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Proceedings Papers

Proceedings Volume Cover
18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
  • Nuclear Engineering Division
ISBN:
978-0-7918-4933-0
In This Volume
18th International Conference on Nuclear Engineering: Volume 5

Component Reliability and Materials Issues

Ageing Assessment, Condition Inspection and Lifetime Evaluation for Safety Related Fuse in Nuclear Power Plant
Jie Shi, Xinming Jin, Zhiming Liu, Haining Shi, Jianlin Yao, Fengsheng Tu
ICONE 2010; 1-5https://doi.org/10.1115/ICONE18-29013
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Topics: Inspection , Nuclear power stations , Safety , Temperature , Electrodiffusion , Imaging , Metals , Testing
Fluid-Elastic Instability of Normal Square Tube Bundles in Two-Phase Cross Flow
Woo Gun Sim, Mi Yeon Park
ICONE 2010; 7-14https://doi.org/10.1115/ICONE18-29037
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Topics: Cross-flow , Fluids , Cylinders , Damping , Flow (Dynamics) , Heat exchangers , Boilers , Design , Excitation , Flow-induced vibrations
Iconic Representation Extension of Event Sequence Diagram Framework for Nuclear Power Plant
Haiyan Xie, Qi Cai, Yangwei Zhang
ICONE 2010; 15-21https://doi.org/10.1115/ICONE18-29067
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Topics: Nuclear power stations , Reliability
Study of the Corrosion Behavior of Zr-xFe-yCr Alloys in 500°C/10.3MPa Steam
Jun Wang, Shihao Ying, Zhi Miao, Hongyuan Fan
ICONE 2010; 23-26https://doi.org/10.1115/ICONE18-29076
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Topics: Alloys , Corrosion , Steam , Zirconium , Corrosion resistance , Hydrogen , Zirconium alloys , Instrumentation
Corrosion Resistance of Mo-Fe-Ti Alloy for Overpack in Simulating Underground Environment
Toshiyasu Nishimura
ICONE 2010; 27-32https://doi.org/10.1115/ICONE18-29107
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Topics: Alloys , Corrosion resistance , Electrochemical impedance spectroscopy , Transmission electron microscopy , Heat , Heat treating (Metalworking) , Corrosion , Electron field emission , Grain boundaries , Lasers
Preliminary Discussion on Comparison and Analysis on Nuclear Power Plant Materials Standards of ASME and RCC-M
Dong Ning, Yongdong Wang, Hui Li, Zhanggen Bao
ICONE 2010; 33-42https://doi.org/10.1115/ICONE18-29120
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Topics: Corrosion , Fracture toughness , Nuclear power stations , Ferrites (Magnetic materials) , ASME Standards , Fracture (Materials) , Pressure , Stainless steel
Evaluation of Thermal Aging Embrittlement in Main Coolant Pipe Steel by Small Punch Test
Fei Xue, Weiwei Yu, Xiao Chen, Yan Liu, Zhenhao Shi, Guogang Shu, Xitao Wang
ICONE 2010; 43-46https://doi.org/10.1115/ICONE18-29128
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Topics: Coolants , Embrittlement , Pipes , Steel , Fracture (Materials) , Fracture (Process) , Heat treating (Metalworking) , Nuclear power stations , Stainless steel , Temperature
Experimental Investigation of Copper/Stainless Steel Joints Formed by Vacuum Brazing
Changqing Ye
ICONE 2010; 47-55https://doi.org/10.1115/ICONE18-29132
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Topics: Brazing , Copper , Stainless steel , Vacuum
Material Surveillance Program Regulatory Guidance for Steam Generator Tubes Extracted From Canadian CANDU Reactors
Sue Liu, Blair Carroll, Jovica Riznic, Nicholas Christodoulou, Raoul Awad
ICONE 2010; 57-64https://doi.org/10.1115/ICONE18-29149
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Topics: Boilers , Surveillance , Inspection , Nondestructive evaluation , Safety , Uncertainty
