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TRANSACTIONS of the 4th International Conference on STRUCTURAL MECHANICS IN REACTOR TECHNOLOGY. Vol. G. Structural Analysis of Steel Reactor Pressure Vessels 15-19 August 1977

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644 pages
TRANSACTIONS of the 4th International Conference onl STRUCTURAL MECHANICS IN REACTUR TECHNULUGY San Francisco, California, USA "15­19 August 1977 Transaction General Editors: Thomas A. JAEGER ■ Bruno A. BOLEY Vol. G. Structural Analysis of Steel Reactor Pressure Vessels Division G Coordinators: R. W. NICHOLS, UKAEA Engineering and Materials Laboratory, Risley, U.K. L. E. STEELE, Naval Research Laboratory, Washington, D.C., U.S.A. Conference organization by: International Association for Structural Mechanics in Reactor Technology and Commission of the European Communities, Brussels ¡ncooperation with: Bundesanstalt für Materialprüfung (BAM), Berlin Bechtel Power Corp., San Francisco ■ Northwestern University, Evanston General Chairman: Bruno Æ BOLEY Organization Chairman: Scientific Chairmen: Thomas A. JAEGER Harvey F. BRUSH Northwestern University, Bundesanstalt für Material­Evanston, Illinois, USA Bechtel Power Corp., prüfung, Berlin, Germany San Francisco, Calif., USA Dep. Gen. Chairman: Thomas A. JAEGER Bruno A. BOLEY Conference Organisation by: International Association for Structural Mechanics in Reactor Technology e.V. and Commission of the European Communities, Brussels in cooperation with: Bechtel Power Corp., San Francisco/Los Angeles, Cal., U.SA. Bundesanstalt für Materialprüfung (BAM), Berlin, Germany EDS Nuclear Inc., San Francisco, Cal., U.S.A. Electric Power Research Institute (EPRI), Palo Alto, Cal., U.S.A. Franklin Inst.
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TRANSACTIONS
of the
4th International Conference onl
STRUCTURAL
MECHANICS
IN REACTUR
TECHNULUGY
San Francisco, California, USA "15­19 August 1977
Transaction General Editors:
Thomas A. JAEGER ■ Bruno A. BOLEY
Vol. G. Structural Analysis of
Steel Reactor Pressure Vessels
Division G Coordinators:
R. W. NICHOLS, UKAEA Engineering and Materials Laboratory, Risley, U.K.
L. E. STEELE, Naval Research Laboratory, Washington, D.C., U.S.A.
Conference organization by:
International Association for Structural Mechanics in Reactor Technology
and
Commission of the European Communities, Brussels
¡ncooperation with: Bundesanstalt für Materialprüfung (BAM), Berlin
Bechtel Power Corp., San Francisco ■ Northwestern University, Evanston
General Chairman: Bruno Æ BOLEY Organization Chairman: Scientific Chairmen: Thomas A. JAEGER
Harvey F. BRUSH Northwestern University, Bundesanstalt für Material­
Evanston, Illinois, USA Bechtel Power Corp., prüfung, Berlin, Germany
San Francisco, Calif., USA
Dep. Gen. Chairman: Thomas A. JAEGER Bruno A. BOLEY Conference Organisation by:
International Association for Structural Mechanics in Reactor Technology e.V.
and
Commission of the European Communities, Brussels
in cooperation with:
Bechtel Power Corp., San Francisco/Los Angeles, Cal., U.SA.
Bundesanstalt für Materialprüfung (BAM), Berlin, Germany
EDS Nuclear Inc., San Francisco, Cal., U.S.A.
Electric Power Research Institute (EPRI), Palo Alto, Cal., U.S.A.
Franklin Inst.h Laboratories (FIRL), Philadelphia, Pa., U.S.A.
Massachusetts Inst, of Technology (MIT), Cambridge, Mass., U.SA.
Northwestern University, Evanston, Illinois, U.SA.
Nuclear Utilities Services (NUS) Corp., Rockville, Md., U.SA.
Co-Sponsoring Institutions and Societies
Argonne National Laboratory, Argonne, III., U.SA
American Nuclear Society (ANS)
American Society of Civil Engineers (ASCE) ny of Mechanical Engineers (ASME)
British Nuclear Energy Society (BNES)
Canadianr Association
European Nuclear Society (ENS)
Atomic Energy of Japan
Society of Engineering Science
Office of Naval Research (ONR)
Executive Committee
Bruno A. BOLEY, General Chairman and Scientific Chairman
Dean, The Technological Institute, Northwestern University, Evanston, Illinois 60201, U.SA
Harvey F. BRUSH, Organization Chairman
Senior Vice President, Bechtel Power Corporation, San Francisco, California 94105, U.S.A.
