TRANSACTIONS of the 5th International Conference on STRUCTURAL MECHANICS IN REACTOR TECHNOLOGY 13-17 August 1979. Vol. F. Structural Analysis of Reactor Core and Coolant Circuit Structures

TRANSACTIONS
of the
5th International Conference on
STRUCTURAL
MECHANICS
IN REACTUR
TECHNULUGY
International Congress Center Berlin
Berlin, Germany" 13­17 August 1979
Transaction General Editors:
Thomas A. JAEGER ■ Bruno A. BOLEY
Vol. F. Structural Analysis of Reactor Core
and Coolant Circuit Structures
Division Coordinators:
R. L CLOUD, R.L Cloud & Assoc, Palo Alto, Ca., U.SA.
D. G. H. LATZ KO, Delft University of Technology, Delft, The Netherlands
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.
Electricr Research Institute (EPRI). Palo Alto...
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) n Society of Civil Engineers (ASCE)
Americany of Mechanical Engineers (ASME)
Argonne National Laboratory, Argonne, Illinois, U.S.A.
Brookhavenl. 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
MECHANICS
IN REACTOR
TECHNULUGY
Vol. F. Structural Analysis of Reactor Core
and Coolant Circuit Structures
Division Coordinators:
R. L. CLOUD, R.L. Cloud & Assoc, Palo Alto, Ca., U.SA
D. G. H. LATZKO, Delft University of Technology, Delft, The Netherlands 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' (DG. 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' (D.G. 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 SA
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
IN REACTUR
TECHNOLUGY
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 Scientific Chairmen: Organization Chairman:
Thomas A. JAEGER Bundesanstalt für Material­ Thomas A. JAEGER
prüfung, Berlin, Germany Bruno A. BOLEY
Dep. Gen. Chairman: Bruno A. BOLEY Northwestern University,
Evanston, Illinois, U.SA
NORTH­HOLLAND PUBLISHING COMPANY
for
THE COMMISSION OF THE EUROPEAN COMMUNITIES Published by
NORTH-HOLLAND PUBLISHING COMPANY — AMSTERDAM D 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: 0444 85362 6 d ISBN for the set: 0444 85356 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.
IV SMiRT-5 SCIENTIFIC PROGRAM
TOPICAL GROUPING OF THE
CONFERENCE SESSIONS
Division Β. Thermal and Fluid/Structure Dynamics Analysis
Computational Methods I Β1.
Β 2. l Methods II ls III Β 3.
Β 4. Acoustic Methods
Flow Induced Vibrations Β 5.
PWR Problems Β 6.
BWRs I Β 7.
BWRs II Β 8.
Division C. Analysis of Reactor Fuel and Cladding Materials
C1|. Fuel and Fission Product Behavior I
Fuel andntr II C 1||
C 2. Graphite Fuels Analysis
C3|. Cladding Materials Behavior I
C 3||. Claddingsr II
C 4|. Failure Criteria I
C 4||.ea II
Division D. Structural Analysis of
Reactor Fuel Elements and Assemblies
D 1. Fuel Performance Analysis
D 2. Pellet-Clad Interaction Effects on Clad Behavior
D 3. Methods for Analysis for Pellet-Clad Interaction
D 4. Thermal Reactor Subassembly Analysis
D 5. Fast Reactory Analysis
D 6. Accident and Overpower Transient Analysis of
Thermal Reactors
D 7.t andrt Analysis of Fast
Reactors
Division E. Energetics and Structural Dynamics in Fast
Reactor Accident Analysis
E1. HCDA Containment
E 2. Upper Core Structures and Coper Response
E 3. Coolant Systems and Materialse
E 4. Experiments and Code Verification I
E 5.s anden II
E 6. Core Components Response
V Division F. Structural Analysis of Reactor Core and Coolant
Circuit Structures
F1. Reactor Core Structures
F 2. Special Problems
F 3. Piping: Structural Analysis
F 4.: Dynamics
F 5. Fracture Mechanics
F 6. Pipe Rupture
F 7.e Rupture: Methodology
F 8. Components and Support Systems
F 9. Heat Exchangers
Division G. Structural Analysis of Steel Reactor Pressure
Vessels
G 1 Overviews of Integrity Assessment
G 2. Fracture Toughness Measurements
G 3.e Mechanics: Elasto-Plastic
G 4.e: Special Aspects
G 5. Fracture: Stable Crack Growth
G 6.e Mechanics: Materials Modeling
G 7.e: Computation
G 8. Fatigue
G 9. Fracture Mechanics: Thermal Effects
G 10. Stress Analysis
Division H. Structural Engineering of Prestressed
Reactor Pressure Vessels
H1. Materials Behavior I
H 2.sr II
H 3. Design, Research and Surveillance of PCVs
H 4. Structural Analysis of PCVs and Components
H 5. Liner and Thermal Barrier Systems
H 6. Concept and Research for a PCV
with Hot Liner
H 7.t and Research for a PCIV
H 8. Concept andh for a PCV for the LMFBR
VI Division J. Loading Conditions and
Structural Analysis of Reactor Containment
J 1. General Design Criteria andt
Selection
J 2. BWR