Equilibrium Partition Coefficients of Cesium and Iodine Between Sodium Pool and the Inert Cover Gas
Shinya Miyahara, Masahiro Nishimura, Toshio Nakagiri
ICONE 2010; 65-70https://doi.org/10.1115/ICONE18-29169
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Topics: Equilibrium (Physics) , Nuclear fission , Sodium
Prediction of Radioactive Corrosion Product Transfer in Primary Systems of Japanese Prototype Fast Breeder Reactor MONJU
Youichirou Matuo, Masanori Hasegawa, Yoshiharu Maegawa, Shinya Miyahara
ICONE 2010; 71-78https://doi.org/10.1115/ICONE18-29171
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Topics: Breeder reactors , Corrosion , Engineering prototypes , Hazards , Sodium
Threshold Stress Intensity Factor for Delayed Hydride Cracking of a Recrystallized N18 Alloy Plate Along the Rolling Direction
Chao Sun, Shi H. Ying, Jun Tan, Qian Peng, Xun Dai
ICONE 2010; 79-85https://doi.org/10.1115/ICONE18-29212
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Topics: Alloys , Cracking (Materials) , Fracture (Process) , Stress , Texture (Materials) , Zirconium
Applicability Study of Computed Radiography to NDE for Piping and Component in Nuclear Power Plant
Takashi Hasebe, Nobuki Tamai, Syohei Tatsuno, Yuma Itahashi, Kiyoaki Tokunou
ICONE 2010; 87-91https://doi.org/10.1115/ICONE18-29215
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Topics: Nondestructive evaluation , Nuclear power stations , Pipes , X-rays , Imaging , Noise (Sound) , Testing , Biomedicine , Filters , Inspection
Irradiation-Embrittlement of Reactor Pressure Vessel Steel
Guoyun Li, Yukun Wu, Guofu Jiang, Juan Huang, Haisheng Zhang
ICONE 2010; 93-96https://doi.org/10.1115/ICONE18-29240
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Topics: Embrittlement , Irradiation (Radiation exposure) , Reactor vessels , Steel , Surveillance
Study of Weld Residual Stress Field in the Girth Seam H6A of Core Shroud of Boiling Water Reactor
Yongkui Li, Yoshiyuki Kaji, Takahiro Igarashi
ICONE 2010; 97-102https://doi.org/10.1115/ICONE18-29269
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Topics: Boiling water reactors , Stress , Irradiation (Radiation exposure) , Stress corrosion cracking , Neutrons , Temperature , Accidents , Carbon , Corrosion , Cycles
The Improvement Research of Accident Generation Mechanism of Dynamic Event Tree
Yongfa Zhang, Jiejuan Tong, Yu Zhou
ICONE 2010; 103-111https://doi.org/10.1115/ICONE18-29270
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Topics: Accidents , Reliability
Corrosion Test of 304 Stainless Steel in Hydrazine and Methanol Solutions at 320°C Under Gamma-Irradiation and Gamma Radiolysis of Hydrazine and Methanol
Masafumi Domae, Hirotaka Kawamura, Daisuke Akutagawa, Kenji Hisamune, Yosuke Katsumura, Yusa Muroya
ICONE 2010; 113-121https://doi.org/10.1115/ICONE18-29281
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Topics: Corrosion , Irradiation (Radiation exposure) , Methanol , Stainless steel , Hydrogen , Water , Carbon dioxide , Electrolytic corrosion , Oxidation , Pressurized water reactors
Synergistic Effect of Neutron and Gamma Irradiation on CMOS Integrated Circuits
Yan Liu, Xiaoming Jin, Wei Chen, Dongsheng Lin, Shanchao Yang
ICONE 2010; 123-127https://doi.org/10.1115/ICONE18-29291
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Topics: Complementary metal oxide semiconductors , Irradiation (Radiation exposure) , Neutrons , Gamma rays , Damage , Displacement , Radiation (Physics) , Radiation effects
Multiphysics Modeling and Simulation for Stress Corrosion Cracking Considering Oxygen Atom Diffusion Along Grain Boundary
