Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 1(21)

Division 5: Modeling, Testing and Response Analysis of Structures, Systems and Components Division Coordinators: P.C.Basu, Andrei Blahoianu, Susumu Nakamura, Jari Puttonen Technical Sessions (tentative) •

TS 5-1a, b, c, d, e, f: Methodology, Modeling & Design

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TS 5-2a, b, c (d): Experiments & Tests

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TS 5-3a, b: Dynamic Response - Impact

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TS 5-4: Dynamic Response - Impulse

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TS 5-5a, b, c, d (e): Seismic Response & Design - Analysis & Design

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TS 5-6a, b Seismic Response & Design - Component & System

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TS 5-7a, b (c): Seismic Response & Design - Seismic Structural Integrity (SSI)

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TS 5-8a, b: Miscellaneous

Technical Session 5-1a Methodology, Modeling & Design

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TS 5-1.1 (1577)

Yerishca Mudaly1 & M.M. Cepkauskas2 1 Eskom PBMR Client Office, Cape Town, South Africa PBMR Loop Acoustics

TS 5-1.2 (1632)

Attinger Richard, Kluegel Jens-Uwe NPP Goesgen-Daeniken, Switzerland, Switzerland A Model for the Hysteresis of Concrete to Describe the Cyclic Fatigue of Reinforced Concrete Structures During an Earthquake

TS 5-1.3 (1641)

Jukka Kähkönen Fortum Nuclear Services Ltd, Finland Steam Generator Tube Plugging FEM Analysis

TS 5-1.4 (1692)

Akop Sargsian, Andrey Grishin& Elena Gukova Atomenergoproject, Russia Generation of Dynamic Mechanical Model of Inertial Soil Foundation in Consideration of NPP Structures Basement Finite Stiffness

TS 5-1.5 (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 of Unanchored Platforms

Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 2(21) Technical Session 5-1b Methodology, Modeling & Design

TS 5-1.6 (1811)

William Johnson, Necip Akinci Bechtel Power Corporation, Frederick, MD, USA, United States Off-Axis Underground Soil Pressures from Surface Impact Loads

TS 5-1.7 (1833)

Alexey Berkovsky, Peter Vasilyev, Oleg Kireev CKTI-VIBROSEISM, Russia Modeling of high viscous dampers in piping dynamic analysis. Different approaches and acceptable limits for simplifications.

TS 5-1.8 (1940)

Gordon Bjorkman, Doug Ammerman US Nuclear Regulatory Commission, Sandia National Laboratory, United States Strain-Based Acceptance Criteria for Section III of the ASME Boiler and Pressure Vessel Code

TS 5-1.9 (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 37-Element Bundle

TS 5-1.10 (2006)

Sajish.S.D, R.Srinivasan, P.Chellapandi and S.C Chetal Indira Gandhi Center for Atomic Research-Kalpakkam, India, India STRUCTURAL INTEGRITY ASSESSMENT OF DHX UNDER CDA PRESSURE LOADING

Technical Session 5-1c Methodology, Modeling & Design

TS 5-1.11 (2009)

Christophe VASSE EDF Recherche et Développement, France Developing a numerical model to describe the mechanical behaviour of die-formed expanded graphite for valve stems sealing

TS 5-1.12 (1780)

Sudhir J. Shah, Berenger d"Uston and Gary T. Williams AREVA NP Inc., Fuel America, United States Fuel Assembly Two-Beam Dynamic Model Response to Faulted Condition Loads

TS 5-1.13 (1911)

John D. Stevenson J.D. Stevenson, Consulting Engineer, United States APPLICATION AND EVALUATION OF “DESIGN BY RULE” PROCEDURES APPLICABLE TO NUCLEAR POWER PLANT ASME B&PVC SECTION III CLASS 2 AND 3 PIPING

TS 5-1.14 (2043)

Billon François, Goussard Pascale, Batmale Guillaume COMEX NUCLEAIRE, France Advanced Analysis of Gasketed Pressure Vessel Closure Systems

TS 5-1.15 (1843)

