equations R.L. Grover, Defense Products Division, Brunswick Corporation,

Lincoln, Nebraska, S.I. Chou, University of Nebraska, Lincoln, Nebraska, U.S.A.

M 11/2 Applications of the Fundamental Solution for a Thermal Shock on a Finite Orthotropic Cylindrical Thin Shell C.L.D. Huang, P.G. Kirmser, Kansas State University, Manhattan,

Kansas, H.K. Woo, General Atomic Company, San Diego, California,

USA.

M 11/3 Thermal Stresses in Cylindrical Shells Under Arbitrary Tempera­ture Distribution W. Schnell, Technische Hochschule Darmstadt, Darmstadt, Fed.

Rep. Germany

95

M 11/4 Transient Thermal Stresses in a Transversely Isotropic Thick Plate with a Cylindrical Hole due to Surface Heat-Generations Y. Sugano, Y. Takeuti, University of Osaka Prefecture, Sakai,

Osaka, Japan M 11/6 Elastic Behavior of Thick Plates and Shells with Cutouts

CP. Vendhan, J.P. Cash, W.A. Nash, University of Massachusetts, Amherst, Massachusetts, U.S.A.

M 11/7 The Application of the Energy Principle to 3-Dimensional Shell Problems W.W. Feng, Lawrence Livermore Laboratory, Livermore, Califor­

nia, U.S.A. withdrawn

96

TABLE OF CONTENTS

Division N. THERMAL, MATERIALS ENGINEERING, AND STRUCTURAL MECHANICS PROBLEMS OF FUTURE FUSION REACTOR POWER PLANTS

Session N 1.1. Engineering Concepts of Magnetic Confinement Fusion Reactor Systems

N 1.1/1'Magnetic Confinement Fusion Reactor Systems R. Aymar, CEA. Département de Physique du Plasma et de la

Fusion Contrôlée, Centre d'Etudes Nucléaires, Fontenay-aux-Roses, France

N1.1/2*The USA/TNS Programs: Engineering Considerations T.E. Shannon, Oak Ridge National Laboratory, Oak Ridge, Tennes­

see, J.M. Rawls, General Atomic Company, San Diego, California,

USA. N 1.1/3* Mirror Fusion Reactor Design

W.S. Neef, Jr., G.A. Carlson, R.W. Moir, Lawrence Livermore Laboratory, Livermore, California, U.SA.

N 1.1/5 Structural Engineering Problems in FINTOR Conceptual Designs M. Biggio, G. Casini, F. Farfaletti-Casali, M. Rieger, J. van Renterg-

hem, Commission of the European Communities, J.R.C. Ispra Establishment, Ispra,

G. Rubinacci, Università di Napoli, Napolijtaly

Session N 1.2. Engineering Concepts of Inertial Confinement and Hybrid Fusion Reactor Systems and Safety Considerations

N 1.2/1* Inertial Confinement of Fusion Reactors R.W. Conn, University of Wisconsin, Madison, Wisconsin, U.S.A.

N 1.2/2 Electric Power from Laser Fusion: The HYLIFE Concept M.J. Monsler, J.A. Blink, J. Hovingh, W.R. Meier, P. Walter, Law­

rence Livermore Laboratory, Livermore, California, U.S.A. N 1.2/3* Structural Concerns in Fusion Hybrid Reactors

K.R. Schultz, General Atomic Company, San Diego, California, U.S.A.

N 1.2/4 Engineering Design of the SOLASE-H Laser Fusion Hybrid Reactor S.I. Abdel-Khalik, R.W. Conn, G.A. Moses, et al., University of Wis­

consin, Madison, Wisconsin, U.S.A. N 1.2/5* Fusion Reactor Safety

D. Okrent, W.E. Kastenberg, University of California, Los Angeles, California, U.S.A.

Notes: — The sign ("I designates Invited Lectures. — A title ment ioned on the Table of Contents but not fo l lowed by a summary or a paper means t*iat the paper

w a s not available at the t ime of f inishing of the book. — A paper number missing m the numeral order means that the paper was cancelled or w i t h d r a w n

97

Session N 1.3. Thermal-Fluid Dynamics of Fusion Power

Reactor Systems

N 1.3/1'Thermal­Hydraulic Considerations in Magnetically Confined Fu­sion Reactors D.W. Kearney, Solar Energy Research Institute, Golden, Colorado,

U.SA.

N 1.3/2 Thermo­Fluid Mechanics of Liquid or Gas Cooled Tubular First Walls J.A. Filio, J.R. Powell, Brookhaven National Laboratory, Upton,

New York, U.S.A.

N 1.3/3 Thermal Analysis of a High­Temperature Falling Bed Fusion Reactor Blanket J.F. de Paz, S.D. Harkness, Argonne National Laboratory, Argonne,

Illinois, U.SA.

N 1.3/4* Heat Transfer in Inertial Confinement Fusion Reactor Systems J. Hovingh, Lawrence Livermore Laboratory, Livermore, California,

U.SA.

N 1.3/5 Hydrodynamic Effects in Inertial Fusion Reactors S.L.Thomson, Bechtel National, San Francisco, California, U.S.A.

N 1.3/6 Shock and Blast Load Attenuation in Inertial Confinement Fusion Reactors CA. Kot, Argonne National Laboratory, Argonne, Illinois, U.S.A.

N 1.3/8 Cooldown and Warmup Thermal Analysis of the Mirror Fusion Test Facility (MFTF) Superconducting Magnet R.F. O'Neill, R.E. Tatro, General Dynamics Convair, San Diego,

California, USA.

Session N 2.1. Structural Analysis of Magnets

Ν2.1/Γ Existing and Future Structural Analysis Techniques and Their App­lication to Superconducting Magnets M. Reich, Brookhaven National Laboratory, Upton, New York,

U.SA.

N 2.1/4 Finite Element Structural Analysis of Coil and Casing of a Large Superconducting Toroidal LCT­Magnet J. Erb, Universität Karlsruhe, Karlsruhe, A. Grünhagen, G. Messemer, H. Zehlein, Kernforschungszentrum

Karlsruhe, Karlsruhe, Fed. Rep. Germany

N 2.1/5 On the Mechanical Anisotropy in Superconducting Toroidal Coil Windings F. Arendt, C­Η. Dustmann, Kernforschungszentrum Karlsruhe,

Karlsruhe, Fed. Rep. Germany

N 2.1/6 Method for Determining the Magnet Shape in Toroidal Arrange­ments J. Erb, W. Maurer, Kernforschungszentrum Karlsruhe, Karlsruhe,

Fed. Rep. Germany

98

N 2.1/7 Structural Analysis of Non-Circular Coils for Fusion Experiments K.E. Buck, J.W. Hammel, Brown, Boveri & Cie., Mannheim, Fed.

Rep. Germany N 2.1/8 Structural Analysis of Compact Experiments for Thermonuclear

Ignition B. Coppi, Massachusetts Institute of Technology, Cambridge,

Massachusetts, U.S.A., A. Taroni, Centro Calcolo, CNEN, Bologna, Italy

N 2.1/9 Fields Analysis of TFR 604 Copper Coils P. Bourrier, C. Dubois, SOCOTEC, Paris, P. Deschamps, CEA./CEN-Saclay, Gif-sur-Yvette, A. Millard, CEA. ICEN, Fontenay-aux-Roses, France

Session N 2.2. Magnet Technology

N 2.2/1'Structural Materials for Fusion Magnets CD. Henning, Lawrence Livermore Laboratory, Livermore, Cali­

fornia, E.N.C. Dalder, United States Department of Energy, Washington,

D.C, U.S.A. N 2.2/2 General Dynamics Convair Division Approach to Structural Anal­

ysis of Large Superconducting Coils R.W. Baldi, General Dynamics Convair Division, San Diego, Cali­

fornia, U.S.A. N 2.2/3 Applications of Metallic Composites in the Magnet System of a

Demonstration Fusion Reactor R. Matera, Commission of the European Communities, J.R.C.-Ispra

Establishment, Ispra, Italy, R. Potts, D.H. Prothero, International Research and Development

Co., Ltd., Newcastle, U.K., G. Pasotti, M.V. Ricci. N. Sacchetti, M. Spadoni, CNEN, Laboratorio

Gas lonizatti, Frascati, Italy N 2.2/4 The Structural Design of Superconducting Magnets for the Large

Coil Program W.H. Gray, W.C.T. Stoddart, C.J. Long, Oak Ridge National Labo­

ratory, Oak Ridge, Tennessee, U.SA. N 2.2/5 Structural Design of DEALS Magnet

P. Bezler, S.Y. Hsieh, Brookhaven National Laboratory, Upton, New York,

T. Balderes,T. Brown, J. Bundy, Grumman Aerospace Corporation, Bethpage, New York, U.S.A.

99

Session N 2.3. First Wall Performance in Fusion Reactors

N 2.3/1 * A Review of Lifetime Analyses for the First Wall of a Tokamak-Ba-sed Reactor S.D. Harkness, Argonne National Laboratory, Argonne, Illinois, J. Davis, McDonnell Douglas Astronautics Co., St. Louis, Missouri,

U.S.A. N 2.3/2 FWLTB - A Computer Program for Predicting the Lifetime of a Fu­

sion Reactor First Wall W. Daenner, J. Raeder, Max-Planck-Institut für Plasmaphysik, As­

sociation EURATOM-IPP, Garching, Fed. Rep. Germany N 2.3/3 Approaches to Assessing the Failure Resistance of Fusion Reactor

First Walls G.R. Odette, University of California, Santa Barbara, California, T.O Reuther, U.S. Department of Energy, Washington,D.C, W.G.Wolter, University of Wisconsin, Madison, Wisconsin, U.S.A.

N 2.3/5 Stress Wave Edge Effects in ICTR Structural Components M.S. Hejazi, Northwestern University, Evanston, Illinois, E.G. Lovell, University of Wisconsin, Madison, Wisconsin, U.S.A.

