Automotive Industry Response to its Global QMS Standard ISO/TS
Division€5:€Modeling,€Testing€and€Response€Analysis€of ...€¢ TS€5...
Transcript of Division€5:€Modeling,€Testing€and€Response€Analysis€of ...€¢ TS€5...
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components1(21)
1 Presentation (speaker) not confirmed before printing of the programme
Division 5: Modeling, Testing and Response Analysis of Structures,Systems and ComponentsDivision Coordinators:
P.C.Basu, Andrei Blahoianu, Susumu Nakamura, Jari Puttonen
Technical Sessions (tentative)• TS 51a, b, c, d, e, f: Methodology, Modeling & Design
• TS 52a, b, c (d): Experiments & Tests• TS 53a, b: Dynamic Response Impact
• TS 54: Dynamic Response Impulse• TS 55a, b, c, d (e): Seismic Response & Design Analysis & Design
• TS 56a, b Seismic Response & Design Component & System• TS 57a, b (c): Seismic Response & Design Seismic Structural Integrity (SSI)
• TS 58a, b: Miscellaneous
Technical Session 51a Methodology, Modeling & Design
TS 51.1 (1577) Yerishca Mudaly1 & M.M. Cepkauskas2
1 Eskom PBMR Client Office, Cape Town, South Africa
PBMR Loop Acoustics
TS 51.2 (1632) Attinger Richard, Kluegel JensUwe
NPP GoesgenDaeniken, Switzerland, Switzerland
A Model for the Hysteresis of Concrete to Describe the Cyclic Fatigue of ReinforcedConcrete Structures During an Earthquake
TS 51.3 (1641) Jukka Kähkönen
Fortum Nuclear Services Ltd, Finland
Steam Generator Tube Plugging FEM Analysis
TS 51.4 (1692) Akop Sargsian, Andrey Grishin& Elena Gukova
Atomenergoproject, Russia
Generation of Dynamic Mechanical Model of Inertial Soil Foundation in Considerationof NPP Structures Basement Finite Stiffness
TS 51.5 (1784) Sohrab Esfandiari 1, Christopher Wandell 2
1 ENOVA Engineering Services, Walnut Creek, California, USA,2 Arizona Public Service Company, Tonopah, Arizona, United States
Comparison of Approximate Methods for Sliding and Rocking Evaluation ofUnanchored Platforms
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components2(21)
1 Presentation (speaker) not confirmed before printing of the programme
Technical Session 51b Methodology, Modeling & Design
TS 51.6 (1811) William Johnson, Necip Akinci
Bechtel Power Corporation, Frederick, MD, USA, United States
OffAxis Underground Soil Pressures from Surface Impact Loads
TS 51.7 (1833) Alexey Berkovsky, Peter Vasilyev, Oleg Kireev
CKTIVIBROSEISM, Russia
Modeling of high viscous dampers in piping dynamic analysis. Different approachesand acceptable limits for simplifications.
TS 51.8 (1940) Gordon Bjorkman, Doug Ammerman
US Nuclear Regulatory Commission, Sandia National Laboratory, United States
StrainBased Acceptance Criteria for Section III of the ASME Boiler and Pressure VesselCode
TS 51.9 (1942) Lei Jiang1, Ken MacKay1, and Robert Gibb2
1Martec Limited, Halifax, Canada; 2CNSC, Ottawa, Canada , Canada
Numerical Model of the Thermal and Mechanical Behavior of a CANDU 37ElementBundle
TS 51.10 (2006) Sajish.S.D, R.Srinivasan, P.Chellapandi and S.C Chetal
Indira Gandhi Center for Atomic ResearchKalpakkam, India, India
STRUCTURAL INTEGRITY ASSESSMENT OF DHX UNDER CDA PRESSURE LOADING
Technical Session 51c Methodology, Modeling & Design
TS 51.11 (2009) Christophe VASSE
EDF Recherche et Développement, France
Developing a numerical model to describe the mechanical behaviour of dieformedexpanded graphite for valve stems sealing
TS 51.12 (1780) Sudhir J. Shah, Berenger d"Uston and Gary T. Williams
AREVA NP Inc., Fuel America, United States
Fuel Assembly TwoBeam Dynamic Model Response to Faulted Condition Loads
TS 51.13 (1911) John D. Stevenson
J.D. Stevenson, Consulting Engineer, United States
APPLICATION AND EVALUATION OF “DESIGN BY RULE” PROCEDURES APPLICABLE TONUCLEAR POWER PLANT ASME B&PVC SECTION III CLASS 2 AND 3 PIPING
TS 51.14 (2043) Billon François, Goussard Pascale, Batmale Guillaume
COMEX NUCLEAIRE, France
Advanced Analysis of Gasketed Pressure Vessel Closure Systems
TS 51.15 (1843) Yoshio Ikeda, Yukio Shimomura, Masashi Kawamura, Noriaki Sako
Taisei Corporation, Nihon University Junior College, Nihon University, Nihon UniversityJunior College, Japan
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components3(21)
1 Presentation (speaker) not confirmed before printing of the programme
Analytical Investigation for Attenuation Material with Vibration ReductionPerformance
Technical Session 51d Methodology, Modeling & Design
TS 51.16 (2474) Dr. Taha ALShawaf and Ms. Lingyah Yen
AREVA NP Inc, United States
REACTOR HEAD STAND EVALUATION USING SIMPLIFIED NONLINEAR ANALYSIS
TS 51.17 (2508) Lushuai WANG, Suyuan YU, Shutang ZHU, Xuanyu SHENG
Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084,China, China
The Gearbox for the Helium Cycle of 10MW High Temperature Gascooled Reactor
TS 51.18 (2514) Glauco J. T. Mello Junior, Tarcísio de F. Cardoso & Carlos L. M. Prates