Takahiro Igarashi, Yoshiteru Aoyagi, Yoshiyuki Kaji
ICONE 2010; 129-133https://doi.org/10.1115/ICONE18-29337
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Topics: Atoms , Diffusion (Physics) , Grain boundaries , Modeling , Oxygen , Simulation , Stress corrosion cracking , Fracture (Materials) , Crack propagation , Stress
The Effect of Fabrication Process on Microstructure Evolution of N18 Alloy Sheets
Xun Dai, Hong Liu, Hongman Jiang, Ying Wang
ICONE 2010; 135-140https://doi.org/10.1115/ICONE18-29339
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Topics: Alloys , Manufacturing , Hot rolling , Recrystallization , Texture (Materials) , Cold rolling , Deformation , Density , Annealing , Electron backscatter diffraction
Thermal Aging Effect of CDSS on the Integrity of the PWR Primary Pipe With Damage Tolerance Method
Zhao-Xi Wang, Fei Xue, Hui-Ji Shi, Wei-wei Yu, Guo-gang Shu
ICONE 2010; 141-145https://doi.org/10.1115/ICONE18-29364
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Topics: Damage , Pipes , Pressurized water reactors , Fracture toughness , Pressure , Stress analysis (Engineering) , Damage mechanics , High temperature , Life extension , Materials properties
Stress Corrosion Cracking Incidents and Repair Technologies on PWR Dissimilar Weld Metal Joints in Japan
Naoki Chigusa, Shinro Hirano, Takehiko Sera, Hitoshi Kaguchi, Masayuki Mukai, Yusuke Yoshida
ICONE 2010; 147-156https://doi.org/10.1115/ICONE18-29390
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Topics: Maintenance , Metals , Pressurized water reactors , Reactor vessels , Stress corrosion cracking
The Reliability Analysis of Bearing in Large Blower System
Jun Zhao, QinZhao Zhang, JieJuan Tong, Hong Wang
ICONE 2010; 157-163https://doi.org/10.1115/ICONE18-29391
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Topics: Bearings , Event history analysis , Reliability
Parameters Influencing the Secondary Hydrogenation of Zr-Sn and Zr-Nb Alloys During Steam Oxidation Under LOCA and Severe Accident Conditions
Mirco K. Grosse, Martin Steinbrueck, Juri Stuckert
ICONE 2010; 165-171https://doi.org/10.1115/ICONE18-29405
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Topics: Accidents , Alloys , Oxidation , Steam , Tin , Zirconium , Hydrogen , Cladding systems (Building) , Gas flow , Temperature
Quality Control of Interface Between Tungsten Coating and Cu Alloy Heat Sink of PFC for EAST Tokamak by Infrared Thermography
Pan Qi, Guangnan Luo, Qiang Li, Xiaojun Kuang, Haishan Zhou
ICONE 2010; 173-178https://doi.org/10.1115/ICONE18-29435
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Topics: Coating processes , Coatings , Copper alloys , Heat sinks , Quality control , Thermography , Tokamaks , Tungsten , Nondestructive evaluation , Testing
Study on the Hydrogen Effect on the Temper Embrittlement of 2.25Cr-1Mo Steel
Xiliang Zhang, Changyu Zhou
ICONE 2010; 179-184https://doi.org/10.1115/ICONE18-29503
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Topics: Embrittlement , Hydrogen , Steel , Grain boundaries , Hydrogen embrittlement , Testing , Augers , Electrons
The Mechanical Properties and Friction and Wear Behavior of C/C-SIC
Gao Wen, Chongsheng Long, Tang Rui, Jiping Wang
ICONE 2010; 185-190https://doi.org/10.1115/ICONE18-29705
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Topics: Friction , Mechanical properties , Wear , Composite materials , Carbon , Stress , Silicon , Water , Carbon fibers , Scanning electron microscopy
Chemico-Physical Causes of Radiation-Induced “Long Cell” Action Corrosion in Water Cooled Reactors
Genn Saji
ICONE 2010; 191-206https://doi.org/10.1115/ICONE18-29714
