18th International Conference on 
Structural Mechanics in Reactor Technology


 

DIVISION F: DESIGN METHODS AND RULES FOR COMPONENTS

 

Constitutive Modeling and Ratcheting of Materials I

F01-1Identification of Constitutive Laws by Inverse Method Based on EBSD, Microextensometry and Finite Elements Simulations. Application to Zirconium Grade 702
Marie Dexet, Jérôme Crepin, Lionel Gelebart, André Zaoui
F01-2Experiment Research on Ratcheting of Pressurized Pipe Subjected Reversed Bending
Bingjun Gao, Xu Chen, Gang Chen
F01-3Multiaxial Ratcheting of 1Cr18Ni9Ti Stainless Steel
Xu Chen, Xin Li, Rong Jiao
F01-4A Unified Time Dependent Model for Low Cycle Fatigue and Ratcheting Failure Based on Microcrack Growth
Xianjie Yang
F01-5Uniaxial Ratcheting of SS316L Stainless Steel at High Temperature: Experiments and Simulations
Guozheng Kang, Qing Gao
F01-8Neutron Irradiation Embrittlement Modeling in RPV Steels - an Overview
M.F. Hashmi, S.J. Wu, H.X. Li
F01-9Application of a Unified Fatigue Modelling to Some Thermomechanical Fatigue Problems
K. Dang Van, H. Maitournam, Z. Moumni

Constitutive Modeling and Ratcheting of Materials II

F02-1Elastic Core Concept in Shakedown Analysis
Janek Porowski, Tom O'Donnell
F02-2Application of Nano-Indentation Technique to Evaluate Mechanical Properties of Irradiated Materials
Y. S. Choo, Kee Nam Choo, D.S. Kim, B.G. Kim, Y. Choi
F02-3Statues of the Study on the Irradiated Materials by a Special Capsule in HANARO
Young-Hwan Kang, Bong-Goo Kim, Man-Soon Cho, Yong Choi
F02-5Design Criteria for Ratcheting Fatigue of 316FR Steel under Fast Reactor Conditions
Nobuhiro Isobe, Masayuki Sukekawa, Yasunari Nakayama, Tomomi Ohtani, Shingo Date, Yukio Takahashi, Naoto Kasahara, Kyotada Nakamura, Hiroshi Shibamoto, Hideaki Nagashima, Kazuhiko Inoue
F02-6Comparisons of Ratchetting Analysis Methods Using RCC-M, RCC-MR and ASME Codes
Yu Yang, M.T. Cabrillat
F02-7Microstructure Development and Corrosion Behavior of Copper-Silver Nano-Filamentary Composites
Yong Choi, M.Y. Choi, J.H. Song, S.H. Shin

Fatigue and Creep Interaction of Materials

F03-1Experimental Verification of Different Parameters Influencing the Fatigue S/N-Curve
Eberhard Roos, Karl Maile, Karl-Heinz Herter, Xaver Schuler
F03-2A Probabilistic Assessment on the Random S-N Relations and the ASME Design S-N Curves of 0Cr18Ni10Ti Piping Steel
Yongxiang Zhao, Bing Yang
F03-3The Entire Mean Stress Relaxation of 0Cr18Ni10Ti Piping Steel
Bing Yang, Yongxiang Zhao
F03-5On the Creep Crack Growth Behaviour of Inconel 718
Antonietta Lo Conte
F03-6Mechanical Aspects Concerning Thermal Fatigue Initiation in the Mixing Zones of Piping
J.M. Stephan, F. Curtit

International Codes and Standards I

F04-1Design Principles and Overall Aspects to Proof the Integrity of Pressurized Components
Eberhard Roos, Karl-Heinz Herter, Xaver Schuler
F04-2Recent Developments for Fast Reactor Structural Design Standard (FDS)
Naoto Kasahara, Kyotada Nakamura, Masaki Morishita, Hiroshi Shibamoto, Hideaki Nagashima, Kazuhiko Inoue
F04-3EPR Codes and Standards for Pressure Equipments
Claude Faidy
F04-4Advances in the R5 and R6 Defect Assessment Procedures
Robert Anthony Ainsworth
F04-6J Simplified Assessment for Cracked Pipes and Elbows in the RSE-M Code
Patrick LE Delliou, Jean-Philippe Sermage, Philippe Gilles, Stéphane Marie, Yann Kayser, Bruno Barthelet
F04-7Formation of Stress/Strain Cycles for Analytical Assessment of Fatigue Crack Initiation and Growth
Alexander V. Tashkinov

