Proceedings of the First International Conference on STRUCTURAL IN REACTOR TECHNOLOGY 20-24 September 1971. Vol. 3 REACTOR COMPONENTS Part F Structural Analysis of Core Support and Coolant Circuit Structures

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Proceedings
of the
First International Conference on
STRUCTURAL
IN REACTUR
TEGHNOLUGY
Berlin, Germany · 20-24 September 1971
Vol. 3 REACTOR COMPONENTS
Part F Structural Analysis of Core Support
and Coolant Circuit Structures
compiled by: Thomas A. Jaeger
Organized by:
Commission of the European Communities, Brussels
Bundesanstalt für Materialprüfung (BAM) , Berlin
in cooperation with: FIRL IKT IPPT ISD NIS NUS SDK Conference Organisation by:
Commission of the European Communities, Brussels
Bundesanstalt für Materialprüfung (BAM), Berlin, Germany
in cooperation with:
The Franklin Institute Research Laboratories (FIRL), Philadelphia, Pa.
Institut für Kerntechnik (IKT), Technische Universität Berlin
Instytut Podstawowych Problemów Techniki (IPPT),
Polska Akademia Nauk, Warsaw
Institut für Statik und Dynamik (ISD), Technische Universität Stuttgart
Nuklear-Ingenieur-Service GmbH (NIS), Hanau
Nuclear Utilities Service (NUS), Rockville, Md.
Ingenieurunternehmen für spezielle Statik, Dynamik und Konstruktion (SDK),
Lörrach
Sponsoring Societies :
American Concrete Institute (ACI)
The American Society of Mechanical Engineers (ASME),
Nuclear Engineering Division
The American Nuclear Society (ANS)
Atomic Energy Society of Japan (AESJ)
The British Nuclear Energy Society (BNES)
Kerntechnische Gesellschaft (KTG),
incorporated in the Deutsches Atomforum e.V.
Schweizerische Vereinigung für Atomenergie (SVA)
Vereinigung der Grosskesselbetreiber e.V. (VGB)
Executive Committee :
Thomas A. Jaeger, General Chairman
John H. Argyris, for ISD
Hartwig Benzler, for Commission of the European Communities
Klaus Brandes, for BAM
William J. Gallagher, for NIS
Charles F. Jones, for NUS
Hans H. Hofmann, for SDK
Antoni Sawczuk, for IPPT
Zenons Zudans, for FIRL
Representatives of Sponsoring Societies :
Yoshio Ando, for AESJ
Ian Davidson, for BNES
Claus-Benedict von der Decken, for KTG
Nathan M. Newmark, for ACI
Karl Wirtz, for ANS
Otto Schaub. for SVA
K. E. Schroeter, for ANS Local Section in Central Europe
Ottmar Schwarz, for VGB
J. E. Zerbe, for ASME Nuclear Engineering Division
Patronage : Der Bundesminister für Wirtschaft und Finanzen
General Support : Senate of the City of Berlin (West)
Editor : Commission of the European Communities
DG XIII
Center for Information and Documentation - CID
Luxembourg Proceedings
of the
First International Conference on
STRUCTURAL
IN REAGTUR
TEGHNULUGY
Berlin, Germany · 20-24 September 1971
Vol. 3 REACTOR COMPONENTS
Part F Structural Analysis of Core Support
and Coolant Circuit Structures
EUR 4820 d-f-e
compiled by: Thomas A. Jaeger
Organized by:
Commission of the European Communities, Brussels
Bundesanstalt für Materialprüfung (BAM) , Berlin
in cooperation with: FIRL IKT IPPT ISD NIS NUS SDK PREFACE
The purpose of the First International Conference on STRUCTURAL
MECHANICS IN REACTOR TECHNOLOGY was to bring together
engineers and scientists who are actively engaged in solving structural
mechanics problems in the field of reactor technology and fundamentalists
in the general field of engineering mechanics to present and discuss
applied and fundamental papers on structural mechanics problems
in reactor technology.
The meeting of more than 800 reactor technologists and engineering
mechanicians from 33 countries all over the world has brought together
a wealth of information and inspiration for the benefit of both reactor
technology and structural mechanics science.
All contributed original papers together with the discussions, as well
as the summaries of the invited lectures (designated by *), are contained
in the present Proceedings published by the Commission of the European
Communities. A survey of the topical grouping of the Proceedings
is given on the next pages. The detailed overall list of contents of the
Proceedings is given in Volume 1.
The 70 invited lectures have been published in special conference
issues of the journal NUCLEAR ENGINEERING AND DESIGN, North-
Holland Publishing Co., Amsterdam. The arrangement of contents
of these issues (Vol. 18, No. 1, 2, 3; Vol. 19, No. 1, 2; Vol. 20, No. 1, 2;
(1972)) is given in Volume 1 of the present Proceedings.
Thomas A. JAEGER,
General Chairman of the Conference
Berlin, March 1972 CONTENTS
Pgeas
Session F 1 Structural Analysis of Reactor Core Support
Structures
Chairmen :
E. KOCH,
Fachgebiet Leistungsreaktoren, Allgemeine Elektricitätsgesellschaft,
AEG- Telefunken, Frankfurt am Main, Germany
G.R. WAYMIRE,
Fast Flux Test Facility, WADCO Corporation, Hanford Engineering
Development Laboratory, Richland, Washington, U.S.A.