N 2.3/6 Loads and Stresses in ICF Reactors withdrawn IO. Bohachevsky, L.A. Booth, T.G. Frank, J.H. Pendergrass, Los

Alamos Scientific Laboratory, Los Alamos, New Mexico, U.S.A. N 2.3/7 Thermal, Radiation and Structural Mechanics Problems of Ma­

gnetic-Confinement CTR First Wall B.M. Ma, Iowa State University, Ames, Iowa, U.S.A.

Session N 2.4. Fusion Blanket Structural Analysis

N 2.4/1* First Wall and Blanket Structure Performance W. Daenner, Max-Planck-Institut für Plasmaphysik, Association

Euratom-IPP, Garching, Fed. Rep. Germany N 2.4/2 Fracture Mechanics Aspects of Irradiated Blanket Structures

B.A. Cramer, J.W. Davis, McDonnell Douglas Astronautics Com­pany, St. Louis, Missouri, U.S.A.

N 2.4/3 Dynamic and Static Structural Analysis of Liquid Lithium Blanket of Fusion Power Plant M. Masuda, T. Horie, G. Yagawa, Y. Ando, University of Tokyo, To­

kyo, Japan N 2.4/4 Stress Analysis of Blanket Vessel for JAERI Experimental Fusion

Reactor K. Sako, A. Minato, Japan Atomic Energy Research Institute, Tokai

Research Establishment, Ibaraki-ken, Japan N 2.4/5 The Structural Design Techniques Used in the Mirror Fusion Test

Facility (MFTF) Vacuum Vessel L.W. Pollard, Lawrence Livermore Laboratory, Livermore, Califor­

nia, U.S.A. withdrawn

100

N 2.4/6 Mechanical Studies for Supraconducting Toroidal Field Coils of Large Tokamak Fusion Device R. Aymar, Y. Roux, CE.A./CEN-FAR (DPh-SCP), Fontenay-aux-

Roses, P. Bourrier, C Dubois, SOCOTEC, Paris, A. Millard, CEA./CEN-Saclay, DEMT, Gif-sur-Yvette, France

N 2.4/7 Mechanical Static Analysis of the JET Vacuum Vessel B. Streibl, JET Project Abingdon, Oxon, U.K., P. Bourrier, Th. Foult, SOCOTEC, Paris, France

N 2.4/8 Structural Design Methods for Ceramics in Fusion Reactors G.G. Trantina, J.P.D. Wilkinson, General Electric Corporate Re­

search Et Development, Schenectady, New York, U.SA. N 2.4/9 Engineering Design of a Direct-Cycle Steam-Generating Blanket

for a Long-Pulse Fusion Reactor CE. Cort, R.L. Hagenson, R.W. Teasdale, W.E. Fox, P.D. Soran, CG. Bathke.H.S.Cullingford, R.A. Krakowski, Los Alamos Scienti­

fic Laboratory, Los Alamos, New Mexico, U.S.A.

Session N 2.5. Materials and Plasma-Fluid Wall Interaction

N 2.5/1 "The Change of Materials Properties During Irradiation in Fusion Reactor Service F.W. Wiffen, Oak Ridge National Laboratory, Oak Ridge, Tennes­

see, U.S.A. N 2.5/2 Radiation Effects on Elasticity of Metals

M. Afzali, Arya-Mehr University of Technology, Isfahan, Iran, S. Nemat-Nasser, Northwestern University, Evanston, Illinois,

U.S.A. N 2.5/3 Corrosion of Structural Materials in Dynamic Lithium

F. Casteels, H. Tas, J. DeKeyser, M. Soenen, F. Lievens, Studiecen­trum voor Kernenergie, S.CK./CE.N., Mol, Belgium

N 2.5/4 The Response of Stainless Steel to the Pellet Debris in a Laser Fusion Reactor T.J. McCarville, A.M. Hassanein, G.L. Kulcinski, University of

Wisconsin, Madison, Wisconsin, U.SA. N 2.5/5 Dynamic Loading of the Structural Wall in a Lithium Fall Fusion

Reactor L.A.Glenn, Lawrence Livermore Laboratory, Livermore, California,

U.S.A. N 2.5/7 Structural Alloys for Superconducting Magnets in Fusion Energy

Systems H.I. McHenry, R.P. Reed, National Bureau of Standards, Boulder,

Colorado, U.S.A.

101

AUTHORS INDEX

AbdeL-KhaUk S.I.

Abe H.

Abel J.F.

Adams N.J.I.

Adams P.H.

Afzali M.

Agrawal P.K.

Agrone M.

Agüero A.A.

Ahmed H.U.

Ahmed K.M.

Aihara S.

Ainsworth R.A.

Aird H.M.

Aizawa T.

Akashi T.

Akay H.U.

Akkas N.

Akky M.R.

Albertini C.

Albeson K.

Albrecht W.

Al-Dabbagh Α.

Alderson Μ.Α.Η.G.

Alix M.

Alujevic A.

Amii—Mazahen' H.D.

A-Moneim M.T.

Amzallag C.

Anand A.K.

Anantharaman K.

Anderko K.

Andersen A.

Andersen S.I.

Anderson P. II.

Anderson R.G.

Ando Y.

Andrews W.R.

Antony-Spies P.

Aoyagi Y.

Aquaro D.

Arai K.

Arendt F.

Argon A.5.

Argyris J.H.

N 1 .2 /4

H 4 / 9 ,

M 5 / 3

G 2 / 5 ,

L 13 /8

N 2 . 5 / 2

K 1/6

K 11 /10

K 5 /7

B 4 / 6 ,

K 6 /7

K 8 / 5 ,

L 11 /8

H 3 / 4

L 5/4

M 4 /7

M 9/6

B 4 /5

K 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 ,

G 8 /2

C 3 / 1 0 ,

C 3 / 1 1

L 12 /7

J 6 / 6 ,

G 1 0 / 1 *

K 11 /9

D 5 /10

E 4 / 7 ,

G 5/2

B 7 / 3

H 4 / 9 ,

L 9 /6

K 13 /7

N 2 . 1 / 5

D 3/5

M 2 / 2 *

J 4 / 4

G 3 / 1 *

H 8 / 6 ,

M 1/5

E 3 /4

C 3 / 1 1

J 6 / 8

F 2 / 8 ,

J 4 / 1 * ,

K 1 2 / 5 , K 1 2 / 1 0 , L 6 / 3 , M 4 / 6

L 5 / 4 , H 6 / 4 , N 2 . 4 / 3

J 4 / 4 , J 4 / 5 , J 4 / 6 , J 4 / 7

105

Ar iman T . D 7 / 4 , E 3 / 5 , K 11 /4

Arnaudeau F.C. M 1/3

A r n o l d L. E 4 / 1 *

A r n o l d P. K 5 /3

A r o c k i a s a m y M. K 4 / 7

A r r o s J . Β 8 /5

A r t h u r D.F. L 9/5

Asada K. L 10 /5

Asada Y. L 13 /10

Asa i S. F 3 / 7 , M 5/5

A s c h l H. H 1/4

Ash J . E . E 6 /2

Asmis G . J . K . J 3 / 2 , K 2 /8

Assedo R. F 2 / 1 , F 2 /2

A t a l i k T . S . K 9 /3

A t c h i s o n R . J . J 3 / 2 , K 2 /8

At l u r i S . N . G 4 / 3

A tsumi K. M 1/5

A u g u s t i G. L 1 1 / 9 *

A u r i c h D. G 2 /3

A x i s a F. E 6 /7

A v e t - F l a n c a r d R. J 7 / 1 *

Aymar R. N 1 . 1 / 1 * , N 2 . 4 / 6

Ay res D. F 5 / 1 *

A z i z T . S . K 1 1 / 5 , K 11 /7

B a l d e r e s T .

B a l d i R.W.

B a l l R .E .

B a l t e s Β.

B a n e r j e e A . K .

B a n t l e S.

B a r a i L.

B a r r a c h i n B.

Barsoum R.S.

B a s t i e n R.

Basu P.

Basu S.

Ba tes J . F .

Ba the K . J .

Ba thke C.G.

Bauer J .

Baum M.R.

B a y l a c G.

N

N

M

E

K

J

F

L

L

H

M

C

C

M

N

J

f

F

2 . 2 / 5

2 . 2 / 2

5/2

5/6

4 /5

6 / 6 , J 6 / 8

8 / 4

7 /8

1 0 / 2 *

5 / 6

7 /7

3 / 1 0 , C 3 / 1 1

3 /9

2 / 1 *

2 . 4 / 9

9 / 3

6/5

2 / 1

106

Bazant Ζ.Ρ. Η 8/1*, J 4/9 Bazergui A. F 8/3 Beck R.L. J 2/9 Becker E.B. Β 5/4 Bedrosian B. J 2/7, Κ 12/11 Beeston J.M. F 1/1 Beine Β. Η 7/1 Beinert J. G 4/5 Belytschko T.B. B 1/4, E 2/2, E 3/3, E 6/3*, H 8/1*, H 8/2 Benamou J 3/8 Benjamin J.R. M 8/3 Benuzzi A. E 4/1* Berger Ε. K 5/2 Berkner U. F 1/4 Bernard A. D 5/7 Bernasconi G. L 11/4, L 12/6 Bernreuter O.L. K 3/3, K 3/4, K 3/5 Berriaud C. J 7/1* Berro A. J 5/6 Bertaut C. F 2/4 Besnier F. H 3/7 Bethmont M. F 5/10 Betts W.S. H 5/5 B e v i l a c q u a L. F 7/5

B e z l e r P. F 4 / 5 , K 8 / 3 , K 1 2 / 1 , N 2 . 2 / 5

Bhardwa j S .A. D 4 / 6

Bho je S .B . D 3 / 7 , D 5 / 6

B i a n c h i n i J . C . J 9 / 4 , M 2 /5

B i g g i o M. Ν 1 .1 /5

B i lek Ζ . G 1 / 2 , G 6 /3

B i l l a u x M. C 1/8

B i r o n A. L 5 / 1

B i r S ingh S. 0 3 / 7 , D 5 / 6

B lack W.E. H 5 / 5 , H 5 / 6

B l a i r W. H 8 /5

B l i n k J . A . N 1 .2 /2

B l u n d e l l R. H 8 /5

Bohachevsky 1 . 0 . N 2 . 3 / 6

Bohm G . J . K 8 / 7 , L 7 /2

B o i s s e r i e J . M . L 1/6

B o n g a r t z K. C 2 / 2 , C 2 /3

Booker B . L . P . F 5 /12

Booker M.K. F 5/12

Booth L .A . N 2 . 3 / 6

B o r d e t R. J 1/6

107

Bork M. Borkowski Α. Bornscheuer F.W. Bosser M. Bounin D. Bourgeois P. Bourrier P. Boye-Moller K. Boyle J.T. Bozzo F. Brais A. Brandes K. Brandi P. Brandt K. Brennan J.A. Brierley P. Brinkman CR. Briot P. Broadhouse B.J. Brooks G.N. Brouard D. Brousse P. Brown M.L. Brown S.J. Brown T. Brunnhuber R. Brusa L. Brzoska B. Bucheri K.P. Buchhardt F. Buck K.E. Bui-Quoc T. Bundy J. Burback R.L. Burducea C. Burr T.K. Buttmann P.

