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TRANSACTIONS
of the
3rd International Conference
STRUCTURA
MECHANICS
IN REACTUR
TECHNULOG
LONDON, United Kingdom, 1-5 September 1975
Vol. 5 METHODS FOR STRUCTURA
ANALYSIS
Part M. Methods for Structural Analys I
Compiled by:
Thomas A. JAEGER, Bundesanstalt für MaterialprüfurB Bin Conference Organisation by:
International Association for Structural Mechanics in Reactor Technology
Commission of the European Communities (CEO, Brussels
The British Nuclear Energy Society (BNES)
in co-operation with:
Bundesanstalt für Materialprüfung (BAM), Berlin
Associated Nuclear Services, London (ANS)
Central Electricity Generating Board (CEGB)
Electric Power Research Institute, Palo Alto, Cal. (EPRI)
Franklin Instituteh Laboratories (FIRL), Philadelphia.
Massachusetts Institute of Technology School of Engineering, Cambridge
Mass. (MIT)
South of Scotland Electricity Board (SSEB)
Co-sponsoring Societies
Kerntechnische Gesellschaft (KTG)
American Nuclear Society (ANS)
American Society of Mechanical Engineers (ASME)
Institution of Mechanical Engineers (I Mech E)
Publication Management
Mme. J. Stalpaert, Commision of the European Communities,
Directorate General „Scientific and Technical Information and Information
Management-' (D.G.XIII) - Brussels
Executive Committee
Howard Gott (Immediate Past-President BNES) - General Chairman
W.J. Prior (Vice-President, BNES) - Deputy General Chairman
R.K. Appleyard (CEC)
Gordon Brown (President, BNES)
F. Caccia-Dominioni (CEO
Henry M. Carruthers (BNES) (Organisation Chairman)
Thomas A. Jaeger (BAM) (Scientific Chairman)
R.W. Nichols (I Mech E)
Organisation Committee
Henry M. Carruthers - Organisation Chairman
B. Edmondson (CEGB)
B.A. Keen (BNES)
Mme J. Stalpaert (CEO
Prof. G.N. Walton (BNES)
P.H.W. Wolff (Vice-President, BNES) TRANSACTIONS
øf the
3rd International Conference on
STRUCTURAL
IN REACTOR
TECHNOLOGY
LONDON, United Kingdom, 1-5 September 1975
Vol. 5 METHODS FOR STRUCTURAL
ANALYSIS
Part M. Methods for Structural Analysis
Compiled by:
Thomas A. JAEGER, Bundesanstalt für Materialprüfung (BAM), Berlin
Conference organization by:
International Association for Structural Mechanics in. Reactor Technology
and
Commission of the European Communities, Brussels
The British Nuclear Energy Society, London
in cooperation with:
BAM ANS CEGB EPRI FIRL MIT SSEB
Berlin London London Palo Alto Philadelphia Cambridge Glasgow
Cal. Pa. Mass. 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, 1975
All rights reserved. No part of this publication may be reproduced, stored in a retrieval system, or trans­
mitted, in any form or by any means, electronic, mechanical, photocopying, recording or otherwise,
without the prior permission of the copyright owner.
II "Structural mechanics are at the very centre of nuclear tech­
nology, because it is the safe, reliable structure that counts.
The major problems in building today's reactors and develo­
ping tomorrows are mechanical and structural. "
Professor Dr. Altiero SPINELLI
Member of the Commission of the European Communities,
in his Foreword to the Proceedings of the 1st SMiRT Conference
PREFACE
REACTOR TECHNOLOGY requires a synthesis of many skills. The rapid development of
reactor technology has given rise to a multitude of problems in the area of STRUCTURAL
MECHANICS, and the ability to solve these structural mechanics problems encountered is
of vital importance for achieving economic, reliable and safe exploitation of nuclear power.
The unprecedented combination of mechanical and structural requirements posed by reac­
tor technology are both a great challenge and a great stimulus to the field of structural
mechanics which 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 computerme-
thods and quality control. Great advances have been made during the past decade; howe­
ver, structural mechanics and related problems still pose severe difficulties in reactor tech­
nology.
At the same time, the solution of special problems of reactor technolgy provides one of
today's most important influxes of basic enrichment and inspiration in the general field of
structural mechanics.
The purpose of performing International Conferences on Structural Mechanics in Reactor
Technology is to bring 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 to present and discuss applied and fundamental
paper on structural mechanics problems in reactor technology.