GAN.T, Eletronuclear, Rua da Candelária, 65, Rio de Janeiro, CEP 20091906, Brasil.,Brazil
Reactor Building 3DModel for Evaluating the Pressures on Concrete Regularizationand Foundation Waterproofing Membrane
TS 51.19 (1786) Jason P. Petti, Donald A. Kalinich, Joonyub Jun, & Herman L. Graves III
Sandia National Laboratories and U.S. Nuclear Regulatory Commission, United States
Effects of Liner Degradation on the Severe Accident Consequences at a PWR Plant witha Reinforced Concrete Containment
TS 51.20 (1640) Jorge D. Riera 1, Ignacio Iturrioz 2 and Letícia F. F. Miguel 2
1 Department of Civil Engineering,2 Department of Mechanical Engineering, Universidade Federal do Rio Grande do Sul,Porto Alegre, RS, Brazil, Brazil
On Scale Effects and Mesh Independence in Dynamic Fracture Analysis by Means ofthe Discrete Element Method
TS 51.21 (2035) S.M.Basha1, R. K. Singh2 & T. Kant3
1Architecture & Civil Engineering Division, 2 Reactor Safety Division, Bhabha AtomicResearch Centre, Trombay, Mumbai, India, 3 Indian Institute of Technology Bombay,Powai, Mumbai, India
Numerical simulation of Plain Concrete Fracture experiments with Fictitious CrackModel
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components4(21)
1 Presentation (speaker) not confirmed before printing of the programme
Technical Session 51e Methodology, Modeling & Design
TS 51.22 (1787) Miloslav Hrazsky, Ivan Lopos, Milan Mikus
VUJE, Inc., Trnava, Slovakia
High energy pipe rupture effects elimination experience from projects dealing withWWER 440 V2 NPP piping assessment
TS 51.23 (1866) Takashi Maki, Yoshinari Munakata, Yoshiyuki Sato, Keiji Sekine, Takamasa Nishioka,Nobuyuki Niwa, Osamu Kontani
Japan Nuclear Fuel Limited, Kobori Research Complex Inc., Japan
Study on Radiation Shielding Performance of Reinforced Concrete Wall (1) LoadingTest of RC wall and Modeling of Concrete Cracks
TS 5.1.24 (1865) Takashi Maki, Yoshinari Munakata, Yoshiyuki Sato, Keiji Sekine, Yoshinori Sakai, KojiOishi, Kazuyuki Torii
Japan Nuclear Fuel Limited,Ohsaki Research Institute, Inc.,Shimizu Corporation, Japan
Study on Radiation Shielding Performance of Reinforced Concrete Wall (2): ShieldingAnalysis
TS 51.25 (1660) Katsuki Takiguchi et al
Tokyo Institute of Technology, Japan
Experiments on GammaRay Shielding Performance of Cracked Reinforced ConcreteWall
TS 51.26 (2148) Kenichi Suzuki1, Masakatsu Inagaki1, Shirou Fukunishi1, Tadashi Iijima2 , & TakashiMatsumoto3
1 Seismic Safety Division, Japan Nuclear Energy Safety Organization,, Japan
Seismic Capacity Test of Overhead Crane under Horizontal and Vertical Excitation Element Model Test Results on NonLinear Response Behavior
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components5(21)
1 Presentation (speaker) not confirmed before printing of the programme
Technical Session 51f Methodology, Modeling & Design
TS 51.27 (2479) V.Belyaev 1, V.Guskov 2, Y.Routman 3
1 Professor, Research Center for Capital Construction, SaintPetersburg; 2 Dr., JSCBureau of Special Mechanical Engineering, SaintPetersburg; 3 Professor, JSC Bureau ofSpecial Mechanical Engineering, SaintPetersburg ,
NPP SEISMIC PROTECTION AGAINST SHOCK AND VIBRATION LOADS
TS 51.28 (1668)
note1
Ilin Kirill, Korotkov Vladimir
OAO “Atomenergoproekt”, Russia
Reducing of spectral accelerations in NPP civil structures at the expense ofoptimization of their geometry
TS 51.29 (1945)
note1
David L. Luxat (1) and John C. Luxat (2)
(1) AMEC NSS, Toronto, Ontario, (2) McMaster University, Hamilton, Ontario, Canada
Response and Failure Criteria of Large Cylindrical Vessels to Rapid Pressurization inCANDU Severe Accidents
TS 51.30 (2016)
note1
GingLong Lin, ChiChang Lin, and JerFu Wang
Department of Civil Engineering, National Chung Hsing University, Taiwan
Protection of Seismic Structures using Variable FPS typed TMD System
TS 51.31 (2049) A. Limam, C. Mathon
Université de Lyon, INSALyon, LGCIE, F69621, Villeurbanne, France, France
Effect of Geometrical Defects and Cracks on the Collapse of Heat Exchanger UBentTubes Submitted to External Pressure
TS 51.32 (1667)
note1
Korotkov Vladimir, Kapustin Dmitry
OAO “Atomenergoproekt”, Moscow, Bakuninskaya str, 7, building 1, Russia, email:[email protected], Russia
More Precise Definition of Rayleigh Damping Matrix in Dynamic Analysis of NPP CivilStructures on ABAQUS
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components6(21)
1 Presentation (speaker) not confirmed before printing of the programme
Technical Session 52a Experiments & Tests
TS 52.1 (1598) Y. M. Parulekar 1, G.R. Reddy 1, K.K. Vaze 1, A.K. Ghosh 1,C. UmaShankar 1, H.S. Kushwaha 1, R. Ramesh babu 2, K.N. Mahule 1
1 Bhabha Atomic Research Centre, Mumbai, India
Seismic Stability of Glove Boxes Experiments and Analysis
TS 52.2 (1700) Sandrine Lermitte 1, Thierry Chaudat 1 Alexis Courtois 2