International Codes and Standards II

F05-2Comparison of "VERLIFE" and Russian Methodologies for Reactor Pressure Vessel Integrity Assessment
Vladislav Pistora, Ales Kacor
F05-3Proper Understanding of Relevant Articles in RCC-M and Pane G-7-002
Zaozhan Sun
F05-5A View on the Ways Design of Reliability Criteria in Structural Mechanics
Miroslav Kopecky
F05-6Review of Stress Analysis Results According to Decoupling Criteria Change and Suggestion of Alternative Solution
Joong-Kyo Shin, Kyoung-Mo Yang

Design of Piping, Vessels, and Components I

F06-1Equivalent Properties for Perforated Plates - An Analytical Approach
M. M. Cepkauskas, Jianfeng Yang
F06-2Design of the Filter Pressure Vessel of HTR-10 Safety Valve Testing Loop
Jianling Dong, Junjie Liu, Shuyan He, Suyuan Yu
F06-3Strength Compliance of Pipe Fittings with Large Ovality
Gabor Kovacs, Zoltan Zsidi, Zoltan Vigh, Eleonora Pek
F06-4Interactive Thresholding in the Topology Optimization Process
Ryszard Kutylowski
F06-5Computer Simulation of Drop Test on Lead Shielded Shipping Cask and its Validation
U.P. Singh, S.M. Ingole, A.G. Chhatre, S. Vedamoorthy, R.S. Mahajan, S. Raju
F06-7Numerical Simulation of Residual Stress in Piping Components at FRAMATOME-ANP
Philippe Gilles, Christian Franco, Marie-France Cipière, Pascal Ould
F06-9Design and Suspension Experiments of the Full-Size Active Magnetic Bearing Test Rig for the HTR-10GT
Qiyue Lu, Lei Shi, Lei Zhao, Suyuan Yu
F06-10Application of DSP in Active Magnetic Bearing (AMB-F) Control for the HTR-10GT
Huan Yu, Lei Shi, Suyuan Yu

Design of Piping, Vessels, and Components II

F07-1Thermo-Mechanical Design of a Photoneutron Source for Time-of-Flight Experiments
Eberhard Altstadt, Carsten Beckert, Vladimir Galindo, Baerbel Naumann, Frank-Peter Weiss
F07-2Development of Computational Methods of Design by Analysis for Pressure Vessel Components
Shiyi Bao, Yu Zhou, Shuyan He, Honglin Wu
F07-3A Simplified Technique for Shakedown Load Determination
Hany F. Abdalla, Maher Y. A. Younan, Mohammed M. Megahed
F07-4Application of FEM Analysis Methods to a Cylinder-Cylinder Intersection Structure
Liping Xue, G.E.O. Widera, Zhifu Sang

Design of Piping, Vessels, and Components III

F08-1Design Rules for the O Ring Seal in Nuclear Reactors
Xuanyu Sheng, Suyuan Yu, Dan Zhou, Honglin Wu
F08-2Limit Load Analysis of Bolted Flange Connections
Jürgen Deininger, Robert Kauer
F08-3Design on the Recuperator Used in Power Conversion Unit with the Direct Helium-Turbine Cycle of HTR-10
Xinxin Wu, Qingliao Yin, Jisheng Wang
F08-4High-Temperature Strength and Inelastic Behavior of Plate-Fin Structure for HTGR
Fumiko Kawashima, Toshihide Igari, Yasuyuki Miyoshi, Masanori Tanihira
F08-5A Discussion of Application Possibility of LBB Methodology for PWR High Energy Piping Lines other than Main Coolant Pipe inside Containment
Bingbing Liang, Wendao Gao
F08-6Design Verification for Reactor Head Replacement
Keshab K. Dwivedy, Melvin S. Whitt, Robert Lee

 

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