Yoshio Ikeda, Yukio Shimomura, Masashi Kawamura, Noriaki Sako Taisei Corporation, Nihon University Junior College, Nihon University, Nihon University Junior College, Japan

1

Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 3(21) Analytical Investigation for Attenuation Material with Vibration Reduction Performance

Technical Session 5-1d Methodology, Modeling & Design TS 5-1.16 (2474)

Dr. Taha AL-Shawaf and Ms. Lingyah Yen AREVA NP Inc, United States REACTOR HEAD STAND EVALUATION USING SIMPLIFIED NON-LINEAR ANALYSIS

TS 5-1.17 (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 Gas-cooled Reactor

TS 5-1.18 (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 20091-906, Brasil., Brazil Reactor Building 3D-Model for Evaluating the Pressures on Concrete Regularization and Foundation Waterproofing Membrane

TS 5-1.19 (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 with a Reinforced Concrete Containment

TS 5-1.20 (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 of the Discrete Element Method

TS 5-1.21 (2035)

S.M.Basha1, R. K. Singh2 & T. Kant3 1Architecture & Civil Engineering Division, 2 Reactor Safety Division, Bhabha Atomic Research Centre, Trombay, Mumbai-, India, 3 Indian Institute of Technology Bombay, Powai, Mumbai, India Numerical simulation of Plain Concrete Fracture experiments with Fictitious Crack Model

1

Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 4(21) Technical Session 5-1e Methodology, Modeling & Design TS 5-1.22 (1787)

Miloslav Hrazsky, Ivan Lopos, Milan Mikus VUJE, Inc., Trnava, Slovakia High energy pipe rupture effects elimination - experience from projects dealing with WWER 440 V2 NPP piping assessment

TS 5-1.23 (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) Loading Test of RC wall and Modeling of Concrete Cracks

TS 5.1.24 (1865)

Takashi Maki, Yoshinari Munakata, Yoshiyuki Sato, Keiji Sekine, Yoshinori Sakai, Koji Oishi, Kazuyuki Torii Japan Nuclear Fuel Limited,Ohsaki Research Institute, Inc.,Shimizu Corporation, Japan Study on Radiation Shielding Performance of Reinforced Concrete Wall (2): Shielding Analysis

TS 5-1.25 (1660)

Katsuki Takiguchi et al Tokyo Institute of Technology, Japan Experiments on Gamma-Ray Shielding Performance of Cracked Reinforced Concrete Wall

TS 5-1.26 (2148)

Kenichi Suzuki1, Masakatsu Inagaki1, Shirou Fukunishi1, Tadashi Iijima2 , & Takashi Matsumoto3 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 Non-Linear Response Behavior-

1

Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 5(21) Technical Session 5-1f Methodology, Modeling & Design TS 5-1.27 (2479)

V.Belyaev 1, V.Guskov 2, Y.Routman 3 1 Professor, Research Center for Capital Construction, Saint-Petersburg; 2 Dr., JSC Bureau of Special Mechanical Engineering, Saint-Petersburg; 3 Professor, JSC Bureau of Special Mechanical Engineering, Saint-Petersburg , NPP SEISMIC PROTECTION AGAINST SHOCK AND VIBRATION LOADS

TS 5-1.28 (1668)

Ilin Kirill, Korotkov Vladimir OAO “Atomenergoproekt”, Russia Reducing of spectral accelerations in NPP civil structures at the expense of optimization of their geometry

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TS 5-1.29 (1945) note

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TS 5-1.30 (2016) note

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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 in CANDU Severe Accidents Ging-Long Lin, Chi-Chang Lin, and Jer-Fu Wang Department of Civil Engineering, National Chung Hsing University, Taiwan Protection of Seismic Structures using Variable FPS typed TMD System

TS 5-1.31 (2049)

A. Limam, C. Mathon Université de Lyon, INSA-Lyon, LGCIE, F-69621, Villeurbanne, France, France Effect of Geometrical Defects and Cracks on the Collapse of Heat Exchanger U-Bent Tubes Submitted to External Pressure

TS 5-1.32 (1667)