1 CEA DEN/Saclay, Laboratoire d’Etudes de Mécanique Sismique,2 EDF SEPTEN, Groupe Dynamique et Séisme, France
SMART 2008 Project Experimental Tests of a Reinforced Concrete Building Subjectedto Torsion Part 2 : Presentation Of The Tests Results
TS 52.3 (1702) Sooyong Park, YungMoo Shin, HaYeon Kim, Sanghyun Choi, DaeHyuk Kim ChangHun Hyun, MoonSoo Kim, SangYun Kim
Korea Maritime University, Korea National Railroad College, Korea Institute of NuclearSafety, Korea, South
Identification of Modal Parameters of a Containment Building Using Ambient VibrationMeasurements
TS 52.4 (1713) KyungWon Hahm 1, KyungJin Lee 2, and YongPyo Suh.3
KEPRI (Korea Electric Power Research Institute), Korea, South
Experimental Study on Seismic Reduction Effectiveness of Main Control Room in N.P.Pusing 3Directional Isolation System
TS 52.5 (1777) Kazuyuki Nagasawa, Shuichi Orita, Nobuaki Oshima, Norihide Tohyama, YoshioNamita,Shuichi Orita
Tokyo Electric Power Company, HitachiGE Nuclear Energy Ltd, Hitachi Ltd, ShimizuCorporation, Japan
Verification test for integrity of equipment foundations affected by dynamic load
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components7(21)
1 Presentation (speaker) not confirmed before printing of the programme
Technical Session 52b Experiments & Tests
TS 52.6 (1792) Haruhiko Kurino, Ryu Shimamoto, Fukashi Mori, Tomonori Kitaori, Satoru Aizawa,Yukio Naito
Kajima Corporation, Tokyo, Japan, Japan
Vibration Tests on Nuclear Power Station Stacks Equipped with Structural Control OilDampers
TS 52.7 (1875) Sung Gook Cho, Yang Hee Joe, Sung Tak Kim, SangKook Lee, Gi Sung Pang
JACE KOREA, Gyeonggi, Korea, Korea, South
Experimental Study on Modal Identification and Dynamic Amplification of a SteelFrame Structure
TS 52.8 (1885) Tarvinder Singh, R K Singh and A. K. Ghosh
Bhabha Atomic Research Centre, Trombay,India, India
INELASTIC AXISYMMETRIC ANALYSIS OF BARC PRESTRESSED CONCRETECONTAINMENT MODEL
TS 52.9 (1900) Yves E. Mondet1, Adele Klein2, Urs Bumann3
1Basler & Hofmann Consulting Eng.,2Basler & Hofmann Consulting Eng.,3HSK – SwissFederal Nuclear Safety Inspectorate, Switzerland
Structural Dynamic Analysis of a Non Symmetrical RC Building within the Scope of aBlind Prediction Contest – Project SMART 2008
TS 52.10 (1977) R K Singh, A K Ghosh, H S Kushwaha
Reactor Safety Division, Health Safety and Environment Group, Bhabha AtomicResearch Centre, Trombay, Mumbai 400 085, INDIA, India
Indian PHWR PreStressed Concrete Containment Performance Evaluation withBARCOM and Round Robin Analysis Program
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components8(21)
1 Presentation (speaker) not confirmed before printing of the programme
Technical Session 52c Experiments & Tests
TS 52.11(2008) Byong Jeong Choi 1, Keunkyeong Kim 2, ChongHak Kim 3, and Tae Young Kim 4
1) Associate Professor, Dept. of Architectural Engineering, Kyonggi University,SeodaemoonGu, Chungjeong Ro 2Ga 71, Seoul, Korea, [email protected], 2)KoreaHydeo and Nuclear Power Company, Youngdongdaero 411, KangnamGu, Seoul [email protected], 3) Korea Hydro and Nuclear Power Co., Daejeon, Korea,[email protected], 4) Principal Engineer, Dept. of Civil Engineering, Korea EngineeringCo., Yongin, Korea, [email protected], Korea, South
Experimental Compression Behavior of Stiffened SteelPlate Concrete (SSC) Structuresunder Compressive Loading
TS 52.12 (1680) Akihiro Matsuda, Yuichi Uchiyama, Masakatsu Inagaki, Susumu Tsuchino, HiroyukiUmetsu and Koji Shirai
University of Tsukuba, JNES and CRIEPI, Japan
Study on the MOX Fuel Manufacture Glovebox Containment for Earthquakes Deformation and Leakage Tests for Window Panels
TS 52.13 (1783) LE MAOULT Alain (1), BAIRRAO Rogerio (2) , & QUEVAL JeanClaude (3)
(1) CEA/DEN/SEMT/EMSI, (2) LNEC/DE/NESDE, (3) CEA/DEN/SEMT/EMSI, Portugal
Dynamic Interaction between the Shaking Table and the Specimen during EarthquakeTests
TS 52.14 (2002) P.Chellapandi, R.Srinivasan, S.C.Chetal and Baldev Raj
Indira Gandhi Centre for Atomic Research, Kalpakkam603102 India, India
Qualification of Creep, Fatigue and Fracture Design of PFBR Components Based OnTests
TS 52.15 (2564) Han Fengshan, Sun Libin
Institute of Nuclear and New Energy technology, China
Response of graphite dowelsocket structure under various loads
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components9(21)
1 Presentation (speaker) not confirmed before printing of the programme
Technical Session 52d Experiments & Tests
TS 52.16 (1892)
note1
Marco Domaneschi and Maria Gabriella Mulas
Department of Structural Engineering, Politecnico di Milano, Milano, Italy email:[email protected], [email protected], Italy
Structural Modeling and Analysis of the SMART2008 Shaking Table Specimen
TS 52.17 (2019)
note1
J.C. LE ROUX & A. ZEGHADI
EDF R&D, France