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Topics: Corrosion , Radiation (Physics) , Water , Fittings , Electrochemistry , Electrons , Boiling water reactors , Chemical potential , Chemistry , Cooling systems
Aspects of Minimizing Steel Corrosion in Liquid Lead-Alloys by Addition of Oxygen
Carsten Schroer, Olaf Wedemeyer, Juergen Konys
ICONE 2010; 207-218https://doi.org/10.1115/ICONE18-29726
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Topics: Lead alloys , Oxygen , Steel corrosion , Sensors , Liquid metals , Steel , Testing
Assessment of ODS Ferritic Alloy for Advanced Nuclear Energy System
Zhangjian Zhou, Ming Li, Lu Liao, Pei He, Yingli Xu
ICONE 2010; 219-222https://doi.org/10.1115/ICONE18-29854
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Topics: Alloys , Nuclear power , High temperature , Steel , Oxidation , Temperature , Cladding systems (Building) , Corrosion , Generation IV reactors , Mechanical properties
Development of Electrical Resistivity Measurement Systems for Inspecting Void Swelling in Irradiated Microscopy Discs
Mitsuyuki Sagisaka, Yoshihiro Isobe, Frank Garner, Satoshi Fujita, Taira Okita
ICONE 2010; 223-228https://doi.org/10.1115/ICONE18-29893
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Topics: Disks , Electrical resistivity , Measurement systems , Microscopy , Radiation (Physics) , Alloys , Carbon , Precipitation , Test facilities , Titanium
Corrosion Properties of Welded Ferritic-Martensitic Steels in Liquid Lead-Bismuth at 600C
Asril Pramutadi Andi Mustari, Minoru Takahashi
ICONE 2010; 229-235https://doi.org/10.1115/ICONE18-29927
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Topics: Corrosion , Steel , Base metals , Diffusion (Physics) , Cross section (Physics) , Electric current , Electrical conductance , Electron beam welding , Fracture toughness , Gas tungsten arc welding
Rupture Frequency of CANDU® Large-Diameter Primary Heat Transport Piping Estimated Using Probabilistic Fracture Mechanics Codes
Rob McLean, Xinjian Duan, Michael J. Kozluk
ICONE 2010; 237-246https://doi.org/10.1115/ICONE18-29973
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Topics: Fracture mechanics , Heat , Pipes , Rupture , Leakage , Probability , Welded joints , Manufacturing
Dynamic Analysis of Core Magnetic Circuit of Direct Action Solenoid Valve
Qianfeng Liu, Hanliang Bo, Benke Qin
ICONE 2010; 247-253https://doi.org/10.1115/ICONE18-30045
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Topics: Circuits , Dynamic analysis , Solenoids , Valves , Electromagnetic force , Magnetic fields , Computer software , Hydraulic drive systems , Intellectual property , Magnetic materials
Irradiation Damage and Embrittlement in RPV Steels Under the Aspect of Long Term Operation: Overview of the FP7 Project LONGLIFE
Eberhard Altstadt, Frank Bergner, Hieronymus Hein
ICONE 2010; 255-263https://doi.org/10.1115/ICONE18-30049
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Topics: Damage , Embrittlement , Irradiation (Radiation exposure) , Steel , Neutrons , Surveillance , Fluence (Radiation measurement) , Hardening , Mechanical properties , Neutron diffraction
Effect of Temperature in the Preparation of Zirconium Hydride
Lijun Wang, Li Zhang, Yuanhui Luo, Weidong Chen, Jianwei Wang
ICONE 2010; 265-268https://doi.org/10.1115/ICONE18-30068
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Topics: Temperature , Zirconium , Hydrogen , Phase transitions , Pressure , Cracking (Materials) , Fracture (Process) , Hydrogen storage , Nuclear reactors , Phase diagrams
The Welding Deformations of Stainless Steel Pipes With Thick Wall by Narrow Gap Gas Tungsten Arc Welding