Korotkov Vladimir, Kapustin Dmitry

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OAO “Atomenergoproekt”, Moscow, Bakuninskaya str, 7, building 1, Russia, e-mail: [email protected], Russia More Precise Definition of Rayleigh Damping Matrix in Dynamic Analysis of NPP Civil Structures on ABAQUS

1

Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 6(21) Technical Session 5-2a Experiments & Tests TS 5-2.1 (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 5-2.2 (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 Subjected to Torsion Part 2 : Presentation Of The Tests Results

TS 5-2.3 (1702)

Sooyong Park, Yung-Moo Shin, Ha-Yeon Kim, Sanghyun Choi, Dae-Hyuk Kim ChangHun Hyun, Moon-Soo Kim, Sang-Yun Kim Korea Maritime University, Korea National Railroad College, Korea Institute of Nuclear Safety, Korea, South Identification of Modal Parameters of a Containment Building Using Ambient Vibration Measurements

TS 5-2.4 (1713)

Kyung-Won Hahm 1, Kyung-Jin Lee 2, and Yong-Pyo Suh.3 KEPRI (Korea Electric Power Research Institute), Korea, South Experimental Study on Seismic Reduction Effectiveness of Main Control Room in N.P.P using 3-Directional Isolation System

TS 5-2.5 (1777)

Kazuyuki Nagasawa, Shuichi Orita, Nobuaki Oshima, Norihide Tohyama, Yoshio Namita,Shuichi Orita Tokyo Electric Power Company, Hitachi-GE Nuclear Energy Ltd, Hitachi Ltd, Shimizu Corporation, Japan Verification test for integrity of equipment foundations affected by dynamic load

1

Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 7(21) Technical Session 5-2b Experiments & Tests TS 5-2.6 (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 Oil Dampers

TS 5-2.7 (1875)

Sung Gook Cho, Yang Hee Joe, Sung Tak Kim, Sang-Kook Lee, Gi Sung Pang JACE KOREA, Gyeonggi, Korea, Korea, South Experimental Study on Modal Identification and Dynamic Amplification of a Steel Frame Structure

TS 5-2.8 (1885)

Tarvinder Singh, R K Singh and A. K. Ghosh Bhabha Atomic Research Centre, Trombay,India, India INELASTIC AXISYMMETRIC ANALYSIS OF BARC PRESTRESSED CONCRETE CONTAINMENT MODEL

TS 5-2.9 (1900)

Yves E. Mondet1, Adele Klein2, Urs Bumann3 1Basler & Hofmann Consulting Eng.,2Basler & Hofmann Consulting Eng.,3HSK – Swiss Federal Nuclear Safety Inspectorate, Switzerland Structural Dynamic Analysis of a Non Symmetrical RC Building within the Scope of a Blind Prediction Contest – Project SMART 2008

TS 5-2.10 (1977)

R K Singh, A K Ghosh, H S Kushwaha Reactor Safety Division, Health Safety and Environment Group, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, INDIA, India Indian PHWR Pre-Stressed Concrete Containment Performance Evaluation with BARCOM and Round Robin Analysis Program

1

Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 8(21) Technical Session 5-2c Experiments & Tests TS 5-2.11(2008)

Byong Jeong Choi 1, Keunkyeong Kim 2, Chong-Hak Kim 3, and Tae Young Kim 4 1) Associate Professor, Dept. of Architectural Engineering, Kyonggi University, Seodaemoon-Gu, Chungjeong Ro 2Ga 71, Seoul, Korea, [email protected], 2)Korea Hydeo and Nuclear Power Company, Youngdongdaero 411, Kangnam-Gu, Seoul Korea [email protected], 3) Korea Hydro and Nuclear Power Co., Daejeon, Korea, [email protected], 4) Principal Engineer, Dept. of Civil Engineering, Korea Engineering Co., Yongin, Korea, [email protected], Korea, South Experimental Compression Behavior of Stiffened Steel-Plate Concrete (SSC) Structures under Compressive Loading

TS 5-2.12 (1680)

Akihiro Matsuda, Yuichi Uchiyama, Masakatsu Inagaki, Susumu Tsuchino, Hiroyuki Umetsu 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 5-2.13 (1783)