Crack opening in steam generator tubes submitted to an internal pressure:experimental and numerical modelling
TS 52.18 (2062)
note1
R. Redlinger, M. Kuznetsov, W. Breitung J. Grune, K. Sempert, T. Franke
Forschungszentrum Karlsruhe GmbH, ProScience GmbH, EnBW Kernkraft GmbH,Germany, Germany
Experimental and numerical simulation of radiolysis gas detonations in BWR exhaustpipes and mechanical response of the piping to the detonation pressure loads
Technical Session 53a Dynamic Response Impact
TS 53.1 (1595) XianXing (Lambert) Li
SNCLavalin Nuclear Inc., Canada
Nonlinear Impact Analysis of Pipe Whipping onto Restraints
TS 53.2 (1670) Jukka Kähkönen, Pentti Varpasuo
Fortum Nuclear Services Ltd, POB 100, 00048 FORTUM, Finland, Finland
The Effect of Cover Unit Drop on Loviisa NPP Primary Circuit During MaintenanceOutage
TS 53.3 (1857) Necip Onder Akinci, Jaspal Singh Saini, William H. Johnson
Bechtel Power Corporation, United States
Finite Element Analysis of the Primary Shield Structure and Evaluation for PostulatedReactor Pressure Vessel Head Drop
TS 53.4 (1601) E. Roos, W. Stadtmueller, S. Offermanns
Materialprüfungsanstalt Universität Stuttgart, Germany
Pipe Behaviour under Radiolysis Gas Detonations
TS 53.5 (1951) Renatas Karalevicius, Gintautas Dundulis, Sigitas Rimkevicius
Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute, Lithuania
Investigation of building structures response to heavy item drop
TS 53.6 (2057) Mehdi S. Zarghamee and KengWit Lim
Simpson Gumpertz & Heger Inc. , United States
Structural Evaluation of Drop Load Effects on Buried Structures
Technical Session 53b Dynamic Response Impact
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components10(21)
1 Presentation (speaker) not confirmed before printing of the programme
TS 53.7 (1603) XianXing (Lambert) Li
SNCLavalin Nuclear Inc., Canada
Missile Impact on Structural Members
TS 53.8 (1816) Anton Andonov, Kiril Apostolov, Dimitar Stefanov, Marin Kostov
Risk Engineering LTD., Bulgaria
On the Floor Response Spectra due to Aircraft Impact
TS 53.9 (1921) Markku Tuomala Kim Calonius, Arja Saarenheimo Auli Lastunen & Pekka Välikangas
Technical University of Tampere, email: [email protected], Finland
Numerical studies on prestressed impact loaded concrete walls
TS 53.10 (1730) Koji SHIRAI
Central Research Institute of Electric Power Industry (CRIEPI), Japan
Experimental studies of confinement integrity of metal cask subjected to impulsiveloads due to aircraft engine crash (Part.1)
TS 53.11 (1746) François Tarallo, MarieHélène Bonhomme, Nicolas Bourasseau, Bertrand Cirée,Georges Nahas and JeanMathieu Rambach
Institut de Radioprotection et de sûreté nucléaire (IRSN), France
IMPACT program tests: numerical simulations and interpretationof tests 661, 663 and673
TS 53.12 (1941) Gordon Bjorkman
US nuclear Regulatory Commission, United States
A Simple Dynamic Model for Estimating the Effect of Gaps on Response of a Spent FuelTransportation Cask Closure Lid During a Drop Impact
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components11(21)
1 Presentation (speaker) not confirmed before printing of the programme
Technical Session 53c Dynamic Response Impact
TS 53.13 (1961) Robert T. Bocchieri, Lawrence A. Twisdale, Claudia Northrup, Gary P. Gauthier andSteven W. Kirkpatrick
Applied Research Associates, Inc., United States
LSDYNA Impact Analyses of Nuclear Power Plant Structures for Tornado Missile RiskAnalysis
TS 53.14 (1711) Robert T. Bocchieri, Steven W. Kirkpatrick, David Kitzinger
1Applied Research Associates, Inc., 2672 Bayshore Parkway, Suite 1035, MountainView, CA 94043, USA, United States
Expansion of the Riera Approach for Predicting Aircraft Impact Damage to Steel andConcrete Buildings
TS 53.15 (2015) Nebojsa Orbovic1, Medhat Elgohary2, Namho Lee2, Andrei Blahoianu1
1Canadian Nuclear Safety Commission – Commission canadienne de sûreté nucléaire,280 Slater St. Ottawa, Ontario K1P 5S9, Canada, nebojsa.orbovic@cnscccsn.gc.ca,Canada
TESTS ON REINFORCED CONCRETE SLABS WITH PRESTRESSING AND WITHTRANSVERSE REINFORCEMENT UNDER IMPACT LOADING
TS 53.16 (2050) Ari Silde 1, Simo Hostikka 2, Ari Kankkunen 1
1 Technical Research Center of Fnland (VTT),2 Tehnical University of Helsinki (HUT), Finland
Studies of Liquid Dispersal from a Missile Impacting a Wall
TS 53.17 (1844) Arja Saarenheimo 1, Kim Calonius 1, Markku Tuomala 2 & Ilkka Hakola 1
1 Technical Research Center of Fnland (VTT)2 Tampere University of Technology (TUT), Finland
Numerical studies on shear reinforced impact loaded concrete walls
TS 53.18 (1666)
note1
Aleksandar Paskalov & Norbert Krutzik
Murray & Roberts SNCLavalin Nuclear (Pty) Ltd. (EPCM contractor to Pebble BedModular Reactor (Pty) Ltd on the PBMR DPP Project), Pebble House, 1279 MikeCrawford Avenue, Centurion 0046, South Africa, email:[email protected] NJKConsulting, Balduinstrasse 72, 60599Frankfurt/Main, Germany, email: [email protected], South Africa