Cagliostro D.J. E 1/3, E 4/2, E 5/4 Caldis E.S. F 5/3 Callahan J.P. H 3/2, H 4/5 Cambien R.B. K 11/2 Campbell F.R. J 3/2 Campbell K.W. K 3/4

J 9 /7 ,

L 6/6

J 6 /7 ,

G 8/2

H 7/2

C 1 /1*

G 10/3,

J 6/5*

L 4 / 1 * ,

J 5/6

M 3/10

J 7/3,

J 6/3

M 7/3

K 5/7,

M 9/9

F 5/12

F 2/4

E 4 / 1 *

D 3/3

F 3/2

L 10/7,

J 8/7

B 5/13,

N 2.2/5

M 8/5

M 6/5

0 21 λ

J 3/1

J 6/3

N 2.1/7

L 5/1

N 2.2/5

G 6/4

F 7/6

F 1/1

J 7/5

K 2/7

J 6/9

N 2 .1 /9 , N 2 .4 /6 ,

L 4/5

M 6/2

K 12 /11 , L 9/9

M 7/5

K 12/9

N 2.4/7

108

Campbel l R.D.

Campbel l T . E .

Cane t ta G.

C a r l s o n G.A.

C a r l t o n D.

Carmignan i C.

C a r r e i r a D . J .

Car te r P.G.

Cash J . P .

C a s i n i G.

C a s t e e l s F.

C a s t e l l a n i Α.

C a s t e l l o G.

Caumette P.

C a u q u e l i n C.

Causey A . R .

Cecconi S.

C e l e b i M.

C e n e r i n i R.

Cepkauskas M.M.

Cerne i B.

Cernocky E.P.

Cesa r i F.

Chaboche J . L .

Chan C.

Chan D.P.

Chandra S.

Chang R.

Chang Y.W.

C h a r g i n M.

C h a t t e r j e e M.

Chavant C.

Chedmai l J . F .

Che issoux J . L .

C h e l i G.G.

Chen C.

Chen T . H .

Chen W . - H .

Chen W.W.H.

Chern J .M.

Chesi C.

C h e v a l l a r d G.

Chha t re A . G .

Chiba Ν.

Chiba 0 .

Κ 2 / 1 *

F 5/2

M 3 / 4

Ν 1 . 1 / 3 *

J 8 / 1

F 5 / 1 3 , L 9 /4

J 3 /7

J 8 /8

M 1 1 / 6

N 1 .1 /5

N 2 . 5 / 3

J 3 /9

F 2 /1

F 6 / 1 *

F 6 / 1 *

F 1/2

K 1 / 9 , K 9 /2

K 7/7

E 4 / 4

F 4 /2

D 3 /4

L 7 / 1

F 3 /4

L 11 /3

K 13 /12

D 5/3

F 1/6

M 3 / 9

B 1 / 1 * , E 3 / 3 , E 5 / 3 * , E 5/5

Β 4 / 9

Κ 7 / 6 , Κ 7 /7

Β 2 / 8 ,

Ε 2 / 3 ,

F 6 /3

G 9 /6

Κ 8 / 1 *

Μ 3 / 9

L 3 / 5 , Μ 9 / 4

Κ 7 /6

Ε 3 / 7 , L 8 /5

J 3 /9

F 7 /7

D 4 / 6

J 8 /9

Κ 1/2

M 7 /8

J 9 / 4 , M 111

109

C h i r i g o s J . N . F 5/2

C h i t n u y a n o n d h L. J 3 / 4 , J 3 / 5 , M 2 /4

Ch iù K .D . M 10/5

Cho F .L . K 1 0 / 6 , M 9 /5

Chopra P.S. D 5 /8

Chou C K . K 3 /7

Chou S . I . M 1 1 / 1

Chow P.Y. H 3 / 3

Chu C K . B 2 / 4 , B 7 /4

Chu H.Y. B 1 / 1 * , E 1/4

Chu M.L . B 5 / 1 3 , K 12 /9

Chung D.H. K 3 /3

C h u r c h i l l A . R . M 8 /7

C h u r i e r H. F 5 /9

C i a c c i R. F 7 / 8 , M 6 /5

C i t e r i e y R .L . B 4 / 9 , M 5/2

C i t t ì P. L 13/7

C l e a r y M.P. M 2 / 1 *

Co fe r L . J . K 6 /4

Coleman M.C. C 4/11

Combescure Α. M 5/6

Conn R.W. Ν 1 . 2 / 1 * , Ν 1 . 2 / 4

Connors D.C. F 5 / 4 , F 5 /6

C o n t r e r a s H. M 10 /6

Cook W.A. M 4 / 5

Cooper G.W. Ν 1 . 2 / 4

Coppens L. M 4 / 4

Coppi Β. N 2 . 1 / 8

C o r d i e r G. L 11/3

Cords H. C 2/5

C o r n e l l C A . Κ 2 / 1 *

C o r o l i G. D 1/2

Cor t C E . N 2 . 4 / 9

Corwin W.R. F 5 /12

Cos taz J . L . J 1 / 6 , J 7 /4

Costes D. J 6 / 1 , K 2 /2

C o u r t o i s C D 1/9

Cousseran P. L 5 /3

Cowler M.S. B 1 / 6 , E 5 /1

C o z z a r e l l i F.A. L 11 /4

Cramer B.A. N 2 . 4 / 2

Crook C E . G 2/4

Crouse C.B. K 2/3

C r u t z e n Y. J 7 / 2 , M 5/9

C u l l i n g f o r d H.S. N 2 . 4 / 9

110

Cummings G.E. Cur ioni S. Curran D.R. Curreri J. Curtress N.

K 3/2

F 3 /4

G 6/4

K 8 / 3 , K 1 2 / 1 , K 1 2 / 6 , M 10 /7

J 8 /7

Daddaz io R.P.

Daenner W.

D a f a l i a s Y . F .

D a l d e r E . N . C

Danay A.

Dang Van K.

Dan i sch R.

Dao K.C.

D a r l a s t o n B . J . L .

D a r l i n g R.S.

Das M.

D a t t a g u r u B.

Dav ies I . L l .

D a v i s J.W.

Day B.V.

Day S.M.

Deans J . J .

Deeken G.

D e i t r i c h L.W.

De Keyser J .

D e l a l e F.

D e l a v a l M.

Del Grosso A.

Del P u g l i a A.

De Ngo

De P a t e r C

De Paz J . F .

De Rouvray A.

Deschamps P.

Dese leve P.

Devaux J . C

De Vi U i e r s I . P .

D ienes J . K .

D ie tmann H.

D i m e l f i R . J .

D imopou los A.

D i x i t K.B.

Dodge W.G.

L 9 /9

N 2 . 3 / 2 , N 2 . 4 / 1 *

K 1/8

N 2 . 2 . / 1 *

J 7 /11

L 11/3

J 5/8

G 6 /4

F 5 / 4 , F 5 /6

D 2 / 4 , D 2 /8

D 4 / 6

G 10/7

H 4 / 2 , H 8 / 7 , J 8 / 1

N 2 . 3 / 1 * , N 2 . 4 / 2

M 9 /9

K 7 /6

J 7 / 1 1 , K 7/3

M 6 /3

D 7 /2

N 2 . 5 / 3

G 4 /2

E 1/5

K 6 / 6

L 12 /4

H 3 /3

L 4 / 6

N 1 . 3 / 3

E 2 / 3 , M 2 /5

N 2 . 1 / 9

B 4 / 3 , F 2 /4

G 8 / 1 *

M 2 / 6

B 6 /2

G 2/3a

D 7/2

B 3 / 2 a , J 3 / 1 0

G 10 /7

H 4 / 5 , H 4 / 7

111

Doñea J .

Dong R.G.

Dong S .B .

Donten K.

D o s t a l M.

Dow l ing Ν .E .

Doyen J . J .

D r e n i c k R.F.

Dubo is C

Dubois J .

Du f f C G .

Du lac J .

Dustmann C . ­ H .

Β 1 / 3 , Β 3 / 1 *

Β 5 / 1 0 , Κ 3 /9

M 10 /1

J 4 / 8 , Κ 1 3 / 1 0

Κ 4 / 6

L 13 /4

F 3 / 1 , F 5 /10

K 8 / 4

N 2 . 1 / 9 , N 2 . 4 / 6

B 2 / 8 , B 4 / 3 , E 2 / 3 , J 9 / 4 , M 2 / 5 , M 7/E

K 1 1 / 5 , K 11 /7

J 7 /4

N 2 . 1 / 5

Edwards N.W.

Eggen D.T.

E i n z i g e r R .E .

Eke G.B.

E l b a z J .

E l fmann W.

E l l i s J . R .

E l ­ T a h a n H.

Emery A . F .

E n d e r l e G.

Engbaek P.