TS 5-2.14 (2002)

TS 5-2.15 (2564)

1

LE MAOULT Alain (1), BAIRRAO Rogerio (2) , & QUEVAL Jean-Claude (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 Earthquake Tests P.Chellapandi, R.Srinivasan, S.C.Chetal and Baldev Raj Indira Gandhi Centre for Atomic Research, Kalpakkam-603102 India, India Qualification of Creep, Fatigue and Fracture Design of PFBR Components Based On Tests Han Fengshan, Sun Libin Institute of Nuclear and New Energy technology, China Response of graphite dowel-socket structure under various loads

Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 9(21) Technical Session 5-2d Experiments & Tests TS 5-2.16 (1892) note

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TS 5-2.17 (2019) note

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TS 5-2.18 (2062) note

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Marco Domaneschi and Maria Gabriella Mulas Department of Structural Engineering, Politecnico di Milano, Milano, Italy - e-mail: [email protected], [email protected], Italy Structural Modeling and Analysis of the SMART-2008 Shaking Table Specimen 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 R. Redlinger, M. Kuznetsov, W. Breitung J. Grune, K. Sempert, T. Franke Forschungszentrum Karlsruhe GmbH, Pro-Science GmbH, EnBW Kernkraft GmbH, Germany, Germany Experimental and numerical simulation of radiolysis gas detonations in BWR exhaust pipes and mechanical response of the piping to the detonation pressure loads

Technical Session 5-3a Dynamic Response - Impact TS 5-3.1 (1595)

Xian-Xing (Lambert) Li SNC-Lavalin Nuclear Inc., Canada Nonlinear Impact Analysis of Pipe Whipping onto Restraints

TS 5-3.2 (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 Maintenance Outage

TS 5-3.3 (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 Postulated Reactor Pressure Vessel Head Drop

TS 5-3.4 (1601)

E. Roos, W. Stadtmueller, S. Offermanns Materialprüfungsanstalt Universität Stuttgart, Germany Pipe Behaviour under Radiolysis Gas Detonations

TS 5-3.5 (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 5-3.6 (2057)

Mehdi S. Zarghamee and Keng-Wit Lim Simpson Gumpertz & Heger Inc. , United States Structural Evaluation of Drop Load Effects on Buried Structures

Technical Session 5-3b Dynamic Response - Impact

1

Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 10(21) TS 5-3.7 (1603)

Xian-Xing (Lambert) Li SNC-Lavalin Nuclear Inc., Canada Missile Impact on Structural Members

TS 5-3.8 (1816)

Anton Andonov, Kiril Apostolov, Dimitar Stefanov, Marin Kostov Risk Engineering LTD., Bulgaria On the Floor Response Spectra due to Aircraft Impact

TS 5-3.9 (1921)

Markku Tuomala Kim Calonius, Arja Saarenheimo Auli Lastunen & Pekka Välikangas Technical University of Tampere, e-mail: [email protected], Finland Numerical studies on pre-stressed impact loaded concrete walls

TS 5-3.10 (1730)

Koji SHIRAI Central Research Institute of Electric Power Industry (CRIEPI), Japan Experimental studies of confinement integrity of metal cask subjected to impulsive loads due to aircraft engine crash (Part.1)

TS 5-3.11 (1746)

François Tarallo, Marie-Hélène Bonhomme, Nicolas Bourasseau, Bertrand Cirée, Georges Nahas and Jean-Mathieu Rambach Institut de Radioprotection et de sûreté nucléaire (IRSN), France IMPACT program tests: numerical simulations and interpretationof tests 661, 663 and 673

TS 5-3.12 (1941)

1

Gordon Bjorkman US nuclear Regulatory Commission, United States A Simple Dynamic Model for Estimating the Effect of Gaps on Response of a Spent Fuel Transportation Cask Closure Lid During a Drop Impact

Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 11(21) Technical Session 5-3c Dynamic Response - Impact TS 5-3.13 (1961)

Robert T. Bocchieri, Lawrence A. Twisdale, Claudia Northrup, Gary P. Gauthier and Steven W. Kirkpatrick Applied Research Associates, Inc., United States LS-DYNA Impact Analyses of Nuclear Power Plant Structures for Tornado Missile Risk Analysis