Thomas A. JAEGER, Scientific Chairman and Deputy General Chairman
Direktor und Professor, Bundesanstalt für Materialprüfung, Berlin (West) 45, Germany
Raymond K. APPLEYARD, C.E.C. Representative
Director General, Directorate-General 'Scientific and Technical Information and Information Management' (D.G.
XIII)
Commission of the European Communities, Brussels, Belgium
F. CACCIA-DOMINIONI, C.E.C. Representative
Director, Nuclear and Energy Directorate
Directorate-General 'Industrial and Technological Affairs' {D.G. Ill)
Commission of the European Communities, Brussels, Belgium
Local Organization Committee
Harvey F. BRUSH, Chairman
Philip D. BUSH
Vice President, Kaiser Engineers, Oakland, Cal.
Karl S. PISTER
Professor of Engineering Science, University of California, Berkeley, Cal.
Yusef R. RASHID
Manager, Applied Mechanics, Nuclear Fuel Department, General Electric Co., San José, Cal.
Chauncey STARR,
President, Electric Power Research Institute, Palo Alto, Cal.
Publication Management
Mme J. STALPAERT,
Commission of the European Communities, Directorate-General for Scientific and Technical Information and
Information Management (D.G. XIII) - Dissemination of the Product of Research, Luxembourg TRANSACTIONS
of the
4th International Conference on
STRUCTURAL
IN REACTOR
TECHNOLOGY
San Francisco, California, USA ■ 15 - 19 August 1977
Transaction General Editors:
Thomas A. JAEGER ■ Bruno A. BOLEY
Vol. G. Structural Analysis of
Steel Reactor Pressure Vessels
Division G Coordinators:
R. W. NICHOLS, UKAEA Engineering and Materials Laboratory, Risley, U.K.
L. E. STEELE, Naval Research Laboratory, Washington, D.C., U.SA
Conference organization by:
International Association for Structural Mechanics in Reactor Technology
and
Commission of the European Communities, Brussels
in cooperation with: Bundesanstalt für Materialprüfung (BAM), Berlin
Bechtel Power Corp., San Francisco ■ IMorthwestern University, Evanston
General Chairman: Bruno A. BOLEY Organization Chairman: Scientific Chairmen: Thomas A. JAEGER
NorthwesternUniversity, Harvey F. BRUSH Bundesanstalt für Material-
Evanston, Illinois,USA BechtelPowerCorp.,prüfung, Berlin, Germany
Dep. Gen. Chairman: Thomas A. JAEGER SanFrancisco-Calif.,USABmno A β01_Εγ 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, 1977
All rights reserved. No part of this Dublication 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. TOPICAL GROUPING OF THE CONFERENCE SESSIONS
Division B. Thermal and Fluid/Structure Dynamics Analysis
Β 1. Computational Methods I
Β 2.ls II
Β 3. Free and Forced Vibrations
Β 4. Blowdown Suppression I
Β 5.nn II
Division C. Structural Analysis of Reactor Fuel and Cladding
C 1. Modeling and Analyses I
C 2.g ands II
C 3. Material Properties and Failure Criteria
C 4. LMFBR-Fuel Rod Modeling and Analyses
Division D. Structural Analysis of Reactor Fuel Elements
D 1. Fuel Rods
D 2. Subassembly Analysis
D 3. Local Effects (incl. Vibrations)
D 4. Accident and Seismic Response Analysis
D 5. Graphite Fuel Element Analysis
Division E. Structural Dynamics in Fast Reactor Accident Analysis
E 1. Analyses and Codes for LMFBR Containment
E 2. LMFBR Components Response to HCDA
E 3. Subassembly Response to Abnormal Conditions
E 4. Treatment of Dynamic Effects in LMFBR
E 5. Large Sodium-Water Reactions and their Consequences
E 6. LMFBR Containment Materials Problems
Division F. Structural Analysis of Reactor Core and Coolant Circuit Structures
F 1. Piping and Components I
F 2.g ands II
F 3. Piping Dynamic Behavior I
F 4.gcr II
F 5. Reactor Intervals General/Reactor Internal Vibrations
F 6. Flow Induced Vibration
F 7. Fracture Mechanics - Pipes and Tubes I
F 8.es -s ands II
F 9. Heat Exchangers
Division G. Structural Analysis of Steel Reactor Pressure Vessels
G 1. Fracture Mechanics - General
G 2.es - Elasto-Plastic and Plastic
G 3. Fracture Mechanics - More Detailed Aspects of Elastic-Plastic Analysis
G 4.es - Computational Methods G 5. Fracture Mechanics - Some Detailed Analytical Aspects
G 6. Probabilistic Fracture Mechanics