Enge l J . J .

Enge l R.

E n g e l b r e k t s o n

Enge l ke V . H .

Enn i s P . J .

Enomoto K.

E p s t e i n A.

Erb J .

Erbe H.H.

Erdogan F.

d ' E s c a t h a Y.

E t t e i E.

E t t o u n e y M.M.

Ezawa Y.

B 8 / 7 , J 2 / 1 *

D 7/3

C 4 / 3

F 6 / 6

M 8/5

L 8 /3

L 1 2 / 3

K 7/9

C 4 / 8 , G 4 / 1 *

B 6 / 1 *

G 1 0 / 1 *

L 3 / 2 *

F 1/5

J 6 / 5 *

B 3 / 7

L 13 /6

F 2 /8

F 2 / 1 , F 2 /2

N 2 . 1 / 4 , N 2 . 1 / 6

G 2/3

G 4 /2

G 8 / 1 *

H 6 / 5

J 2 / 7 , J 7 / 9 , K 5 / 7 , K 1 2 / 1 1 , L 9 /9

M 9/8

F a m i g l i e t t i M.

Fanning D.N.

F a r f a l e t t i ­ C a s a l i F.

F 7 / 7 , F 7/8

H 4 / 7

N 1 .1 /5

112

F a s o l i - S t e l l a P. Β 1/3

Fautz Μ. Β 2 /5

Fav rod J . - D . H 2 / 6 , H 4 / 8

F e l t e n P. H 5 / 5 , H 5 / 6

Feng W.W. M 11 /7

Ferguson F.R. L 5/2

F i e r o I . B . D 2 / 4 , D 2 /8

F i l i p p i G. K 11 /11

Fi I l o J . A . N 1 . 3 / 2

F i s c h e r D.F. K 12 /8

F i s h e r H.D. D 4 / 3

F l e i s c h e r C C . H 4 / 1 * , H 4 / 2

F le i schman T . S . G 4 /4

F o r a s a s s i G. L 9 / 6

F o r g i e S . H . H 3 / 4

F o r k e l M. B 3 /9

F o u i t T h . F 3 / 1 , N 2 . 4 / 7

Fox W.E. N 2 . 4 / 9

Frank M.V. D 6 / 4

Frank R. F 1/5

Frank T . G . N 2 . 3 / 6

F r e d e l l J . J 2 /4

F r i t z Κ. H 6 / 1 *

Fu L . S . L 5 /8

Fuchs H.P. D 2 / 1

F u j i t a Κ. K 1 3 / 7 , K 13 /8

Fukuda Y. L 1 2 / 8 , L 13 /9

F u r r e r H. K 6 /5

Gambarova P. J 4 / 9

Gamby D. M 3 / 3

Gang l M. H 6 / 5 , H 6 / 6

Gan taya t A . N . B 4 / 4 , K 6 /8

Garas F.K. H 3 / 7 , H 4 / 1 * , H 4 / 2

G a r c i a J . L . F 6 / 1 * , F 6 /3

G a r n i e r C. L 7 /8

G a r t n e r M. C 3 /5

Garwood S . J . G 3 / 1 *

G a r z a r o l l i F. D 2 / 1

Gauva in J . K 1 3 / 1 *

G a v a r i n i C. L 2 / 1 *

Gehl S.M. C 1/6

Gehlen P.C. G 9 /2

Gehr H . - L . C 2/2

113

Geidel W. F 4/6

Geradin M. M 7 / 1 *

Gerscha A. G 4/6

Ghoniem N.M. C 1/2

Ghosh A.K. D 4/7

Gibert R.J. B 4 / 1 * , E 6 /7 , F 2 / 1 , F 2/2

Giencke Ε. B 3 /9 , B 7 / 1 *

Gil lemot F. G 3/2

G i t tus J.H. C 3/8

G iu l i an i S. B 1/3, B 3 / 1 *

Giul iano V. E 4 /6 , K 1/9, K 9/2

Glahn M. L 6/4

Glazik J . L . , J r . E 6/5

Glenn L.A. N 2.5/5

Glöckner H. ­J . K 12/7

Gloudeman J.F. M 1/1*

Gluekler E.L. H 8/4

Gobert T. J 10 /1*

Godbout P. M 3/10

Gokhfeld D.A. L 1/7, L 2/3*

Golan D. J 10/5

Goldstein S. Β 3/2

Göller Β. Β 8/3, Β 8/4*

Gomez M.P. G 5/1*a

Goodall I.W. F 5/5, L 11/8

Goodman A.M. L 11/6

Goradia H. K 8/3, K 12/6

Gorholt W. H 5/1

Gorman D.J. B 5/1

Gorman M. K 2/5

Gortemaker P.C.M. L 4/6

Goto C M 4/3

Goto T. F 9/1, F 9/2

Gotoh Ν. K 10/7

Govindarajan S. D 5/6

Goudreau G.L. B 1/5, M 1/7*

Grainger B.N. H 5/2

Graubner U. J 5/8

Graveleau J .L . B 1/7

Gray W.H. Ν 2.2/4

Greco Α. M 6/5

Greenstreet W.L. H 3/2

Gregis J .L . E 2/3

Griesbach T . J . F 5 / 1 *

Griesmeyer J.M. C 1/2

114

Griffiths J.E.

Gri llenberger T.

Grosberg A.J.

Grover R.K.

Grover R.L.

Grünhagen A.

Guelicher L.

Guelin P.

Guerreiro Ribeiro S.V.

Gui linger W.H.

Güldenpfennig J.

Gunyasu K.

Gupta A . K .

Gupta D.C.

Gupta V .K .

Gürdogan 0 .

Guzman R.

Gvi I dys J .

F 5/5

F 8 /2

D 7 /6

D 4 /7

M 1 1 / 1

N 2 . 1 / 4

H 7 /1

L 1/6

L 7 / 6

K 8/7

H 5 / 4

K 11 /3

M 6 /6

K 1/6

F 8 /1

M 9 /6

K 2/3

Β 1 / 1 * , E 5/5

Habedank G.

Hab ip L .M .

Hagenson R .L .

Hag iwara H.

Hahn G.T .

Hai I f i n g e r G.

H a l l e u x J . P .

H a l l q u i s t J . C .

Hamanaka J .

Hammel J.W.

Han H.C.

Hancock S . L .

Hara F.

Harbourne B . L .

H a r d r a t h W.T.

Harkness S .D .

H a r r i a g u e S.

H a r t l e y C S .

Hassane in A . M .

H a s t i n g s I . J .

Haug E.

Hayase Y.

Hayhu rs t D.A.

Head J . L .

Heeschen U.

F 7 / 6 , K 12 /12

J 6 / 6 , K 12 /12

N 2 . 4 / 9

K 13 /9

G 9/2

B 8 / 2 * , B 8 / 4 *

B 1/3

L 9 / 5 , M 6 /8

F 9 / 1 , F 9 /2

N 2 . 1 / 7

J 2 /8

B 1 /6

B 5 /9

D 1 / 1 *

G 4 / 4

N 1 . 3 / 3 , N 2 . 3 / 1 *

D 1/2

L 7 /4

N 2 . 5 / 4

C 1/3

M 1/3

F 2 /8

L 5 /1 *a

D 7 / 6 , H 7 /4

F 3 / 3 , L 8/3

115

Heglin B.M.

Heidebrecht A.C.

Heine H.

Hellen R.A.J.

Hellen T.K.

Hellenberg H.W.

Hel ler M.

Helms R.

Henderson J .

Hennart J . C

Henning CD.

Henriksson T.

Hering W.

Herren M.

Herter J .

Hibbeler R.C

Higgins C.J.

H i l sdo r f H.K.

H i n t e r l e i t n e r H.

Hinton E.

H i r t C.W.

Hoang Y.S.

Hoffmann A.

Hofmann E.

Hofmann H.

Hoggatt D.

Hogge M.A.

Holland J.A.

Holman G.S.

Holtbecker H.

Holzlöhner U.

Holzmann M.

Horie T.

Hornby I.W.

Horvay G.

Hovingh J.

Howard G.E.

Hsieh B.J.

Hsieh S.Y.

Hsu T.R.

Hsueh P.S.

Hua L.C.

Huang C L . D .

Huang T.F.

J 3/10

K 11/8

J 8/2

F 5/4, F 5/6

M 5/4

D 7/4

F 7/4

G 2/3

L 5/2

F 4 / 4 , K 11/2

N 2 . 2 / 1 *

J 2/4

D 2 /4 , D 2/5

C 2 / 1 *

J 7/3

L 3/6

K 13/12

H 1/2, H 2 / 1 , H 2/3

H 5 /3 , H 6 /2 , H 6 /3 , H 6/5

F 5/3

B 6 / 2 , B 7/2

E 5/6

B 2 /8 , B 4 / 1 * , J 7 / 1 * , K 1 3 / 1 * , L 4 / 7 , M 5/6,

M 7/8

F 3/3

B 2/3

K 6 /4 , K 13/5

B 3 /4 , M 7 / 1 *

H 3/4

B 8/8

B 3/10

M 10/3

G 1/2, G 6/3

N 2.4/3

H 3 /5 , H 5/2

L 4/8

N 1.2/2, N 1.3/4*

K 7 /5 , K 13/12

L 9/3

N 2.2/5

C 3/12

J 7/9

M 3/6

H 1/6, M 11/2

J 2/9

116

Huber Α.

Hudak S.J., Jr.

Hudman G.D.

Hueckel T.

Hughes T.H.

Hughes T.J.R.

Hugot G.

Hult J.

Ishac M.F.

Issler L.

Itoh K.

Jamet P.

Janson J.