The concept of the 3rd International Conference on STRUCTURAL MECHANICS IN
REACTOR TECHNOLOGY, London, 1-5 September, 1975, is that of a meeting prepared
for extensive discussions, facilitated by advance distribution of transactions of the papers
to by presented to the registered conference participants.
A survey of the topical grouping of the transactions volumes is given on the next pages. The
summaries of all papers to be presented at the 3rd SMIRT Conference are compiled in an
accompanying Book of Summaries.
Berlin, June 1975
Thomas A. JAEGER
Scientific Chairman and Technical Program Chairman
on the 3rd SMiRT Conference
c/o. Bundesanstalt für Materialprüfung, Berlin
III TOPICAL GROUPING OF THE CONFERENCE SESSIONS
Division A/B Plenary Session
NUCLEAR FUEL ELEMENTS
Division C Structural Analysis of Reactor Fuel Elements
C 1.l Analysis of Coated Fuel Particles and Graphite Fuel/Moderator Ele­
ments
C 2. Structural Analysis of Fuel Element Cladding I
C 3.ls of Fuel Element Cladding II
C 4. Fracture Mechanics Analysis of Fuel Element Cladding
Division D Structural Analysis of Reactor Fuel Elements
*
D 1. Structural Analysis of LWR and LMFBR Fuel Elements
D 2. Fuel Element Vibrations
REACTOR CORE AND COOLANT CIRCUIT
Division E Fast Reactor Accident Analysis
E 1. Fuel-Coolant Interaction ; Structural Response of Fuel Subassembly Ducts I
E 2. Structural Response of Fuel Subassembly Ducts II
E 3. Primary Containment Analysis
E 4. Miscellaneous Structural Dynamics Topics
Division F Structural Analysis of Reactor Core and Coolant Circuit Structures
F 1. Dynamic Analysis of Reactor Core Structures
F 2. Solid-Fluid Interaction Phenomena
F 3. Structural Analysis of Pipework Systems
F 4. Dynamics ofks I
F 5.c Analysis of Pipework Systems II
F 6. Structurals of Diverse Coolant Circuit Components
F 7.l Analysis of Heat Exchangers
F 8. Miscellaneous Topics
REACTOR VESSELS
Division G Structural Analysis of Steel Reactor Pressure Vessels
G 1. Stress and Strain Analysis of Reactor Pressure Vessels
G 2. Analysis of Pressure Vessel Heads
G 3. Assessment of the Integrity and Reliability of Reactor Pressure Vessels
G 4. Fracture Mechanics Analysis I
G 5.ess II
V Division H Structural Analysis of Prestressed Concrete Reactor Pressure Vessels
H 1. Concrete Properties Relevant to PCRV
H 2. Structural Analysis I
H 3.ls II
H 4. Failure Mode Analysis
REACTOR PLANT STRUCTURES AND CONTAINMENT
Division J Loading Conditions and Structural Analysis of Reactor Containment
J 1. Reactor Plant Safety and Reliability Analysis
J 2. Loading Conditions and Structural Design of Containment Structures
J 3. Structural Analysis of Containment Structures
J 4. Dynamic Response of Pressure Suppression Systems
J 5. Containment Structure Pulse and Impact Loading
Division K Seismic Response Analysis of Nuclear Power Plant Systems
Kl. Seismic Motion and Design Criteria
K 2. Soil-Structure Interaction I
K 3.en II
K 4. Seismic Analysis of Nuclear Power Plant Structures I
K 5.cs ofrr Plants II
K 6. Seismic Analysis of Nuclear Power Plant Structures III
K 7.c Analysis of Nuclear Power Plant Piping and Equipment
K 8. Seismics of Reactor Core Structures
METHODS FOR STRUCTURAL ANALYSIS
Division L Heat Conduction and Thermal Stress Analysis; Inelastic Analysis of Metal
Structures
L 1. Heat Conduction Analysis
L 2. Miscellaneous Thermal Stress Problems
L 3. Inelastic Behaviour of Materials and Structures I
L 4.cr ofs ands II
L 5. Inelastic Behaviour of Materials and Structures HI
L 6.cr ofs ands IV
L 7. Fracture Mechanics: Special Topics
Division M Methods for Structural Analysis
M 1. Computation Procedures; Finite Element Program Systems
M 2. Finite Element Methods for Structural Analysis
M 3. Analysis of Shell Structures I
M 4.s of Shells II
M 5. Miscellaneous Methods for Structural Analysis
VI TABLE OF CONTENTS
L. HEAT CONDUCTION AND THERMAL STRESS ANALYSIS;
INELASTIC ANALYSIS OF METAL STRUCTURES
L1. Heat Conduction Analysis
L1/1* Conjugate Heat Transfer and Thermoelastic Analyses of Heat Generating Rods
Z.J. Holy, J.J. Thompson, School of Nuclear Engineering, The University of New South Wales, Kensington,
N.S.W., Australia
L1/2 Eigenvalue Solutions in Finite Element Thermal Transient Problems
J.R. Stoker, Mechanical Engineering Laboratory, GEC Power Engineering Limited, Whetstone, Leicester, U.K.