TS 5-3.14 (1711)

Robert T. Bocchieri, Steven W. Kirkpatrick, David Kitzinger 1Applied Research Associates, Inc., 2672 Bayshore Parkway, Suite 1035, Mountain View, CA 94043, USA, United States Expansion of the Riera Approach for Predicting Aircraft Impact Damage to Steel and Concrete Buildings

TS 5-3.15 (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, [email protected], Canada TESTS ON REINFORCED CONCRETE SLABS WITH PRE-STRESSING AND WITH TRANSVERSE REINFORCEMENT UNDER IMPACT LOADING

TS 5-3.16 (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 5-3.17 (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 5-3.18 (1666) note

1

Aleksandar Paskalov & Norbert Krutzik Murray & Roberts SNC-Lavalin Nuclear (Pty) Ltd. (EPCM contractor to Pebble Bed Modular Reactor (Pty) Ltd on the PBMR DPP Project), Pebble House, 1279 Mike Crawford Avenue, Centurion 0046, South Africa, email: [email protected] NJK-Consulting, Balduinstrasse 72, 60599 Frankfurt/Main, Germany, email: [email protected], South Africa Aircraft Crash Analysis of PBMR module building

1

Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 12(21) Technical Session 5-4 Dynamic Response - Impulse TS 5-4.1 (1819)

Yin-Nan Huang and Andrew Whittaker University at Buffalo, United States Structural Responses of Conventional and Base-Isolated Nuclear Power Plants for Blast Loadings

TS 5-4.2 (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 two-phase flow experiment

TS 5-4.3 (1883)

Nicolas JOBERT, Jean-Luc CHAMBRIN , Thierry MULLER, Benoît MIGOT AREVA-NP, France Flow Induced Vibrations for Reactor Internals of PWR – Less art, more science

TS 5-4.4 (2580)

Daegi Hahm, In-Kil Choi, Hong-Pyo Lee Korea Atomic Energy Research Institute and Korea Electric Power Research Institute, Korea, South Internal pressure capacity evaluation of prestressed concrete containment buildings considering multiple aging effects

TS 5-4.5 (2465)

JAVED IQBAL University of Engineering & Technology Taxila, Pakistan Evaluation of Containment against Blast-Induced Ground Shock in Gneiss

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Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 13(21) Technical Session 5-5a Seismic Response & Design - Analysis & Design TS 5-5.1 (1597)

Y. M. Parulekar1, G.R. Reddy1, K.K. Vaze1, A.K. Ghosh1, H.S. Kushwaha1, R. Rameshbabu2 1 Bhabha Atomic Research Centre, Mumbai-400085, India, India Seismic response evaluation of safety related nuclear structure with yielding Dampers using Linearization Techniques.

TS 5-5.2 (1656)

1) Dietrich Klein, Fritz-Otto 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 5-5.3 (1683)

Pierre Labbé IAEA / EDF, France Title: Safety Significance of a Type of Seismic Input Motions and Consequences on Nuclear Industry Practice sub-title:Results of the IAEA Coordinated Research Project on the Safety Significance of Near-Field Earthquakes

TS 5-5.4a (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 Spectra-Compatible Time Histories for the ACR NPP in Eastern North America

TS 5-5.4b (2472)

N. Alloety, A. Saudy, and M. Elgohary Atomic Energy of Canada Limited (AECL), Mississauga, Ontario, Canada, Canada Soil-Structure Analysis for ACR Nuclear Island

TS 5-5.5 (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 5-5.6 (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

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Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 14(21) Technical Session 5-5b Seismic Response & Design - Analysis & Design TS 5-5.7 (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 and Verification for Lattice Model

1

TS 5-5.8 (1838)

Shigeru Furukawa1, Michiya Kuno1, Ryuu Shimamoto1 Minoru Kanechika2, Kazuhiro Kusama2, 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 and Ultimate 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 the Oversight of Olkiluoto 3

TS 5-5.10 (1947)