B 2/3

G 5/5

C 4/3

K 1/7

D 7/2

B 1/2

F 2/2

L 11/1*

Hundt J.C. H 1 / 3

Hunsbedt A. û 10/6

Husslage W. L 1 3 / 1

Ibanez P. < 7/5, K 13/12

Ichikawa K. J 4/1

*

Idriss I.M. K 1/3

Igarashi T. K 1 3 / 7

Iida K. L 12/8, L 13/9

Ikeda T. K 1 1 / 3

Ikonen K. F 6 / 4

Imazu A. F 3/5

Inbasakaran M. M 2 / 7

Inglebert G. L 3 / 2

*

Ireland D.R. G 6/1

*

Irisa Y. D 1 / 4

Irobe M. H 4 / 3

K 11/8

Ishiwata S. H 6 / 4

Isobata 0. J 4 / 6

F 4 / 1 *

I t o Y. L 1 2 / 8

' L 1 3 / 9

E 6/6

Iwasaki R. K 1 / 4

Iwata K. F 3 /7 , M 5 /5 , M 7/2

Jackson R.J. D 5 / 3

Jahns W. H 7 / 1

Jain A. G 4 / 1 *

Jakubowicz H. F 3 / 1

/ L 6 / 5

J 7 /1*

Jamieson H . C F 1 / 2

L 11/1*

Janssen G.T.M. L 13/1

Jeandidier C. K 13/1

*

117

Jeanpierre F. Β 4/1*, Κ 9/5

Jedlicka J. F 7/6

Jehlicka P. K 13/2, K 13/3

Jenkins D.A. C 3/13, L 7/4

Jiyawan R. B 5/11

Johnson D.L. C 4/3

Johnson J.J. K 3/6, K 3/8, K 7/2

Joly J. B 3/2

Jonas W. J 8/5, J 8/6*

Jones A.V. B 1/3, E 2/6, E 4/1*

Jones R.T. L 11/5

Jouris G.M. M 9/2

Jowett J. J 8/7

Jullien F. M 3/8

Kafka P. M 8/1*

Kaiser A. J 10/2

Kakodkar A. D 4/7, G 10/5

Kalinowski J.E. D 5/1*

Kalnins A. B 4/8

Ka l tho f f J .F. G 4 /5 , G 4/6

Kamal S.A. E 3/7

Kamil H. J 9 / 1 , K 5 /4 , K 6 /4 , K 6/8

Kangas M. F 6/4

Kanninen M.F. G 9/2

Känning J .L . B 5/6

Kano T. F 3 /7 , L 10/5

Kappler H. J 9/3

Kasai Y. K 12/3

Kasami H. H 1/7

Kaspar G. C 3/5

Kastenberg W.E. D 6 /4 , N 1.2/5*

Kathiresan K. G 4/3

Kato M. K 4 / 1 *

Katz F. B 6 / 1 * , B 6/6

Katzenmeier G. F 4/1*

Kawanishi K. F 6/2

Kawakatsu T. K 9/4, K 13/8

Kazimierzak B. D 5/2

Kearney D.W. N 1.3/1*

Kececioglu D. M 8/8

Kelly J.M. K 9/1*

Kemter F. K 12/7

Kendall K.C. E 4/1*, E 4/5

118

Kennedy J . M .

Kennedy N.A.

Kennedy R.P.

K e s k i n e n R.

Khatua T . P .

K i c i m a n O.K.

K i e d r z y n s k i A.

K i k u c h i M.

Kim Y . J .

K i r c h e r C A .

K i r m s e r P.G.

K i t a d e K.

K i t a g a w a H.

K i t a g a w a M.

K i v i t y Y.

K j a e r ­ P e d e r s e n N.

K l e i b e r M.

K l e i s e r K.

K l e i s t G.

Klemm W.

Knauf f M.

Kneuss R.

Knowles N.C.

Ko P .L .

Kobayash i A . S .

Koch V.

Ko l lmann W.

Kondo S.

Kön ig M.

K o n t e r A.W.A.

K o o r i Y.

K o p l i k B.

K o r d i n a K.

K o s i n s k i W.

Kos t G.

Kot C A .

K o t t a s R.

Kowalczuk G.

Kowalske D.

Kozek i M.

K o z i o l J . J .

K rakowsk i R.A.

Kramer J . M .

K r a t o c h v i l J .

K r ä t z i g W.B.

Β 1 / 4 , E 2 / 2 , E 6 / 3 *

L 13 /5

Κ 2 / 1 * , Κ 4 / 3

F 4 / 3

M 2 / 8 , M 6 / 6

J 10 /6

M 4 /4

G 7/2

C 3/12

K 13/5

H 1 / 6 , M 11/2

F 6 / 2 , K 9 / 4 , K 13 /8

G 1/6

F 9 / 1 , F 9 /2

J 10/5

D 1/5

L 6 / 6

H 2 /1

C 2/5

G 4/5

J 4 / 8 , K 13 /10

H 2/6

M 1/6

F 9 /4

C 4 / 8 , G 4 / 1 *

J 10 /7

B 3 /10

E 4 / 7

M 5 /1

L 1 3 / 1

K 7 / 1 *

K 8 / 3 , K 1 2 / 1 , K 1 2 / 6 , M 10 /7

H 1/5

L 2 / 6

J 9 / 1 , K 5 / 4 , K 6 /8

J 1 0 / 4 , N 1 . 3 / 6

H 1/2

L 7 /8

G 10/2

K 8 / 6

G 1 /7 *

N 2 . 4 / 9

D 7 /2

L 2 / 4 *

K 8 /2

119

Kraus S. G 10/6, K 12/4

Krause G. K 10/4

Krautwasser P. C 2/1* Krempl E. L 7/1 Krieg R. Β 6/5, Β 8/2*, Β 8/4* Krings W. M 7/6 Krishnan A. G 10/7 Krishnamoorthy CS. M 2/7 Krishnasamy S.G. L 13/5 Krivy J. J 9/6 Krutz ik N.J. J 9 / 1 , J 9 /8 , J 10/2, K 5/3, K 6/8

Kubota T. E 6/6

Kuczera B. C 1/8

Kukkola T. F 6/4

Kulak R.F. Β 2 / 1 * , E 1/2*, E 2 /5 , E 6/2

Ku lc insk i G.L. Ν 1.2/4, Ν 2.5/4

Kumar V. G 5/2

Kumpf H. H 6/2

Kunick A. C 3/3

Kuntze W.M. J 9/6

Kuperman S. H 8/5

Kuroda K. K 12/2, K 12/3

Kuroiwa M. H 4/3

Kurosaki A. K 8/6 Kurotobi M. F 5/7 Kushida H. K 13/4 Kussmaul K. G 2/3a Kuwabara Υ. K 5/5, K 9/4 Kuzay T.M. D 7/4 Kuzelka V. F 1/3 Kwee H.K. F 3/8

Laboudigue J.F. J 1/6, J 7/4 Laflen J.H. L 4/2 Lafore P. M 9/7 Lam P.C. K 5/6 Lamarre G.B. M 8/8 Lambert S.B. L 8/2 Landes J.D. G 3/4 Langhans J. J 1/9 Langui lie A. C 1/11 Lanning D.D. D 6/3 Lannoy A. J 10/1* Lardenoye L.M. F 9/5*

120

Larder R.A. Larkin P.A. Larsen E.M. Lasker L. Lassmann K. Lavake J. Lazzeri L. Lebey J. Lecarpentier F Lee D.J. Lee J. Lee J.J. Lee L. Lee L.H.N. Lee T.T. Lee W.H. Lee Y.S. Lehmann Th. Leigh K.M. Leimbach K.-R. Leis B.N. Lemaïtre J. Leonard J.W. Leoni R. Leridon A. Lestingi J.F. Lethert E.K. Levy A. Lewinski P. Liebecq G. Liebowitz H. Lievens F. Limberger E. Lin C J . Lin C-W. Lin H.C Lin T.H. Lin T.Y. Lin Y.J. Linder F. Litewka A. Litton R.W. Liu M.C.M. Liu T.H. Liu W.K.

L 9/5

J 2 /9

N 1 .2 /4

K 12 /6

D 3 / 1 *

D 2/5

F 3 / 6 , J 5 / 6 , K 1 / 9 , K 9 / 2 ,

F 5 / 1 0 , L 5 /3

G 10 /3

L 8 /6

G 6 / 2 *

C 3 / 1 3 , L 7 / 4

F 1/6

K 1 1 / 4 , L 12/5

B 2 /4

F 7 /1

L 7 /2

L 1 / 1 *

E 1/7

B 3 / 7 , F 4 / 6 , K 10/2

L 4 / 2

L 5 / 1 b *

B 4 / 6 , K 1 2 / 1 0 , M 4 / 6

F 7/8

C 4 / 2

B 5 / 1 3 , K 12/9

H 7/3

M 1/2

L 8 /4

B 3 /10

G 6 / 2 *

N 2 . 5 / 3

J 7 /3

J 2/8

K 1 1 / 6

L 9 /3

L 7 / 6

H 3 / 3

J 5 /4

J 9 /8

L 12 /9

M 2 / 6

L 7 / 1

K 1 1 / 9 , L 9 /8

B 1/2

K 1 1 / 1 0 , K 11 /11

121

L i u Y .Y.

L i v o l a n t M.

Lo T . Y .

L o c c i J . M .

L o c e f f F.

Long C . J .

Louve t P.

Love W . J .

Lu S . C . H .

L u c i a A .C .

Ludwig Α.

Ludwig P .W.P.H.

L u i H . C

L u t h r a V . J .

D 3 /5

Β 4 / 1 » , Κ 9 / 5 , Κ 1 3 / 1 *

Κ 3 /7

G 9 / 4 , Μ 1/3

Κ 7 / 4 , Κ 1 1 / 9 , L 9 /8

Ν 2 . 2 / 4

Β 1/7

C 4 / 8 , G 4 / 1 *

Β 8 /8

Μ 8 /5

Β 6 / 1 * , Β 6 / 5 , Β 6 / 7

F 9 / 5 *

Β 2 /4

C 4 / 8

Ma B.M.

Ma D.

Macch i G.

MacEwen S.R.

MacGregor J . G .

MacNeal R.H.

Mager T .R .

M a i e r G.

M a l c h e r L.

Ma lkus D.S.

Malmberg T .

Mamoun M.M.

Man J .

M a n f r e d i E.