Jainxun Zhang, Chuan Liu, Jing Niu
ICONE 2010; 269-274https://doi.org/10.1115/ICONE18-30088
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Topics: Deformation , Gas tungsten arc welding , Pipes , Stainless steel , Welding , Shrinkage (Materials) , Finite element model , Nuclear power stations , Stiffness , Transients (Dynamics)
Proactive Aging Management: PAM 2.0
Robert K. Perdue, Matthew H. Kelley, Raymond E. O’Rourke, Joel Woodcock, Mengyi Zhang, Hui Zheng
ICONE 2010; 275-281https://doi.org/10.1115/ICONE18-30094
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Topics: China , Computer software , Condition monitoring , Engineers , Maintenance , Nuclear power stations , Reliability , Safety , Teaching
Effect of Hazardous Impurities on Steam Generator Tube Degradation
Yucheng Lu
ICONE 2010; 283-291https://doi.org/10.1115/ICONE18-30120
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Topics: Boilers , Alloys , Corrosion , Chemistry , Tubing , Copper , Electrolytic corrosion , Materials degradation , Boundary-value problems , Contamination
Irradiation-Induced Embrittlement of INCONEL 600 Flux Detectors in CANDU Reactors
M. Griffiths, G. A. Bickel, S. R. Douglas
ICONE 2010; 293-298https://doi.org/10.1115/ICONE18-30121
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Topics: Embrittlement , Irradiation (Radiation exposure) , Sensors , Temperature , Wire , Failure , Corrosion , Design , Cables , Heat
An Accurate Probabilistic Model for Estimating the Life Cycle Cost of Degrading Components in Nuclear Power Plants
T. Cheng, M. D. Pandey, W. C. Xie
ICONE 2010; 299-308https://doi.org/10.1115/ICONE18-30130
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Topics: Life cycle costing , Nuclear power stations , Maintenance , Optimization , Cycles , Failure , Inspection , Reliability , Risk , Safety
The Prediction of Long-Term and Emergency Sealability of Silicone and EPDM Gaskets
Mitsuyuki Nakano, Haruko Sasaki, Kanji Hanashima
ICONE 2010; 309-316https://doi.org/10.1115/ICONE18-30169
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Topics: Emergencies , EPDM rubber , Gaskets , Silicones , Containment vessels , Silicone rubber , Rubber , Irradiation (Radiation exposure) , Nuclear power stations , Radiation (Physics)
Application of Extra High Purity Austenitic Stainless Steel to Weld Overlay
Ikuo Ioka, Jun Suzuki, Kiyoshi Kiuchi, Jumpei Nakayama
ICONE 2010; 317-322https://doi.org/10.1115/ICONE18-30197
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Topics: Overlays (Materials engineering) , Stainless steel , Alloys , Corrosion , Metals , Fracture (Materials) , Boiling , Corrosion resistance , High temperature , Ions
High Temperature Aging and Corrosion Study on Alloy 617 and Alloy 230
Kun Mo, Gianfranco Lovicu, Hsiao-Ming Tung, Xiang Chen, James F. Stubbins
ICONE 2010; 323-332https://doi.org/10.1115/ICONE18-30207
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Topics: Alloys , Corrosion , High temperature , Very high temperature reactors , Electron backscatter diffraction , Mechanical properties , Construction , Corrosion resistance , Electric power generation , Engineering design
Pressurized Water Reactor Core Crud Mapping
W. A. Byers
ICONE 2010; 333-339https://doi.org/10.1115/ICONE18-30218
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Topics: Boiling , Chemistry , Computers , Coolants , Corrosion , Fuels , Manufacturing , Pressurized water reactors , Radiation (Physics) , Risk
State of the Art NDT Mechanized Equipment Used in PWR Reactor Vessel Inspection
Ming Li, Huaidong Chen, Xuezhu Xiao, Tianming Lv, Zhe Yu
ICONE 2010; 341-346https://doi.org/10.1115/ICONE18-30232