Short, Steve, Orhan Gurbuz, Mike Salmon SGH, Bechtel Corp., LANL, United States Update of ASCE Standard “Seismic Analysis of Safety-Related Nuclear Structures and Commentary”

TS 5-5.11 (1974)

Jukka Kähkönen, Pentti Varpasuo Fortum Nuclear Services Ltd, Finland Seismic FEM Analysis of Reinforced Concrete Structure in SMART-2008 Project

Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 15(21) Technical Session 5-5c Seismic Response & Design - Analysis & Design TS 5-5.12 (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 Power Plants

TS 5-5.13 (1908)

Jaegyun Park1, Chul-Hun Chung1, Jang Seok Yi 2, Byung-Moo Jin3 1 Dankook University, Korea, South 2 Hyundai Institute of Construction Technology Development, , Korea, South 3 Daewoo Engineering & Construction, , Korea, South Dynamic Analysis of a Concrete Shear-Wall

TS 5-5.14 (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, Center of Saclay, France, 3) Doctor, Research Center of CEFR, China Institute of Atomic Energy, Beijing, China The FSI Seismic Analysis for FBR Core Assemblies

TS 5-5.15 (2074)

Shodo AKITA1, Takuya SUZUKI2, Naohiro NAKAMURA2, Masao KOBA 1, Tomio NAKANO3 1 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 and fragility evaluation using 3 dimensional FEM Part-1 Ultimate seismic condition of building

TS 5-5.16 (2075)

Takuya SUZUKI1, Shodo AKITA 2, Naohiro NAKAMURA1, Masao KOBA 2, Tomio NAKANO3 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 and fragility evaluation using 3 dimensional FEM Part-2 Fragility evaluation

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Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 16(21) Technical Session 5-5d Seismic Response & Design - Analysis & Design TS 5-5.17 (2542)

Akinori TOMODA, Tetsuya WATANABE and Kihachiro TANAKA Division of Mechanical Engineering and Science, Saitama University, Japan Seismic Response of a Two-degree-of-freedom System with Friction Based on the Mass Ratio

TS 5-5.18 (2615)

Warren Price National Nuclear Laboratory, England, United Kingdom Seismic Assessment of the Sellafield B38 Mobile Caves

TS 5-5.19 (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 Seismic Events

TS 5-5.20 (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 5-5.21 (1830)

Masahiko NAKAMURA , Fumio SASAKI , Mitsuru MINE, Kazuki YOKOYAMA,Tetsuo TAMAOKI , Akira TANABE , Wataru MIZUMACHI and Michio YAMADA Tokyo University of Science, Japan Study on Non-Stationarity of Frequency by Synthesis Method of Earthquake Motions

Technical Session 5-5e Seismic Response & Design - Analysis & Design TS 5-5.22 (1689) note

1

TS 5-5.23 (1832) note

1

TS 5-5.24 (1810) note

1

1

Suchibrata Dalal, Dr. Mahua Chakrabarti Veermata Jijabai Technolical Institute, Matunga, Mumbai , India, Analysis of Behaviour of Raft Foundations under Seismic and Impulsive Loading P. Vasilyev CKTI-Vibroseism, Saint Petersburg, Russia Generation of an Artificial Time History Matching Multiple-Damping Floor Design Response Spectra Leonid Lakishev 1 , Alexander Schukin 2, Maxim Vayndrakh 2 1

“CKTI-VIBROSEISM” Co. Ltd, Russia Seismic Analysis of WWER–1000 Control Rod Drive System

Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 17(21) Technical Session 5-6a Seismic Response & Design - Component & System TS 5-6.1 (1594)

Xian-Xing (Lambert) Li SNC-Lavalin Nuclear Inc., Canada Earthquake-Induced Sloshing Effects on Seismic Qualification of Liquid Storage Tanks

TS 5-6.2 (1790)

LE BRETON Francis, PETESCH Cécile (paper presented by Phlippe MONETTE) AREVA, PARIS LA DEFENSE, FRANCE, France Stress Analysis Criteria for Piping. RCC-M 2002 Rules and Validation.