L1/3 The Use of Simplex Direct Search and Finite Element Methods for Determination of Heat Transfer Coeffi­
cients
J. CMadek, CKD, Praha Research Institute, Praha,
J. Jinoch, National Institute for Machine Design, Praha-Bechovice, Czechoslovakia
L1/4 Automatic Mesh Generation for Finite Element Calculations in the Case of Thermal Loads
H. Cords, R. Zimmermann, Institut für Reaktorwerkstoffe, Kernforschungsanlage Jülich GmbH, Jülich, Ger­
many
L1/5 Analytical Study of Unsteady Heat Conduction in Composite Regions
J.J. Portier, Institut de Thermodynamique, Université de Liège, Liège, Belgium
O.A. Amas, Department of Mechanical Engineering, Louisiana State University, Baton Rouge, Louisiana,
U.S.A.
L1 /6 A Collocation Method Using B-Splines for One-Dimensional Moving Boundary Problems in Heat Conduction
T.C. Chawla, G. Leaf, W. Chen, Reactor Analysis and Safety Division, Argonne National Laboratory,
Argonne, Illinois, U.S.A.
L1/7 Thermal Shock on a Finite Disc Using Finite Integral Transform
R. Forghieri, G. Papa, Centro di Calcolo, C.N.E.N., Bologna, Italy
L1/8 Heat Conduction Between Bodies With Wavy Surfaces
J. Dundurs, Department of Civil Engineering, The Technological Institute, Northwestern University, Evan-
ston, Illinois, U.S.A.
L 2. Miscellaneous Thermal Stress Problems
L 2/1 Thermal Stresses in a Spherical Shell with a Circular Elastic Inclusion
P. Prakash, K.P. Rao, Department of Aeronautical Engineering, Indian Institute of Science, Bangalore, India
L2/2 Transient Thermal Stresses in Circular Cylinder under Intermittently Sudden Heat Generation
Y. Sugano, K. Saito, Y. Takeuti, Department of Mechanical Engineering, University of Osaka Prefecture,
Mozu, Sakai, Osaka, Japan
L 2/3 Thermal Stresses and Thermal Buckling of a Rectangular Plate with a Central Circular Hole
T. Sekiya, Faculty of Engineering, University of Osaka Prefecture, Mozu, Sakai, Osaka,
N. Sumi,y of Education, Shizuoka University, Shizuoka City, Japan
L2/4 Decohesive Carrying. Capacity in Thermal Stress Problems
M. Zyczkowski, K. Szuwalski, Technical University of Cracow, Cracow, Poland
L 2/5 A Method of Solution or the Elastic-Plastic Thermal Stress Problem
P. Rafalski, Institute of Nuclear Research, Swierk near Warszawa, Poland
L2/6 Nonlinear Effects of High Temperature on Buckling of Structural Elements
N.G.R. Iyengar, Department of Aeronautical Engineering, Indian Institute of Technology, Kanpur, India
L2/7 Unsteady Thermal Stresses in a Circular Disk Due to Rotating Partial Surface Heat Source
N. Noda, Faculty of Engineering, Shizuoka University, Hamamatsu, Shizuoka
Y. Takeuti,y of, University of Osaka Prefecture, Mozu, Sakai, Osaka, Japan
L 3. Inelastic Behaviour of Materials and Structures I
L 3/1*c Response Analysis of Structures
J.H. Argyris, G. Faust, K.J. Willam, Institut für Statik und Dynamik der Luft- und .Raumfahrtkonstruktionen,
Universität Stuttgart, Stuttgart, Germany
K.S. Pister, Department of Civil Engineering, University of California, Berkeley, California, U.S.A.
notes: — The sign * designates Invited Lectures.
— A title mentioned on the Table of contents and followed by a summary only (at its right place) means that the paper was not
available at the time of publishing the book.
— A paper number not followed by a title means that the paper was cancelled or withdrawn.