Manze l R.

Marbach G.

M a r c h a t e r r e J . F .

M a r c h e r t a s A . H .

Mark K.

Marr W.W.

M a r r i o t t D.L .

M a r r u j o F.G.

M a r s t o n T . U .

M a r t i n A.

M a r t y n e n k o M.E.

Maruyama T.

Masao T .

Masao T .

Masuda M.

D 2 / 7 , Ν 2 . 3 / 7

Η 8 / 6 , Κ 12/5

J 3 / 3

F 1/2

J 3 / 4 , J 4 / 2

B 4 / 9

G 1/7*

L 3 / 1 *

K 1 3 / 2 , K 1 3 / 3

M 6 / 1 *

E 5 /6

D 5/8

G 1/2

L 9 / 4 , L 1 2 / 4

D 2 /1

C 1/11

E 2 / 1 *

E 6 / 2 , H 8 / 1 * , H 8 / 2

K 7/7

D 7 /4

M 8 / 7

F 8 / 1

G 1 / 4 , G 2 / 6 , G 2/7

F 6 /3

L 1/7

G 6 / 1 *

K 1/4

K 7 / 1 *

N 2 . 4 / 3

122

Mate ra R.

M a t t e a z z i S.

M a t t h e e s W.

Mat thews J . R .

Maurer W.

M a x w e l l D .E .

Maynard C U .

Mayr K.

M a z z a r e l l a C

M c C a r v i l l e T . J .

McCauley E.W.

McHenry H . I .

M c L o u g h l i n S.

McMahon P.M.

McMaster W.H.

Mehner A.W.

Mehta S .K .

M e i e r W.R.

Me l i g i A . E .

Menegh in i Α.

M e r c i e r F.

Merckx K.R.

Meschkat R.

M e s k o u r i s K.

Messemer G.

Meyer C.

Meyer J . E .

Meyer zu r C a p e l l e n H.

Meyers B . L .

M i d d l e t o n J .

M i k i K.

M i l l a r d Α.

M i l l e r A . K .

M i l l e r C M .

M i l l e l P.

Mi Ine I .

M i n a t o Α.

M i s f e l d t I b .

M i t c h e l l A . B .

M i t t e r b a c h e r P.

Miyamoto Η.

M izuno Ν.

M izuno S.

M i z u t a M.

Mohr C L .

L 1 2 / 4 , Ν 2 . 2 / 3

L 1 2 / 6

M 10/3a

D 7 / 1 *

N 2 . 1 / 6

L 13 /3

N 1 . 2 / 4

H 6 / 6

L 3 / 4

N 2 . 5 / 4

B 8 / 1 * , B 8 / 8

N 2 . 5 / 7

F 3 /4

J 7 /6

B 1/5

C 2 / 1 *

C 3 / 1 0 , C 3 / 1 1

N 1 .2 /2

K 1 0 / 6

F 3 /4

G 8/2

D 4 /5

J 8 / 5 , J 8 / 6 *

K 8 /2

N 2 . 1 / 4

M 10/4

D 3/5

D 5/2

J 7 /6

M 3 / 1

D 5 /9

G 1 0 / 3 , L 4 / 7 , N 2 . 1 / 9 , N 2

D 3 /3

C 2 /4

C 1/11

G 1/3

N 2 . 4 / 4

C 4 / 7

F 1/2

H 7/2

G 7 / 2 , J 8 / 9

K 13 /4

K 1 0 / 5 , K 10 /9

D 1/4

D 6 / 2 , D 6 /3

123

M o i r R.W.

Mondkar D.P.

M o n s l e r M . J .

Montagnan i M.

Moore W.E.

Moosecker W.

M o r e l Α.

Morgan P . L . T .

Morgand P.

M o r i b e I .

M o r j a r i a M.

M o r r i s E.

Mor rone A.

M o r t g a t C.P.

Moses G.A.

Mös inge r H.

Mo tohash i S.

Mroz Z .

M u e l l e r C

Mukher jee Β.

Muk h e r j e e S . ·

Mukhe r j ee S . N .

Muki R.

M ü l l e r G.

M ü l l e r W.Ch.

M u l l e r ­ L y d a I .

Munro J .

Murakami S.

Mu r ray D.W.

M u r t y K .L .

Muto K.

M u t z l J .

N 1 . 1 / 3 *

F 7 / 3 , M 1/4

N 1 .2 /2

E 3 / 1 *

L 9/8

H 1/4

M 3 / 7 , M 3 / 8

H 4 /2

F 5/9

K 13 /4

L 4 / 3

E 2 /4

K 8 /8

K 3 / 4 , K 3/5

N 1 . 2 / 4

B 6 / 1 *

K 12 /2

L 2 / 2 *

K 6/5

F 5 /11

L 4 / 3

K 6 /9

M 10 /1

L 8/3

B 4 /2

D 3 /6

L 3 / 1 *

L 1 / 4 * , L 1 2 / 1

J 3 / 4 , J 3 / 5 , M 2 / 4

C 3 / 6

K 8 / 5 , K 1 2 / 2 , K 12 /3

H 5 /3

Nagato K.

Nahavand i A . N .

N a k a g i r i S.

Nakamura K.

N a k a n i s h i T .

Nakatogawa T .

Naka tsuka M.

Nakayama S.

Narayana A . D .

Nash W.A.

N a s h i r o T .

L 8 /1

B 3 /8

G 1/6

F 3 / 5 , L 10/5

L 13 /10

F 6 / 2 , K 11 /3

D 3/2

F 2 /8

L 7 /7

M 11 /6

L 2 / 6

Naus D .J .

Needleman Α.

Neef W . S . , J r .

Nei I son A . J .

Ne l son T . Α .

Nemat-Nasser S.

Nemet J .

N e r l i G.

N e s i t k a A.

Newman J . C , J r .

Ng D.H.Y.

Nguyen Dang H.

N i c ho l s B .D .

Ni i n o T .

N i s h i g u c h i I .

N i s h i k a w a H.

N jo D.H.

Noda N.

No r r i s D.M.

N o t l e y M . J . F .

Nova R.

Nuno H.

H 3 / 6

L 1/3*

N 1 . 1 / 3 *

J 8 /8

K 3 /10

N 2 . 5 / 2

H 1 / 1 « ,

L 13 /7

H 6/5

G 7/3

L 12/5

L 3 / 3

B 7 /2

K 11 /3

M 9 /8

F 6 /2

G 1 / 1 *

C 1/5

B 1/5

C 1/3

K 1/7

D 1/4

H 6/1*, H 6/2

Obernhuber 3. Oberpichler R. O'Brien T.P. 0'Connor M. Odar E. Odette G.R. O'Donnell W.J. Oehlberg R. Ogiwara Y. Ogura K. Ohkawa I. Ohmori N. Ohnami M. Ohno T. Ohnuma H. Ohsaki Y. Ohsawa M. Ohta T. Ohte S. Okabe M. Okada K.

K 5 / 1 *

H 5 /7

J 8 /1

C 2/5

M 10/5

N 2 . 3 / 3

L 6 / 1 * ,

D 6 / 5 ,

K 5 / 5 ,

G 1/6

K 1/4

J 4 / 4

F 9 /1

H 4 / 3

H 4 / 9 ,

K 1/4

L 1 2 / 8 ,

K 7 /8

J 8 /9

M 9/8

J 4 /5

L 10/3

D 6 / 6

K 9 /4

J 4 /5

L 13 /9

125

Okamura H.

Ok ren t D.

O land C.B.

O l d f i e l d W.

O l i v e r R.M.

O lsen C S .

O ' N e i l l R.F.

Ople F . S . , J r .

O r k i s z J .

Ortman M.S.

O s t e r i e B.

O t t e r N.R.

O t t o s e n N.S.

Owen D . R . J .

F 5 / 7 , K 2 /6

C 1 / 2 , C 1 / 4 , C 1 / 1 0 , N 1 . 2 / 5 *

H 3 /2

G 2/7

K 1/10

C 1/9

N 1 .3 /8

H 3 / 1 *

M 7 /4

N 1 . 2 / 4

B 4 / 2

L 11 /5

H 2 /5

F 5/3

Pab isek E.

Pagano R.

Pagay S .N .

Pa i D.H.

P a i d o u s s i s M.P.

Pa l N.

P a l a m i d e s s i A.

Pa lgen L.

Palusamy S .S .

P a n d a r i n a t h a n V .G .

Pan i sko F .E.

Panzeca T .

P a r a n j p e S.R.

P a r i s P.C.

Pa rke r J . V .

Pa rmegg ian i A.

P a s o t t i G.

P a t e l M.R.

P a t e l Y .A .

P a t t a n a y a k A . K .

Pauwels C.

Paxson E . B . , J r .

Peano Α.

P e c h e r s k i R.B.

Pedersen D.R.

Peehs M.

Pe l l i s s i e r - T a n o n Ρ

Pende rg rass J . H .

P e r l a H.F.

L 11 /7

Κ 11 /11

Κ 7 /4

E 3 / 7 , L 8/5

Β 5 /3

Κ 4 / 6 , Κ 1 0 / 5 , Κ 10 /9

Ε 4 / 4

L 3 /3

F 5 / 2

M 2 /7

D 6 /3

L 3 / 4

D 3 /7

G 5 /1*a

Κ 6 / 7 , L 8 / 6

F 7/7

N 2 . 2 / 3

D 1 / 1 *

B 3 / 2 a , M 10/2

M 6 / 6

C 4 / 2

M 5/2

M 7/7

L 7 /3

D 7/4

D 2/5

G 8 / 1 *

N 2 . 3 / 6

K 2 / 1 *

126

Pe r r i n R . C

Perzyna P.

P e t e r s W.H.

P e t r e q u i n P.

P e t r i n ä P.

P e t r o s k i H . J .

P e t t i g r e w M . J .

Pezz i G.

P f e i f f e r Α.

P h i l i p G.

Ph i l i p p a c o p o u l o s A . J .

P h i l l i p s J .

P h i l l i p s J.W.