G 7. Stress Analysis - General
G 8.s Analysis - Specific Geometries
G 9. Stresss - Thermal Shock and Fault Conditions/Thermal Effects
Division H. Structural Engineering of Prestressed Reactor Pressure Vessels
H 1. General Design of Prestressed Concrete Pressure Vessels/Prestressed Cast
Iron Pressure Vessels
H 2. Structural Analysis of Prestressed Concrete Reactor Vessels I
H 3.ls ofders II
H 4. Comparisons of Theory with Experimental Data
H 5. Materials Properties Characterization
H 6. Design of Penetrations, Closures and Liners for Prestressed Concrete Reac­
tor Vessels
Division J. Loading Conditions and Structural Analysis of Reactor Containment
J 1. Containment Concepts and Probabilistic Safety Assessment
J 2. Underground and Floating Nuclear Power Plants
J 3. Design and Analysis of Concrete Containments and Internal Structures
J 4. Effects of Temperature and Cracking on Concrete Structural Ele­
ments/Structural and Leak Rate Testing
J 5. Design and Analysis of Containment Openings and Penetrations/Design
and Analysis of Metal Containments and Liner Plates
J 6. BWR Containment Analysis for LOCA and SRV Leads/Design and An­
alysis of Spent Fuel Pools and Containments
J 7. Missile Impact and Transient Loads
J 8. Design and Analysis for Aircraft Impact
J 9. Equipment Response tot Impact/Special Cases of Impact Loading
J 10. Design and Analysis for Tornado Missile Impact/Design and Analysis for
Blast Loading
Division K. Seismic Response Analysis of Nuclear Power Plant Systems
K 11. Ground Motion and Design Criteria I
K 1 n.dn andna II
K 21. Soil Structure Interaction I
K 2 n. Soilen II
K 31. Dynamic Modeling of Structures, Systems and Components I
K 3 n.cg of,s ands II
K 41. Seismic Response of Structures I
K 4 n.ce ofs II
K 5. Seismic Response of Fluid Containers
K 61ce of Piping and Equipment I
K 6 n. Seismic Response ofg andt II
K 7.ce of Reactor Core Structures
K 81. Dynamic Tests and Qualifications of Structures, Systems and Components
I
K 8 n. Dynamic Tests ands of, Systems ands
II
K 9. Design Considerations of Structures, Systems and Components
IV Division L. Inelastic Analysis of Metal Structures
L 1. Advanced Theories
L2. Methods I
L3.s II
L4. Evaluation of Methods
L5. Applications I
L6.s II
L7. Inelastic Analysis and Codes and Standards
L8. Experiment and Theory
L9. Materials Behavior Characterization
Division M. Methods for Structural Analysis
M 1. Integrated Methods of Structural Analysis
M 2. Finite Element Methods for Structural Analysis
M 3. Numerical Methods for Structural Analysis
M 4. Computational Techniques within Finite Element Analyses I
M 5.lsnets II
M 6. Numerical Implementation of Inelastic Constitutive Models and Applica­
tions
M 7. Large Strain Finite Element and Finite Difference Analyses
M 8. Linear Boundary Value Problems
M 9. Probabilistic Approaches to Structural Evaluation TABLE OF CONTENTS
Division G. STRUCTURAL ANALYSIS OF STEEL
REACTOR PRESSURE VESSELS
Session G 1. Fracture Mechanics — General
G 1/1* Heavy-Section Steel Technology Program Intermediate-Scale
Pressure Vessel Test
R. H. Bryan, J. G. Merkle, G. C. Smith, G. D. Whitman, Oak Ridge
National Laboratory, Oak Ridge, Tennessee, U.S.A.
G 1/2* Research on Structural Integrity of Pressure Boundary in LWR
Y. Ando, University of Tokyo, Tokyo, Japan
G 1/3 Enhancement of the Quality of the Reactor Pressure Vessel Used
in Light Water Power Plants by Advanced Material, Fabrication and
Testing Technologies
K. Kussmaul, J. Ewald, et al., Staatliche Materialprüfungsanstalt,
Universität Stuttgart, Stuttgart, Germany
G 1/4 Pressure Vessel Fracture Safety Investigations Using as Criterion
the Onset of Crack Propagation
S. Sahgal, NOK Nuclear Power Plants Beznau, Döttingen,
T. Varga, M. Junker, M. Shakeshaft, Sulzer Bros., Ltd., Winterthur,
Switzerland
G 1/5 Interim Report on the EPRI Surveillance Progam
T. U. Marston, K. E. Stahlkopf, Electric Power Research Institute,
Palo Alto, California,
R. A. Wullaert, Fracture Control Corporation, Palo Alto, California,
U.S.A.