Aircraft Crash Analysis of PBMR module building
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components12(21)
1 Presentation (speaker) not confirmed before printing of the programme
Technical Session 54 Dynamic Response Impulse
TS 54.1 (1819) YinNan Huang and Andrew Whittaker
University at Buffalo, United States
Structural Responses of Conventional and BaseIsolated Nuclear Power Plants for BlastLoadings
TS 54.2 (2042) R.K.Singh, S.K.Sinha A.Rama Rao
Reactor Engineering Division,Bhabha Atomic Research Centre, mumbai,India, India
Study of incident water hammer in an engineering loop under twophase flowexperiment
TS 54.3 (1883) Nicolas JOBERT, JeanLuc CHAMBRIN , Thierry MULLER, Benoît MIGOT
AREVANP, France
Flow Induced Vibrations for Reactor Internals of PWR – Less art, more science
TS 54.4 (2580) Daegi Hahm, InKil Choi, HongPyo Lee
Korea Atomic Energy Research Institute and Korea Electric Power Research Institute,Korea, South
Internal pressure capacity evaluation of prestressed concrete containment buildingsconsidering multiple aging effects
TS 54.5 (2465)
note1
JAVED IQBAL
University of Engineering & Technology Taxila, Pakistan
Evaluation of Containment against BlastInduced Ground Shock in Gneiss
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components13(21)
1 Presentation (speaker) not confirmed before printing of the programme
Technical Session 55a Seismic Response & Design Analysis & Design
TS 55.1 (1597) Y. M. Parulekar1, G.R. Reddy1, K.K. Vaze1, A.K. Ghosh1, H.S. Kushwaha1, R.Rameshbabu2
1 Bhabha Atomic Research Centre, Mumbai400085, India, India
Seismic response evaluation of safety related nuclear structure with yielding Dampersusing Linearization Techniques.
TS 55.2 (1656) 1) Dietrich Klein, FritzOtto Henkel 2) Ruediger Meiswinkel
1) Woelfel Beratende Ingenieure GmbH + Co. KG; 2) E.ON Kernkraft GmbH, Germany
Seismic qualification of class II buildings of nuclear power plants on the basis of nonnuclear seismic codes
TS 55.3 (1683) Pierre Labbé
IAEA / EDF, France
Title: Safety Significance of a Type of Seismic Input Motions and Consequences onNuclear Industry Practice subtitle:Results of the IAEA Coordinated Research Projecton the Safety Significance of NearField Earthquakes
TS 55.4a (2471) G. Atkinson1, N. Allotey2, A. Saudy2, and M. Elgohary2
1 University of Western Ontario, Ontario, Canada,
2 Atomic Energy of Canada Limited (AECL), Ontario, Canada, Canada
SpectraCompatible Time Histories for the ACR NPP in Eastern North America
TS 55.4b (2472) N. Alloety, A. Saudy, and M. Elgohary
Atomic Energy of Canada Limited (AECL), Mississauga, Ontario, Canada, Canada
SoilStructure Analysis for ACR Nuclear Island
TS 55.5 (1772) Tarek S. Aziz, D. Sc., P. Eng. (presented by J. Tcherner)
Atomic Energy of Canada Ltd, 2251 Speakman Drvie, Mississauga, Ontario, Canada,Canada
Earthquake Fatigue Analysis for CANDU Nuclear Power Plants
TS 55.6 (1697) Wonki Kim, Seung Joon Lee, Rae Young Jung and Moonsoo Kim
Professor of Hoseo University, Korea, South
Damping Values for Seismic Design of Nuclear Power Plant SC Structures
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components14(21)
1 Presentation (speaker) not confirmed before printing of the programme
Technical Session 55b Seismic Response & Design Analysis & Design
TS 55.7 (1781) Ryu Shimamoto, Shigeru Furukawa, Michiya Kuno, Minoru Kanechika, Haruhiko Kurino,Yoshinori Mihara
Chubu Electric Power Co, Japan
Analytical Study on Seismic Energy Balance of NPP Buildings Part 1 Formulation andVerification for Lattice Model
TS 55.8 (1838) Shigeru Furukawa1, Michiya Kuno1, Ryuu Shimamoto1 Minoru Kanechika2, KazuhiroKusama2, Yoshinori Mihara2
1Chubu Electric Power Co., Inc., Nagoya, JAPAN 2Kajima Corporation, Tokyo, JAPAN,Japan
Analytical Study on Seismic Energy Balance of NPP Buildings Part 2 Application andUltimate State Estimation with Energy Index
TS 5.5.9 (1851) Pekka Välikangas, Jukka Myllymäki, Jorma Sandberg
Radiation and Nuclear Safety Authority (STUK), Finland
Qualification against Seismic and Other External Vibration, Experiences from theOversight of Olkiluoto 3
TS 55.10 (1947) Short, Steve, Orhan Gurbuz, Mike Salmon
SGH, Bechtel Corp., LANL, United States
Update of ASCE Standard “Seismic Analysis of SafetyRelated Nuclear Structures andCommentary”
TS 55.11 (1974) Jukka Kähkönen, Pentti Varpasuo
Fortum Nuclear Services Ltd, Finland
Seismic FEM Analysis of Reinforced Concrete Structure in SMART2008 Project
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components15(21)
1 Presentation (speaker) not confirmed before printing of the programme
Technical Session 55c Seismic Response & Design Analysis & Design
TS 55.12 (1943) Carlos Coronado. Ph.D., Sanjeev R. Malushte, Ph.D., S.E., Javeed Munshi, Ph.D., S.E.