P i a t t i G.

Pi cau t

P i e t r i P.

P i s t e r K .S.

P i t t n e r K . ­ J .

P l a c e T .A .

P loege r D.W.

Poh l W.

P o l i z z o t t o C.

P o l l a r d L.W.

Ponsot J .

P o p e l a r C.H.

Porowsk i J . S .

Possa G.

P o t t i n g e r R.

P o t t s R.

Pouyet P.

P o w e l l G.H.

P o w e l l J . R .

Prachuk tam S.

P r a n t l G.

P r a t t R.

P r o s t J . P .

P r o t h e r o D.H.

Pug h C E .

P u l l i a m T . H .

D 5/5

L 1/5

G 4 / 4

L 6 /5

J 1/4

E 5 / 2 , E 6 / 1 * , E 6 /5

L 8 /2

K 1/9

J 8 /4

J 9 / 7 , K 2/7

K 8 /4

L 11 /6

B 2 / 6

L 1 1 / 4 , L 1 2 / 4 , L 1 2 / 6

J 3 /8

M 3 /3

K 1/10

J 9 /3

F 5/8

E 4 /2

E 1 / 6 , E 5 / 1 , J 10 /7

L 3 / 4

N 2 . 4 / 5

G 8 /2

G 9/2

L 6 / 1 * , L 10/3

F 7 /7

E 1/7

N 2 . 2 / 3

J 3 /8

K 1 0 / 1 * , K 1 0 / 3 , M 1 / 4 , M 2 / 6

N 1 .3 /2

F 4 /5

G 1 / 1 *

M 4 / 2

F 3 / 1 , G 9 /4

N 2 . 2 / 3

L 12/3

M 4 / 3

Q u a r t a p e l l e L.

Q u i r k A.

B 3 / 1 *

G 2/4

127

Rabbe P.

R a d i n i R.R.

Raeder J .

Ragheb M.M.

Rag land W.A.

Rahe ja R.D.

Ra ju I . S .

Ram K.S.

Ramani D.T.

Ramamurthy T . S .

Ramm E.

Ranganath S.

Ran jan G.V.

Rao A . K .

R a r d i n D.C.

Rash id Y .R .

Rau P.

Rau tenberg J .

Rawls J . M .

Raymont J . M .

Rea le S.

Rebora Β.

Reddy D.V.

Redmer J .

Reed J.W.

Reed R.P.

Reeves C F .

R e i c h M.

Remy F.N.

Renard J . D .

Rest J .

Reu te r W.G.

Reuther T .C .

Reymann A.

R i c c i M.V.

R i c h a r d s o n J . E .

R i c h t e r P . J .

R iech H.

R ieck P . J .

R i e g e r M.

R i e r a J . D .

Riesemann von W.A.

R igby G.L.

R i g h e t t i G.A.

R issone P.

G 8 / 1 *

J 7 /9

N 2 . 3 / 2

N 1 . 2 / 4

E 3/5

Β 3 / 2 a , Κ 1 0 / 6 , M 9 /5

G 7/3

Β 5 /11

B 3 / 2 a , D 3 / 8 , J 3 / 1 0 , M 9/5

G 10/7

J 6 /9

G 1/5

D 3 / 3 , M 4 / 3

G 10 /7

D 5/8

D 6 / 1 *

H 6/2

F 9 /3

N 1 . 1 / 2 *

B 7 /4

F 5 / 1 3 , L 13 /7

H 2 / 6 , H 4 / 8

K 4 / 7 , K 7/9

M 6 / 3

K 4 / 4 , K 13/5

N 2 . 5 / 7

K 4 /5

N 2 . 1 / 1 *

B 5 /7

J 9 / 4 , K 5/2

C 1/6

F 5/8

N 2 . 3 / 3

C 3 /5

N 2 . 2 / 3

L 9 /9

K 4 /3

J 8 / 5 , J 8 / 6 *

K 4 /2

N 1 .1 /5

J 9 /2

K 4 / 3

D 1/7

J 5/6

L 1 3 / 7

128

Rivard W.C.

Rizkalla S.

Roberge Α.

Robert J.

Robinson D.M.

Robinson G.C

Robinson J.N.

Robutti G.

Roche R.L.

Rodet E.

Rodriguez C.

Roemer R.E.

Rogalska E.

Rogers R.J.

Rolstad E.

Romander C M .

Ronzoni E.

Rouiller F.

Roux Y.

Row D.G.

Rowe D.S.

Rozenblum G.

Rubinacci G.

Rüdiger E.

Rustagi R.S.

Rutherford D.H.

Β 6/2

J 3/4, J 4/2

Η 5/6

C 1/11

L 12/3

H 4/5

G 3/1*

H 2/5

L 4/7, L 5/3, L 7/8

M 3/7

H 2/6, H 4/8

F 7/1

L 12/9

F 9/4

C 4/5

E 1/3, E 5/4

H 2/5

K 9/5

N 2.4/6

κ 10/1*

D 6/5

M 3/7

N 1.1/5

J 8/5, J 8/6*

D 4/6

K 6/8

L 12/2, M 9/3

Sacchetti N.

Sackman J.L.

Sadakov O.S.

Sadowski A.

Sage F.

Sahay B.

Saiga Y.

Sakaguchi Y.

Sako K.

Sakuta M.

Sakuyama T.

Salz W.

Sangalli D.

Sasagawa K.

Satoh S.

Sattele J.M.

Saurwein J.J.

N

K

L

J

J

B

F

G

N

H

D

E

J

M

M

J

C

2.2/3

9 / 1 *

1/7

4 /8 ,

8 /4

5/11

9 / 1 ,

7/2

2.4/4

1/7

3/2

5/6

3 / 3

1/5

1/5

o /9

2 /4

K 13/10

F 9/2

129

Savino E.J. Sawhney S.S. Sawruk W. Scala M. Scavuzzo R.J. Schaefer A.O. Schaller K. Schamaun J.T. Schankula M.H. Scheibe W. Schimmelpfennig K, Schlafer W., III Schlechtendahl E.G. Schmidt G. Schmitt R. Schmitt W. Schneider U. Schnell W. Schnellenbach G. Schoeberle D.F. Scholl K.-H. Scholl R.E. Schomburg U. Schöning J. Schrader K.H. Schuëller G.I. Schultz K.R. Schulz H. Schumann U. Schürkamp H. Schuster H. Schwiers H.G. Scibak W. Scott M.E. Seaman L. Seeberger J. Seed H.B. Seino S. Sen S.K. Senski G. Sermet E. Server W.L. Seth V.K. Shaffer D.H. Shah V.N.

D 1/2

C 3 / 1 0 ,

M 3 /9

E 4 / 6

K 5/6

G 1 /7 *

L 6 /5

J 8 /12

D 1/7

L 12 /7

H 3 / 8

K 7/2

B 6 / 1 * ,

K 12 /7

L 12 /7

M 8 / 1 * ,

H 1/5

M 1 1 / 3

H 3 /8

B 1 / 4 ,

F 8 /2

M 10 /6

M 6 /3

H 6 / 4 ,

J 10 /2

J 9 / 3 ,

N 1 . 2 / 3

L 6 / 4

B 6 / 1 * ,

E 1/6

L 13 /6

H 6 / 3 ,

J 4 / 8 ,

D 2 /8

G 6 /4

H 1 / 2 ,

K 5 /2

E 6 / 6

J 3 / 1 ,

C 3 / 3 ,

F 6 / 1 *

G 2 / 1 *

G 10 /7

M 9 /2

K 8 / 7

C 3 / 1 1

B 6 / 6

M 8 / 6

E 6 / 3 *

H 7 /1

M 8 / 1 *

k

B 6 / 4 ,

H 6 / 4 ,

K 1 3 / 1 0

H 2 / 3

J 7 / 6

C 3 /5

B 6 / 7

H 7 / 2 ,

130

Shankar S. J 9 / 1

Shannon T . E . N 1 . 1 / 2 *

Shao L. F 2 / 6 *

S h a r a b i M.N. D 6 / 1 *

Sharpe R.L. J 9 / 1 , K 5 / 4 , K 6 /4

Sherbourne A . N . L 13/5

S h i b a t a H. K 2 / 6 , K 4 / 1 * , K 1 1 / 3

Sh ida S. J 8 /9

Sh ih C F . G 5 / 2 , G 6 /5

S h i m i z u M. K 13 /9

S h i r a k i K. K 1 1 / 3 , K 13/8

Shockey D.A. G 6 / 4

S iang H.H. H 1/6

S i g a l G.B. K 8 /8

S i n h a R.K. G 10/5

S i l v a M.A.G. F 7/5

Simmonds S . H . J 4 / 2

S i n g h M.P. J 5/7

S i n g h S. J 5 / 7 , K 1/6

S k e r g e t P. D 3/4

S k r i k e r u d P .E . K 8 /9

S l i t e r G.E. J 8 /12

Smi th C O . M 8 /9

Smi th C.W. G 4 /4

Smi th E. C 4 / 4 , D 2 / 6 , G 2 / 6 , G 5/4

Sm i th F.W. F 5/8

Smi th I . G . H 4 / 6

Smi th R.D. K 3 / 1 *

Smolderen J . J . B 3 /10

Snyder M.D. M 2 / 1 *

Soenen M. N 2 . 5 / 3

Somma E. M 3/8

Soran P.D. N 2 . 4 / 9

Spadoni M. N 2 . 2 / 3

S p c i d e l S .R. H 4 / 4

Spence J . L 4 / 1 *

S p i l k e r H. F 9 /3

S t a h l k o p f K . E . G 1 / 4 , G 2 / 6

S tangenbe rg F. J 7/5

S t a n i f o r t h R. E 1 / 1 *

S t e e l e Ch.R. M 4 / 3

S t e e l e L . E . G 1 /7*

S t e e l e W. C 1/4

S t e i n e L .R . B 6 /2

S t e i n e r H. D 2/2

131

S t e i n h i I be r H.

S t e l l i n g H . - A .

S tephen J . D .