F 1/1 * Analytical Problems Associated with Core Support
Structures of PWR 1
G.J. BÖHM,
Westinghouse Electric Corporation, Power Systems, Pittsburgh,
Pennsylvania, U.S.A.
Discussion 2
F 1/2 Paper deleted
F 1/3 Reactor Internals Response under a Blowdown Accident 5
G.J. BÖHM,
Westinghouse Electric Corporation, Power Systems, Pittsburgh,
Pennsylvania, U.S.A.
J.P. LAFAILLE,
Ateliers de Constructions Electriques de Charleroi, Charleroi,
Belgium
Discussion 26
F 1/4 Prediction of Stresses and Fatigue Strength of a Bolted
Core Support Structure9
M.J. MANJOINE,
Westinghouse Electric Corporation, Research and Development
Center, Pittsburgh, Pennsylvania
H.W. KELLER,
Westinghouse Electric Corporation, Power Systems, Pittsburgh,
Pennsylvania, U.S.A.
Discussion 47
F 1/5 Core Support Structures for Gas-Cooled Reactors 49
W.O. LIVSEY,
G.E.C. Reactor Equipment Ltd., Whetstone, Leicestershire,
United Kingdom
Discussion 62
F 1/6 Design Analysis for LMFBR Core Restraint 63
J.F. PATTERSON, H.W. YANT,
Westinghouse Electric Corporation, Atomic Power Divisions,
Madison, Pennsylvania, U.S.A.
Discussion 75 VI
Pages
F 1/7 Optimization Study for an Internal Supporting Flange
in a Nuclear Reactor Vessel 79
S. CURIONI, P. NERI,
Comitato Nazionale per l'Energia Nucleare, Programma Reattori
Veloci, Bologna, Italy
Discussion 105
Session F 2 Structural Analysis of Miscellaneous Reactor Com­
ponents
Chairmen :
G.J. BÖHM,
Westinghouse Electric Corporation, Power Systems, Pittsburgh,
Pennsylvania, U.S.A.
C.H.A. TOWN LEY,
Central Electricity Generating Board, Research and Development
Department, Berkeley Nuclear Laboratories, Berkeley, Gloucester­
shire, United Kingdom
F 2/1 Internal Supporting Structures of Pressure Tubes Type
Reactor Core: Analytical Model for Static Analysis 107
S. CARUSO, L. GASPARINI, A. PALMERO,
Progettazioni Meccaniche-Nucleari S.p.A., Genova, Italy
F 2/2 Paper withdrawn
F 2/3 Dynamic Analysis of a Novel Reactor Head Plate Design 129
D. KRAJCINOVIC,
Engineering and Technology Division, Argonne National Labo­
ratory, Argonne, Illinois, U.S.A.
Discussion 142
F 2/4 On the Lateral Deformation of Coupled Tubular Struc­
tures5
L.L. BARINKA,
Babcock & Wilcox Co., Power Generation Division, Lynchburg,
Virginia, U.S.A.
Discussion 167
F 2/5 Probleme bei der Auslegung von Loop-Druckrohren für
den schnellen Hochflußtestreaktor FR 3 169
A. FIEGE, H. PETERSEN,
Institut für Material- und Festkörperforschung, Kernforschungs­
zentrum Karsruhe, Karlsruhe, Germany
Discussion 186
F 2/6 Elastic Stability of Hexagonal Shells 189
D. KRAJCINOVIC,
Engineering and Technology Division, Argonne National Labo­
ratory, Argonne, Illinois, U.S.A. vu
Pages
F 2/7 Elastic Instability of Edge-Reinforced Annular Plates 205
O.E. WIDERA,
Department of Materials Engineering, University of Illinois,
Chicago, Illinois
R. AMON,
Department of Architecture, University of Illinois, Chicago,
Illinois, U.S.A.
Discussion 216
F 2/8 Photothermoelastic and Theoretical Analysis of Stresses
in a Circular Disc Having a Pair of Holes 217
A. ATSUMI, T. HATA, M. KURASCHIGE, S. ITO,
Department of Mechanical Engineering, Faculty of Engineering,
Tohoku University, Sendai, Japan
Session F 3 Structural Analysis of Coolant Circuit Compo­
nents - I
Chairmen :
T. ARIMAN,
Department of Aerospace and Mechanical Engineering, University
of Notre Dame, Notre Dame, Indiana, U.S.A.
D.G.H. LATZKO,
Laboratory for Nuclear Engineering, Department of Mechanical
Engineering, Delft University of Technology, Delft, The Nether­
lands
F 3/1 * Instationäre wärmetechnische Rechnungen als Grundlage
für die Spannungsanalyse von Dampferzeugern und
Wärmetauschern 235
K. FRITZ, F. JAHN, H. LENDL,
Waagner-Biró AG, Wien, Austria
F 3/2 STRAP -¿A Computer Code for the Static and Dynamic
Analysis of Reactor Structures7
J.A. DEARIEN,
Nuclear Safety Development Branch, Aerojet Nuclear Company,
Idaho Falls, Idaho, U.S.A.
Discussion 2