Bechtel Power Corporation, United States
A Rational Seismic Design Approach for Reinforced Concrete Walls for Nuclear PowerPlants
TS 55.13 (1908) Jaegyun Park1, ChulHun Chung1, Jang Seok Yi 2, ByungMoo Jin3
1 Dankook University, Korea, South2 Hyundai Institute of Construction Technology Development, , Korea, South3 Daewoo Engineering & Construction, , Korea, South
Dynamic Analysis of a Concrete ShearWall
TS 55.14 (1983) Yafei MO 1, Daniel PROC 2 and Jing WEN 3
1) Master, Research Center of CEFR, China Institute of Atomic Energy, Beijing([email protected]), 2) Doctor, Seismic Mechanic Study Laboratory of CEA, Centerof Saclay, France, 3) Doctor, Research Center of CEFR, China Institute of AtomicEnergy, Beijing, China
The FSI Seismic Analysis for FBR Core Assemblies
TS 55.15 (2074) Shodo AKITA1, Takuya SUZUKI2, Naohiro NAKAMURA2, Masao KOBA 1, TomioNAKANO31 The Kansai Electric Power Co., Inc.,2 Takenaka Corporation, 3 Newjec Inc., Japan
A study on seismic behavior of nuclear power building in strong nonlinear area andfragility evaluation using 3 dimensional FEM Part1 Ultimate seismic condition ofbuilding
TS 55.16 (2075) Takuya SUZUKI1, Shodo AKITA 2, Naohiro NAKAMURA1, Masao KOBA 2, TomioNAKANO3
1 Takenaka Corporation, 2 The Kansai Electric Power Co., Inc.,3 Newjec Inc., Japan
A study on seismic behavior of nuclear power building in strong nonlinear area andfragility evaluation using 3 dimensional FEM Part2 Fragility evaluation
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components16(21)
1 Presentation (speaker) not confirmed before printing of the programme
Technical Session 55d Seismic Response & Design Analysis & Design
TS 55.17 (2542) Akinori TOMODA, Tetsuya WATANABE and Kihachiro TANAKA
Division of Mechanical Engineering and Science, Saitama University, Japan
Seismic Response of a Twodegreeoffreedom System with Friction Based on the MassRatio
TS 55.18 (2615) Warren Price
National Nuclear Laboratory, England, United Kingdom
Seismic Assessment of the Sellafield B38 Mobile Caves
TS 55.19 (1970) Min Kyu Kim & In Kil Choi
Korea Atomic Energy Research Institute, Korea, South
A Failure Mode Evaluation of a 480V MCC in Nuclear Power Plants at the SeismicEvents
TS 55.20 (2526) Tarcísio de F. Cardoso, Andreia A. Diniz de Almeida, João L. Roehl
ELETRONUCLEAR; PUC Rio, Brazil
On the generation of inelastic secondary system seismic response spectra
TS 55.21 (1830) Masahiko NAKAMURA , Fumio SASAKI , Mitsuru MINE, Kazuki YOKOYAMA,TetsuoTAMAOKI , Akira TANABE , Wataru MIZUMACHI and Michio YAMADA
Tokyo University of Science, Japan
Study on NonStationarity of Frequency by Synthesis Method of Earthquake Motions
Technical Session 55e Seismic Response & Design Analysis & Design
TS 55.22 (1689)
note1
Suchibrata Dalal, Dr. Mahua Chakrabarti
Veermata Jijabai Technolical Institute, Matunga, Mumbai , India,
Analysis of Behaviour of Raft Foundations under Seismic and Impulsive Loading
TS 55.23 (1832)
note1
P. Vasilyev
CKTIVibroseism, Saint Petersburg, Russia
Generation of an Artificial Time History Matching MultipleDamping Floor DesignResponse Spectra
TS 55.24 (1810)
note1
Leonid Lakishev 1 , Alexander Schukin 2, Maxim Vayndrakh 2
1 “CKTIVIBROSEISM” Co. Ltd, Russia
Seismic Analysis of WWER–1000 Control Rod Drive System
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components17(21)
1 Presentation (speaker) not confirmed before printing of the programme
Technical Session 56a Seismic Response & Design Component & System
TS 56.1 (1594) XianXing (Lambert) Li
SNCLavalin Nuclear Inc., Canada
EarthquakeInduced Sloshing Effects on Seismic Qualification of Liquid Storage Tanks
TS 56.2 (1790) LE BRETON Francis, PETESCH Cécile(paper presented by Phlippe MONETTE)
AREVA, PARIS LA DEFENSE, FRANCE, France
Stress Analysis Criteria for Piping. RCCM 2002 Rules and Validation.