S tephenson M.

S t e r k e l H.P.

S t e t s o n M.B.

S tevenson J . D .

S t o c k t o n F.D.

S t o d d a r d W.C.T .

S t o k e r J . R .

S tone C M .

S t o n e r R .E .

S t o r a J . P .

S t o u f f e r D.C.

S t r e i b l B.

Strona P.P.

S t u r a D.

Subramonian N.

Subudhi M.

Sugano Y.

Sugiyama N.

Sun P.C.

Suwabe Α.

Suzuk i Α.

Suzuk i Κ.

Sva lbonas V.

S v i a t o s L a v s k y I . N .

Swamy S.A.

Swanson J . A .

Swel im H.

Swenson D.V.

S z c z e p i n s k i W.

K 1 3 / 2 , K 1 3 / 3

Η 7/5

D 1 / 1 *

Η 8 / 6

K 10/2

K 4 /5

J 1 / 1 * , K 2 / 5 , K 1 1 / 1 *

L 4 / 8

Ν 2 . 2 / 4

M 1/6

L 13 /8

J 2 /9

C 1 / 1 *

L 7 /7

Ν 2 . 4 / 7

Κ 1 1 / 1 0

Κ 6 /6

G 6 / 2 *

Κ 1 2 / 6 , Μ 10 /7

Μ 11 /4

Κ 13/4

Κ 4 /4

Κ 5/5

L 10 /4

Κ 13/9

Μ 5 /7

Ν 1 .2 /4

L 7 /2

Β 4 / 6

Κ 12 /12

D 5 / 1 *

L 1 0 / 1 *

Tabakman Η.D.

T a g a r t S . W . , J r .

Takahash i T .

T a k a s a k i Y.

Takeda H.

Takemor i T .

T a k e u t i Y.

Takezono S.

Tak i kawa Ν.

Tamaki T .

Tanabe M.

J 5/4

J 1/2

J 4 /4

Κ 7 / 1 *

F 3 / 7 , M 5 / 5 , M 7 /2

Κ 5 / 5 , Κ 9 /4

C 1 / 5 , C 1 / 7 , M 11 /4

M 4 / 7 , M 4 / 8

L 8 /1

K 13/4

M 7 /2

132

Tanaka E.

Tanaka H.

Tanaka K.

Tanaka N.

Tang H.T .

Tang J . H . K .

Tanigawa Y.

Tao K

T a r o n i Α.

Tas Η.

T a t r o R.E.

T a y l o r C.

T a y l o r L .M.

T a y l o r R.L.

T e a s d a l e R.W.

T e s s i e r J . H .

Tezduyar H .T .

Thangam Babu P.V.

Theuer E.

Thomas R.G.

Thomson S . L .

T i n g E . C

T i n g Y .D .

Többe Η.

T o b i n R . J .

Tohdo M.

Toka rz F . J .

T o m a s s e t t i G.

Tominaga S.

Too J . J . M .

T o r r e y M.D.

Tow D.

T r a n t i n a G.G.

T r b o j e v i c V .M .

T r e m b l a i s Α.

T r u f f e r t J .

T s u c h i y a H.

Tsugawa T .

T s u r u t o C.

Tsushima Y.

T u r l a n d B.D.

T u r u l a P.

T v e r g a a r d V.

L 1 2 / 1

K 7/8

K 5/5

J 4 / 6

B 5 / 4 , D 4 /1

J 7 / 1 1 , K 7 / 3 , K 11/5

C 1/7

M 4 /8

N 2 . 1 / 8

N 2 . 5 / 3

N 1 .3 /8

B 3 / 3 , F 5 /3

B 5 /4

M 4 / 1 *

N 2 . 4 / 9

E 3/5

K 11 /4

K 4 / 7

F 7 /4

H 7/4

N 1 .3 /5

B 5 / 6

C 1/10

D 5/2

E 4 /2

K 1 / 1 * , K 1/2

K 3 / 1 *

F 5 / 1 3 , L 13 /7

G 6 / 1 *

C 4 / 1 2

B 6 /2

K 7/2

N 2 . 4 / 8

M 1/6

F ill

D 1 / 8 , D 1/9

K 13/9

K 8 /5

F 6 /2

K 13 /4

B 3 /5

J 10/4

L 1 /3*

133

Uchida T. Uchiyama S. Udoguchi T. Ueda M. Uesugi S. Ujiie K. Umeda T. Umemoto T. Uragami K.

J 4/4 K 7/8 F 9/1, F 9/2, L 13/10 J 4/5 F 3/7 K 8/5 F 9/1 F 2/8 L 10/5

Vagliente V.N. Vaish A. Valathur M. Valente G. Valentin R.A. van Campen D.H. van den Hoek M.J. van de Ree H. Vanderglas M.L. van der Hoogt P.J.M, van Goethem G. van Renterghem J. van Rij H.M. Vardanega C Varga T. Vaz L.E. Veith H. Veluswami Μ.A. Vendhan C P . Verbiese S. Verpeaux P. Verzelletti G. Vidard M. Vi Hard Β. Vitale E. Vitiello E. Vivoda E. Vlach B. Vogelsang W.F. Vogl W. Votava E.J. Vrillon B.

Κ 3 /7

Κ 2 / 3

J 5 /7

Η 2 /4

Β 2 / 6 , L

Β 5 /2

Ε 5 / 1 , J

J 9 /5

F 5 /11

Β 5 /2

Β 6 / 3

Ν 1 .1 /5

Μ 2 / 3

Κ 6 / 6

G 1 / 1 *

Μ 2 / 2 *

G 2 / 3

L 4 / 8

M 11 /6

Β 6 / 3

Β 2 / 8 , J

E 4 /4

Β 3 /2

E 6 /7

L 9 /4

M 3/5

K 11 /11

G 6 / 3

N 1 .2 /4

D 2/5

F 2 /3

F 3 /2

9 / 3

9 / 5

7 /1

134

Waas G.

Wada Y.

Wahi K. K.

Waine B.R.

Walker J . S .

W a l l r o t h C F .

Wa l l uschek W.

Walser A.

W a l t e r P.

Wang C.Y.

Wang P.C.

Ward P.

Warnke E.P.

Washby V.

Waszczyszyn Z .

Watabe M.

Watanabe S.

Watanabe T.

Watanabe Y.

Watson R.D.

Wazzan A .R .

Weber W.

Webster F.A.

Wehner T . R .

Wei R.P.

Weimar P.

We issbacher L.

W e i t h ä u s e r H . J .

We l i e i n R.

W e l l s J . E .

Weppe l ink H.

Wesenberg D.L.

West P.H.

Wester H . J .

Wheaton R.

Wh i tehead J . P .

W i f f e n F.W.

W i l h e l m H.

W i l k i n s o n J . P . D .

W i l l a m K . J .

W i l l a s c h e k J .

W i l s o n R.E .

W i l s o n W.K.

W inke l G-

W i n k l e r S.

K 6 / 1 * , K 6 / 3

F 3 /7

L 13 /3

H 4 / 1 * , H 4 / 2

B 2 /6

C 2/4

H 6 / 3

J 3 /7

N 1 .2 /2

B 1 / 1 * , B 1 / 8 , E 2 / 2 , E 5 / 3 *

K 8 /4

M 4 /2

H 7/2

E 1/7

L 11 /7

K 1 / 1 * , K 1/2

J 4 / 4

F 2 / 8 , M 6 /4

J 4 / 1 *

N 1 .2 /4

C 1 / 4 , C 1 /10

K 6 / 1 *

K 4 /4

D 7 /3

G 5/5

D 2/2

H 1 / 1 * , H 2/2

J 8 / 3

M 8 / 6

K 3/2

B 5/2

L 13 /8

E 4 /5

H 7/3

K 2 /3

D 4 /8

N 2 . 5 / 1 *

C 3 /5

G 5 / 2 , N 2 . 4 / 8

M 2 / 2 *

C 2 /6

D 7/4

L 13 /4

J 9 /8

G 4 / 5 , G 4 / 6

135

Wissmann J.W. Witt A. Witt F.J. Wojewodski W. Wolf J.P. Wolfer W.G. Wolff P.H.H. Wong C Woo H.K. Wrana Β. Wu S.-C. Wu S.T. Wu T.S. Wullaert R.A.

M 7 /3

H 6 /6

G 2 / 2 ,

L 8 /4

Κ 5 / 1 * ,

Ν 1 .2 /4 .

Η 8 /7

J 3 / 5 ,

M 11 /2

M 7 /4

M 5 / 3

M 10/5

D 4 / 4 ,

G 2 / 1 *

G 3 /3

K 8 /9

, N 2 . 3 / 3

M 2 / 4

D 5/8

Yagawa G. Yamada H. Yamada K. Yamada Y. Yamakawa T. Yamamoto S. Yang C.C. Yeh G.CK. Yerkees A. Yilmaz C. Yoon K.K. Yoshimura H.R. Yoshinaga T. Yoshioka Y. Yoshizawa H. Youssef M.Z. Yun C.B. Yuuki R.

F 2 / 8 , L 5 / 4 , M 6 / 4 , N 2 . 4 / 3

E 5/2

J 4 /7

F 9 / 2 ,

J 5/2

K 7 / 1 *

K 12/4

F 8 /5

E 1 / 1 * ,

B 4 /5

C 3 / 6

J 8 / 1 2

K 10/7

J 4 / 5 ,

J 8 /9

N 1 .2 /4

K 8 /4

G 1/6

M 9 / 8

E 4 / 1 *

H 1/7

Zarka J .

Z e h l e i n . H .

Z e i s s e r P.

Z e i t n e r W.

Zemann H.

Zeuch W.R.

Z i e b s J .

Z i e g e l d o r f S.

Zimmerman T . K .

Z o l z e t t i c h A.

L 3 / 2 *

E 6 / 4 * ,

C 2/5

M 6 /7

H 1 / 1 * ,

E 3/4

G 2 /3

H 2/1

B 1/2

M 3/8

N

H

2 . 1 / 4

2 /2

136

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