TS 5-6.3 (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 on Stochastic Subspace Identification

TS 5-6.4 (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 of Units 5 and 6, Kozloduy NPP

TS 5-6.5 (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 5-6b Seismic Response & Design - Component & System TS 5-6.6 (2000)

P.Chellapandi, S.C.Chetal and Baldev Raj Indira Gandhi Centre for Atomic Research, Kalpakkam-603 102, India, India SEISMIC ANALYSIS OF PRIMARY SODIUM SYSTEM COMPONENTS FOR THE LOOP TYPE FAST BREEDER REACTOR

TS 5-6.7 (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 5-6.8 (1653)

Andrey V. Petrenko AtomEnergoProject, 2nd Sovetskaya str, 9/2A, St-Petersburg, 191036, Russia, e-mail: [email protected], Russia An optimal solution search under design for a pipeline support system to withstand a seismic excitation

1

Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 18(21) TS 5-6.9 (2089)

Mansour Tabatabaie and Basilio Sumodobila SC Solutions, Inc., United States Component Mode Synthesis Based SSI Analysis of Complex Structural Systems using SASSI

TS 5-6.10 (1635)

Viorel Serban, Marian Androne

note

1

Subsidiary of Technology and Engineering for Nuclear Projects (SITON), Romania Sistematic errors in the numeric analyses of computer programs used for the determination of the flexible structure seismic response

TS 5-6.11 (2588) note

1

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 5-7a Seismic Response & Design - Seismic Structural Integrity (SSI) TS 5-7.1 (1592)

Alexander Tyapin Atomenergoproject (Moscow), Russia FREQUENCY-DEPENDENT IMPEDANCES IN THE TIME-DOMAIN SSI ANALYSIS: MODIFICATION OF SEISMIC INPUT

TS 5-7.2 (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 Interaction Effects and Comparison with Two Additional Sites

TS 5-7.3 (1740)

Farhang Ostadan, Traek Elkhorabi Bechtel, United States Amplification of seismic motion at deep soil sites

TS 5-7.4 (1853)

1

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 Significant Mass Eccentricities and Different Embedment Levels

Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 19(21) Technical Session 5-7b Seismic Response & Design - Seismic Structural Integrity (SSI) TS 5-7.5 (1874)

Sang-Hoon Lee, Joo-Hyung Kang Korea Power Engineering Company, Inc., Korea, South Seismic Response Impact of Incoherent SSI Analysis by New Hard-Rock Coherency Model

TS 5-7.6 (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 Island Structures

TS 5-7.7 (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, Minato-ku, Tokyo, Japan Simulation Analysis of Reactor Buildings on Niigataken Chuetsu-oki Earthquake at Kashiwazaki-Kariwa Nuclear Power Plant

TS 5-7.8 (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, Minato-ku, Tokyo, Japan Response and Seismic Margin of Kashiwazaki Kariwa Nuclear Power Plant Building during Chuetsu-oki Earthquake

1

Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 20(21) Technical Session 5-7c Seismic Response & Design - Seismic Structural Integrity (SSI) TS 5-7.9 (1749) note

1

TS 5-7.10 (1665) note

1

TS 5-7.11 (1611) note

1

Ragunath Sankaranarayanan+ and Oliver Schneider* +AREVA NP Inc, NEEC-A, 7207 IBM Drive, Charlotte, NC, USA. E-mail: [email protected]; *AREVA NP GmbH, NEEC-G, Kaiserleistrasse 29, 63067 Offenbach am Main, Germany. E-mail: [email protected];, United States Conservatism in the use of stick models in dynamic SSI analysis Aleksandar Paskalov, Dan M. Ghiocel & Gary Styger Murray & Roberts SNC-Lavalin Nuclear (Pty) Ltd. (EPCM contractor to Pebble Bed Modular Reactor (Pty) Ltd on the PBMR DPP Project), Pebble House, 1279 Mike Crawford Avenue, Centurion 0046, South Africa, email: [email protected] Ghiocel Predictive Technologies Inc., 38 Harper Drive, Pittsford, New York 14534, USA, email: [email protected], South Africa SSI Analysis of PBMR module building to South African high frequency input motions Yun-Suk CHUNG1 & Isam SHAHROUR2 Korea Institute of Nuclear Safety & University of Sciences and Technologies of Lille, Korea, South Inertial Interaction Analysis in Soil-Piles-Structure System