VII L 3/2* Structural Analysis Technology for High-Temperature Design
W.L. Greenstreet, Oak Ridge National Laboratory, Oak Ridge, Tennessee, U.S.A.
L 3/3 A Work-Hardening Rule for Finite Elastic-Plastic Deformation of Metals at Elevated Temperature
L.H.N. Lee, J.T. Horng, Department of Aerospace and Mechanical Engineering, University of Noti
Notre Dame, Indiana, U.S.A.
L 3/4 Effects of Prior Stress History on Minimum Creep Rate and Creep Fracture
J.D. Snedden, Creep and Tribology Division, National Engineering Laboratory, East Kilbride, Glasgi
L3/5*
L 3/6 Estimation of the Controlling Stress in Creep Fracture
J. Henderson, F.R. Ferguson, Creep and Tribology Division, National Engineering Laboratory, East
Glasgow, U.K.
L 3/7 Inelastic Stress Analysis and Failure Laws
E. Krempl, Department of Mechanical Engineering, Rensselaer Polytechnic Institute, Troy, New Yori
L 3/8 High Temperature Behavior of Inelastic Metals
D.C. Stouffer, A.M. Strauss, Department of Engineering Analysis, University of Cincinnati, Cincinni
U.S.A.
L3/9 Numerical Plasticitv and Creep Analysis Based on the Fraction Model and Experimental Verifica
AISI304
P. Meijers, G.T.M. Janssen, Instituut TNO voor Werktuigbouwkundige Constructies, Delft,
J. Booü, Laboratory of Applied Mechanics, Delft University of Technology, Delft, The Netherlands
L3/10 Design Against Buckling of Nuclear Components
I. Berman, A.C. Gangadharan, G.D. Gupta, Solid Mechanics Department, Foster Wheeler Energy <
tion, John Blizard Research Center, Livingston, New Jersey, U.S.A.
L 4. Inelastic Behaviour of Materials and Structures II
L 4/1* Recent Developments on Thermo-Elasto-Visco-Plasticity and Neutron Irradiation of Metals in Nuclei
tors
T. Ariman, Department of Aerospace and Mechanical Engineering, University of Notre Dame« Notn
Indiana, U.S.A.
L 4/2 Thermoinelasticity of Irradiated Materials
P. Perzyna, Polish Academy of Sciences, Institute of Fundamental Technological Research, Warsaw.
L 4/3 An Experimental Study of Stress Redistribution in Nimonic Cylinders
K.G. Torr, Atomic Energy Board, Pelindaba, Republic of South Africa,
J.L. Head, Mechanical Engineering Department, Imperial College, London, U.K.
L 4/4 Determination of Material Properties Through Computer Simulation
D.P. Mazumdar, P.N. Murthy, Department of Aeronautical Engineering, Indian Institute of Technoloi
pur, India
L 4/5* Elastic-Plastic-Creep Response of Structures under Composite Time History of Loadings
Z. Zudans, Engineering Department, The Franklin Institute Research Laboratories, Philadelphia, ]
vania, U.S.A.
L 4/6 Analysis of Thermoinelastic Dissipative Structures
T.J. Chung, J.E. Key, Department of Mechanical Engineering, The University of Alabama in Ht
Huntsville, Alabama, U.S.A.
L4/7 Thermorheological Behaviour and Coupling Problem of Structural Materials
Z. Bychawski, Technical University of Rzeszow, Rzeszow, Poland
L4/8 Damage-Induced Tensile Instability
J. Hult, Division of Solid Mechanics, Chalmers University of Technology, Gothenburg, Sweden
L 5. Inelastic Behaviour of Materials and Structures III
L5/1* Shakedown Analysis of Elastoplastic Structures: A Review of Recent Developments
G. Maier, Istituto di Scienza e Tecnica delle Costruzioni, Politecnico di Milano, Milano, Italy
J.A. König, Institute of Fundamental Technological Research, Warsaw, Poland
L 5/2 À General Shakedown Theorem for Elastic/Plastic Bodies with Work Hardening
A.R.S. Ponter, Department of Engineering, University of Leicester, Leicester, U.K.
L 5/3 Response of Structures under Random Loading Conditions
M.M. Ghamian, Ferco Engineering, Whitby, Ontario,
S. Krishnasamy, Ontario Hydro Research Division, Toronto, Ontario,
A.N. Sherbourne, Department of Civil Engineering, University of Waterloo, Waterloo, Ontario, Ca
VIII

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