TS 56.3 (1813) Dookie Kim, Sung Gook Cho, Sunghyuk Ko, Young Il Lee
Department of Civil and Environment Engineering, Kunsan National University, Korea,South
Modal Identification of Instrumentation Cabinet of Nuclear Power Plant Based onStochastic Subspace Identification
TS 56.4 (1932) Pavel Spassov, Marin Jordanov, Maya Kancheva, Georgy Kostov and Petar Bakardjiev
EQE Bulgaria AD , Bulgaria
Seismic Analyses of Safety Important Piping Systems Situated in Reactor Building ofUnits 5 and 6, Kozloduy NPP
TS 56.5 (1988) Tian Jinmei
China Nuclear Power Engineering Co.,Ltd. Beijing, 100840, China,email:[email protected], China
The Effects of Seismic Spectrum on Seismic Analysis
Technical Session 56b Seismic Response & Design Component & System
TS 56.6 (2000) P.Chellapandi, S.C.Chetal and Baldev Raj
Indira Gandhi Centre for Atomic Research, Kalpakkam603 102, India, India
SEISMIC ANALYSIS OF PRIMARY SODIUM SYSTEM COMPONENTS FOR THE LOOP TYPEFAST BREEDER REACTOR
TS 56.7 (1973) K.V. Subramanian, S.M. Palekar, H.A. Mapari, R. Balaji
TCE Consulting Engineers, India
Salient Aspects of Analysis and Design of Large Integrated Safety Related Structures
TS 56.8 (1653) Andrey V. Petrenko
AtomEnergoProject, 2nd Sovetskaya str, 9/2A, StPetersburg, 191036, Russia, email:[email protected], Russia
An optimal solution search under design for a pipeline support system to withstand aseismic excitation
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components18(21)
1 Presentation (speaker) not confirmed before printing of the programme
TS 56.9 (2089) Mansour Tabatabaie and Basilio Sumodobila
SC Solutions, Inc., United States
Component Mode Synthesis Based SSI Analysis of Complex Structural Systems usingSASSI
TS 56.10 (1635)
note1
Viorel Serban, Marian Androne
Subsidiary of Technology and Engineering for Nuclear Projects (SITON), Romania
Sistematic errors in the numeric analyses of computer programs used for thedetermination of the flexible structure seismic response
TS 56.11 (2588)
note1
Jing WEN, Lei SUN, Hongyi YANG, Xuede CHEN, Hailong LI, Qing SONG, Xiaoxuan LI &Jiang QIAN
China Fast Reactor Research Center, China Institute of Atomic Energy, Beijing, China,China
Qualification seismic test on control rod driving mechanism of CEFR
Technical Session 57a Seismic Response & Design Seismic Structural Integrity (SSI)
TS 57.1 (1592) Alexander Tyapin
Atomenergoproject (Moscow), Russia
FREQUENCYDEPENDENT IMPEDANCES IN THE TIMEDOMAIN SSI ANALYSIS:MODIFICATION OF SEISMIC INPUT
TS 57.2 (1669) Khawaja Ahsan Qadeer, Muhammad Sadiq, Rong Pan, Hou Chunlin
Pakistan Nuclear Regulatory Authority; Nuclear and Radiation Safety Center, China,Pakistan
Seismic Analysis of Reactor Building of a NPP including Soil Structure InteractionEffects and Comparison with Two Additional Sites
TS 57.3 (1740) Farhang Ostadan, Traek Elkhorabi
Bechtel, United States
Amplification of seismic motion at deep soil sites
TS 57.4 (1853) Ghiocel Dan Mircea 1, Short Stephen 2 and Greg Hardy 2
1 GP Technologies, USA, and 2 Simpson, Gumpertz and Heger, USA, United States
Seismic Motion Incoherency Effects on SSI Response of Nuclear Islands with SignificantMass Eccentricities and Different Embedment Levels
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components19(21)
1 Presentation (speaker) not confirmed before printing of the programme
Technical Session 57b Seismic Response & Design Seismic Structural Integrity (SSI)
TS 57.5 (1874) SangHoon Lee, JooHyung Kang
Korea Power Engineering Company, Inc., Korea, South
Seismic Response Impact of Incoherent SSI Analysis by New HardRock CoherencyModel
TS 57.6 (2076) Mansour Tabatabaie(1), Basilio Sumodobila(1), Calvin Wong(2) and Todd Oswald(2)
(1) SCSolutions, Inc. and (2) AREVA NP, Inc., United States
The Effect of Foundation Embedment on Seismic SSI Response of EPR Nuclear IslandStructures
TS 57.7 (3193) Takayuki Koyanagi 1, Rikiro Kikuchi 1, Minoru Kanechika 2, and Atsushi Suzuki 2
1 Nuclear Asset Management Department, Tokyo Electric Power Company,2 Nuclear Power Department, Kajima Corporation, Akasaka, Minatoku, Tokyo, Japan
Simulation Analysis of Reactor Buildings on Niigataken Chuetsuoki Earthquake atKashiwazakiKariwa Nuclear Power Plant
TS 57.8 (3192) Atsushi Suzuki 2, Rikiro Kikuchi 1, Takayuki Koyanagi 1, Minoru Kanechika 2,and Yoshinori Mihara 2