Technical Session 5-8a Miscellaneous TS 5-8.1 (2004)

Bhuwan Chandra Sati, S. Jalaldeen, Sanjeev Kumar, S.Raghupathy, P. Chellapandi and S.C.Chetal Indira Gandhi Centre for Atomic Research, Kalpakkam, India, India INELASTIC STRAIN AT SLIDING JOINT BETWEEN PRIMARY RAMP AND PRIMARY TILTING MECHANISM OF PROTOTYPE FAST BREEDER REACTOR

TS 5-8.2 (1696)

Pentti Varpasuo, Jukka Kähkönen Fortum Nuclear Services Ltd, Finland FORTUM PARTICIPATION IN BARCOM ROUND ROBIN PRE-TEST SIMULATION: MIDTERM ANALYSIS

TS 5-8.3 (1701)

Pentti Varpasuo Fortum Nuclear Services Ltd,, Finland FORTUM PARTICIPATION IN IAEA EBP BENCHMARK FOR KASHIVAZAKI-KARIWA NPP UNIT 7 RESPONSE IN JULY 2007 EVENT

TS 5-8.4 (1721)

Andrew J. Murphy1, Andrei Blahoianu2, and Alejandro Huerta3 1) U.S. Nuclear Regulatory Commission, Washington, DC, USA ([email protected]), United States Activities of OECD/NEA in the Fields of Seismic Hazard Assessment & Earthquake Engineering Activities of OECD/NEA in the Fields of Seismic Hazard Assessment & Earthquake Engineering

TS 5-8.5 (1807) 1

Anton Andonov, Dimitar Stefanov, Marin Kostov Risk Engineering LTD., Bulgaria

Presentation (speaker) not confirmed before printing of the programme

Division 5 - Modeling, Testing and Response Analysis of Structures, Systems and Components 21(21) Performance Based Capacity Assessment of WWER-1000 Containment Structure for Internal Accidents

Technical Session 5-8b Miscellaneous TS 5-8.6 (1839)

Akihiro Kondo, Yasuo Takenaka, Eiji Takaoka, Makiko Hikita, Yo Hyodo, Haruyuki. Kitamura Kajima Corporation, Japan Heat-Mechanics Interaction Behavior of Lead Rubber Bearings for Seismic Base Isolation under Large and Cyclic Lateral Deformation Part 1: Dynamic Loading Test of LRB and Development of Analytical Method

TS 5-8.7 (1840)

Nobuhisa Sato,Shigeru Furukawa, Michiya Kuno, Ryu Shimamoto,Yasuo Takenaka, Takashi Nakayama, Akihiro Kondo Kajima Corporation, Japan Heat-mechanics Interaction Behavior of Lead Rubber Bearings for Seismic Base Isolation under Large and Cyclic Lateral Deformation Part 2: Seismic Response Analysis of Base Isolated Reactor Building subjected to Horizontal Bi-Directional Earthquake Motion

TS 5-8.8 (1877)

P.N. Dubey, G.R. Reddy, K. K. Vaze, A.K. Ghosh, H.S. Kushwaha Bhabha Atomic Research Centre, India PERFORMANCE OF X-PLATE ELASTO-PLASTIC DAMPERS, A PASSIVE SEISMIC SUPPORTS FOR NUCLEAR PIPING UNDER CYCLIC LOADING

TS 5-8.9 (1963)

Igor Simonovski, Boštjan Kon& 269;ar, Leon Cizelj Jožef Stefan Institute, Reactor engineering division, Jamova cesta 39, SI-1000 Ljubljana, Slovenia, Slovenia Thermo-mechanical analysis of a helium cooled divertor of a fusion reactor

TS 5-8.10 (1829)

Alexander V. Kultsep Alexey M. Berkovsky

note

1

1

CKTI-Vibroseism Ltd., Russia Seismic Margin Assessment of Demineralized water reserve tank

Presentation (speaker) not confirmed before printing of the programme