TRANSACTIONS of the 3rd International Conference on STRUCTURAL IN REACTOR TECHNOLOGY. Vol. 4 REACTOR PLANT STRUCTURES AND CONTAINMENT Part K. Seismic Responce Analysis of Nuclear Power Plant Systems

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• Publié par: EUROPEAN-COMMISSION
• Nombre de lectures: 32
• Langue: English
• Poids de l'ouvrage: 13 Mo

Extrait

TRANSACTIONS
of the
3rd International Conference
STRUCTURA
MECHANICS
IN REACTOR
TECHNOLOGI
LONDON, United Kingdom, 1-5 September 1975
Vol. 4 REACTOR PLANT STRUCTURES AND
CONTAINMENT
Part K. Seismic Responce Analysis of Nuclear
Power Plant Systems
Compiled by:
Thomas A. JAEGER, Bundesanstalt für Materialprüfung (BAM), Berlin
nternational Association for Structural Mechanics in Reactor Technolo
Commission of the European Communities, Brusse
he British Nuclear Energy Society, Londo
Palo Alto Philadelphia Cambridge Giasg 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 Schooi 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
of the
3rd International Conference on
STRUCTURAL
IN REACTOR
TECHNOLOGY
LONDON, United Kingdom, 1-5 September 1975
Vol. 4 REACTOR PLANT STRUCTURES AND
CONTAINMENT
Part K. Seismic Responce Analysis of Nuclear
Power Plant Systems
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 AIMS CEGB EPRI FIRL MIT SSEB
Berlin London London Palo Alto Philadelphia Cambridge Glasgow
Gal. 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. Structural Analysis of Coated Fuel Particles and Graphite Fuel/Moderator Ele­
ments
C 2. Structural Analysis of Fuel Element Cladding I
C 3. l s 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. Fuel­Coolant 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. Solid­Fluid Interaction Phenomena
F 3. Structural Analysis of Pipework Systems
F 4. Dynamic s of k s I
F 5. c Analysis of Pipework Systems II
F 6. Structural s 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. e s s 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
K 1. 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.cs ofr Power Plant Piping and Equipment
K 8. Seismic Analysis of Reactor Core Structures
METHODS FOR STRUCTURAL ANALYSIS
Division L Heat Conduction and Thermal Stress Analysis; Inelastic Analysis of Metal
Structures
L1. 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 III
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