1 Nuclear Asset Management Department, Tokyo Electric Power Company,2 Nuclear Power Department, Kajima Corporation, Akasaka, Minatoku, Tokyo, Japan
Response and Seismic Margin of Kashiwazaki Kariwa Nuclear Power Plant Buildingduring Chuetsuoki Earthquake
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components20(21)
1 Presentation (speaker) not confirmed before printing of the programme
Technical Session 57c Seismic Response & Design Seismic Structural Integrity (SSI)
TS 57.9 (1749)
note1
Ragunath Sankaranarayanan+ and Oliver Schneider*
+AREVA NP Inc, NEECA, 7207 IBM Drive, Charlotte, NC, USA. Email:[email protected]; *AREVA NP GmbH, NEECG, Kaiserleistrasse 29, 63067Offenbach am Main, Germany. Email: [email protected];, United States
Conservatism in the use of stick models in dynamic SSI analysis
TS 57.10 (1665)
note1
Aleksandar Paskalov, Dan M. Ghiocel & Gary Styger
Murray & Roberts SNCLavalin Nuclear (Pty) Ltd. (EPCM contractor to Pebble BedModular Reactor (Pty) Ltd on the PBMR DPP Project), Pebble House, 1279 MikeCrawford Avenue, Centurion 0046, South Africa, email:[email protected] Ghiocel Predictive Technologies Inc., 38 HarperDrive, Pittsford, New York 14534, USA, email: dan.ghiocel@ghioceltech.com, SouthAfrica
SSI Analysis of PBMR module building to South African high frequency input motions
TS 57.11 (1611)
note1
YunSuk CHUNG1 & Isam SHAHROUR2
Korea Institute of Nuclear Safety & University of Sciences and Technologies of Lille,Korea, South
Inertial Interaction Analysis in SoilPilesStructure System
Technical Session 58a Miscellaneous
TS 58.1 (2004) Bhuwan Chandra Sati, S. Jalaldeen, Sanjeev Kumar, S.Raghupathy, P. Chellapandi andS.C.Chetal
Indira Gandhi Centre for Atomic Research, Kalpakkam, India, India
INELASTIC STRAIN AT SLIDING JOINT BETWEEN PRIMARY RAMP AND PRIMARY TILTINGMECHANISM OF PROTOTYPE FAST BREEDER REACTOR
TS 58.2 (1696) Pentti Varpasuo, Jukka Kähkönen
Fortum Nuclear Services Ltd, Finland
FORTUM PARTICIPATION IN BARCOM ROUND ROBIN PRETEST SIMULATION: MIDTERM ANALYSIS
TS 58.3 (1701) Pentti Varpasuo
Fortum Nuclear Services Ltd,, Finland
FORTUM PARTICIPATION IN IAEA EBP BENCHMARK FOR KASHIVAZAKIKARIWA NPPUNIT 7 RESPONSE IN JULY 2007 EVENT
TS 58.4 (1721) Andrew J. Murphy1, Andrei Blahoianu2, and Alejandro Huerta3
1) U.S. Nuclear Regulatory Commission, Washington, DC, USA ([email protected]), UnitedStates
Activities of OECD/NEA in the Fields of Seismic Hazard Assessment & EarthquakeEngineering Activities of OECD/NEA in the Fields of Seismic Hazard Assessment &Earthquake Engineering
TS 58.5 (1807) Anton Andonov, Dimitar Stefanov, Marin Kostov
Risk Engineering LTD., Bulgaria
Division 5 Modeling, Testing and Response Analysis of Structures, Systems and Components21(21)
1 Presentation (speaker) not confirmed before printing of the programme
Performance Based Capacity Assessment of WWER1000 Containment Structure forInternal Accidents
Technical Session 58b Miscellaneous
TS 58.6 (1839) Akihiro Kondo, Yasuo Takenaka, Eiji Takaoka, Makiko Hikita, Yo Hyodo, Haruyuki.Kitamura
Kajima Corporation, Japan
HeatMechanics Interaction Behavior of Lead Rubber Bearings for Seismic BaseIsolation under Large and Cyclic Lateral Deformation Part 1: Dynamic Loading Test ofLRB and Development of Analytical Method
TS 58.7 (1840) Nobuhisa Sato,Shigeru Furukawa, Michiya Kuno, Ryu Shimamoto,Yasuo Takenaka,Takashi Nakayama, Akihiro Kondo
Kajima Corporation, Japan
Heatmechanics Interaction Behavior of Lead Rubber Bearings for Seismic BaseIsolation under Large and Cyclic Lateral Deformation Part 2: Seismic Response Analysisof Base Isolated Reactor Building subjected to Horizontal BiDirectional EarthquakeMotion
TS 58.8 (1877) P.N. Dubey, G.R. Reddy, K. K. Vaze, A.K. Ghosh, H.S. Kushwaha
Bhabha Atomic Research Centre, India
PERFORMANCE OF XPLATE ELASTOPLASTIC DAMPERS, A PASSIVE SEISMIC SUPPORTSFOR NUCLEAR PIPING UNDER CYCLIC LOADING
TS 58.9 (1963) Igor Simonovski, Boštjan Kon&
269;ar, Leon Cizelj
Jožef Stefan Institute, Reactor engineering division, Jamova cesta 39, SI1000 Ljubljana,Slovenia, Slovenia
Thermomechanical analysis of a helium cooled divertor of a fusion reactor
TS 58.10 (1829)
note1
Alexander V. Kultsep Alexey M. Berkovsky
CKTIVibroseism Ltd., Russia
Seismic Margin Assessment of Demineralized water reserve tank