G1/6 A Fracture Mechanics Practice for Crack Arrest
G. T. Hahn, R. G. Hoagland, A. R. Rosenfield, Battelle, Columbus
Laboratories, Columbus, Ohio, U.S.A.
G 1/7 Material Properties and Design Procedures for Arrest of Unstable
Crack Propagation in Nuclear Reactor Pressure Vessels
G. T. Hahn, P. C. Gehlen, R. G. Hoagland, M. F. Kanninen, A. R.
Rosenfield, Battelle, Columbus Laboratories, Columbus, Ohio,
U.S.A.
G 1/8 Crack Initiation and Growth in Welds at 1100°F (593°C)
M. J. Manjoine, Westinghouse Research and Development Center,
Pittsburgh, Pennsylvania, U.S.A.
G 1/9* Nuclear Pressure Boundary Materials Research, Problems and
Proposed Solutions
K. E. Stahlkopf, Electric Power Research Institute, Palo Alto, Cali­
fornia, U.S.A.
Session G 2. Fracture Mechanics — Elasto-Plastic and Plastic
G 2/1 * A U.K. Proposal for the Assessment of the Significance of Flaws in
Pressurized Components
B. J. L. Darlaston, R. P. Harrison, K. Loosemore, I. Milne, C.E.G.B.,
Berkeley Nuclear Laboratories, Berkeley, Gloucestershire, U.K.
Notes: —The sign ' designates Invited Lectures.
— A title mentioned on the Table of contents and followed by a summary (at its right place) only
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. G 2/2 Methodology for Plastic Fracture ­ A Progress Report
J. P. D. Wilkinson, Corporate Research and Development, General
Electric Co., Schenectady, New York,
G. T. Hahn, Battelle Columbus Laboratories, Columbus, Ohio,
R. E. Smith, Electric Power Research Institute, Palo Alto, California,
U.S.A.
G 2/3 Effects of Specimen and Vessels Size on Toughness Measure­
ments and Crack Propagation in Ductile Structures
J. Lebey, R. Roche, D. Brouard, CEA­CEN/Saclay, DEMT, Gif­sur­
Yvette, France
G 2/4 Finite Element Elastic­Plastic Analysis of Initiation and Stable
Crack Growth in Three­Point Bending
Y. d'Escatha, Ecole Polytechnique, Palaiseau,
J. C. Devaux, Framatome, Courbevoie, France
G 2/5 Stable Crack Growth Under Sustained Load
H. D. Schulze, Rheinisch­Westfälischer Technischer Überwa­
chungs­Verein e. V., Essen, Germany
G 2/6 On the Assessment of Cracks for Elasto­Plastic Material Behaviour
J. G. Blauel.T. Hollstein, Fraunhofer Gesellschaft, Institut für Fest­
körpermechanik, Freiburg, Germany
Session G 3. Fracture Mechanics ­More Detailed Aspects
of Elastic­Plastic Analysis
G 3/1* Comments on Fracture Toughness of Structural Steels
G. H. Irwin, University of Maryland, College Park, Maryland, U.S.A.
G 3/2 Some Comments about the J­|­lntegral Criterion in Post Yield
Fracture Mechanics
R. L. Roche, CEA­CEN/Saclay, DEMT, Gif­sur­Yvette, France
G 3/3 The Use of a Path Independent Integral in Non­Linear Fracture Me­
chanics
T. K. Hellen, C. E. G. Β., Berkeley Nuclear Laboratories, Berkeley,
Gloucestershire, U.K.,
W. S. Blackburn, C. A. Parsons Ltd., Newcastle­upon­Tyne, U.K.
G 3/4 Application of J­lntegral Concept to Cracks Emanating from a Hole
M. G. v. d. Ruijtenbeek, M. J. G. Broekhoven, Delft University of
Technology, Delft, The Netherlands
G 3/5
G 3/6 A Critical Evaluation of the Tangent Modulus Method of Elasto­
Plastic Fracture Analysis
A. B. Holt, Torjusbakken 20, Oslo 3, Norway
G 3/7 Plastic Energy Dissipation and Criteria for Stable and Unstable
Fracture
S. K. Bhandari, G. Α. Α. Α., Le Plessis­Robinson,
C. Decolon, Conservatoire National des Arts et Metiers, Paris,
France
withdrawn
VIII