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Topics: Inspection , Pressurized water reactors , Reactor vessels
Bruce Power Aging Obsolescence Program
Ian Cruchley, Rick Dam, Ralf Gold, Brian Ferguson
ICONE 2010; 347-356https://doi.org/10.1115/ICONE18-30249
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Topics: Failure , Heat exchangers , Maintenance , Pipes , Reliability , Resolution (Optics)
Introduction of Hot Isostatically Pressed, Reactor Coolant System Components in PWR Plant
John L. Sulley, Ian Hookham, Barry Burdett, Keith Bridger
ICONE 2010; 357-367https://doi.org/10.1115/ICONE18-30253
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Topics: Bonding , Design , Inspection , Leakage , Manufacturing , Mechanical properties , Mechanical testing , Nuclear reactor coolants , Nuclear reactors , Pressure
Surveillance Specimen Program for Lifetime Extension of RPV
Milan Brumovsky, Milos Kytka
ICONE 2010; 369-374https://doi.org/10.1115/ICONE18-30258
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Topics: Surveillance , Design , Life extension , Nuclear power stations , Reactor vessels , Embrittlement , Irradiation (Radiation exposure) , Temperature , Testing
Steam Generator Ageing Management Database
Junqi Chen, Fei Xue, Peng Liu, Lin Zhou, Lei Lin, Wenxin Ti
ICONE 2010; 375-378https://doi.org/10.1115/ICONE18-30279
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Topics: Boilers , Databases , Nuclear power stations , Reliability , Safety , Data acquisition , Data centers , Engineers , Steam , Stress corrosion cracking
Progress of the Study on Corrosion Behavior of Graphite in HTGRs
Peng Wang, Xinli Yu, Suyuan Yu
ICONE 2010; 379-385https://doi.org/10.1115/ICONE18-30357
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Topics: Corrosion , Graphite , Very high temperature reactors , Water , Accidents , Oxidation , Carbon dioxide , Coolants , Engineering simulation , Mechanical properties
Development of a Large Diameter Electromagnetic Pump for 4S
Rie Aizawa, Seiji Fujiwara, Yasuko Oyamatsu, Kenji Katsuki, Minoru Funato, Hiroyuki Ota
ICONE 2010; 387-392https://doi.org/10.1115/ICONE18-30374
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Topics: Pumps , Sodium , Flow (Dynamics) , Flowmeters , Design , Maintenance , Calibration , Control systems , Engineering prototypes , Flow instability

Structural Integrity

Dynamic Motion of RC Beams and One-Way Slabs Impacted by a Missile at Medium Velocity: Models for Spreadsheet Application
Jean-Mathieu Rambach
ICONE 2010; 393-402https://doi.org/10.1115/ICONE18-29087
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Topics: Missiles , Slabs
Random Seismic Response Analysis of Coupling Structure Interconnected by Hysteretic Dampers
Qian Huang, Fenggang Zang, Yixiong Zhang
ICONE 2010; 403-412https://doi.org/10.1115/ICONE18-29140
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Topics: Dampers , Excitation
Using Microplane Material Model for Concrete in Soft Missile Impact Analysis
Jukka Ka¨hko¨nen, Pentti Varpasuo
ICONE 2010; 413-421https://doi.org/10.1115/ICONE18-29142
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Topics: Concretes , Missiles , Anisotropy , Constitutive equations , Damage , Impact testing , Plasticity
Floor Response Spectra of Loviisa NPP Reactor Buildings
Jukka Ka¨hko¨nen, Pentti Varpasuo
ICONE 2010; 423-428https://doi.org/10.1115/ICONE18-29174
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Topics: Nuclear power stations , Spectra (Spectroscopy) , Structures , Circuits , Concretes , Damping , Elevations (Drawings) , Finite element analysis , Materials properties , Probabilistic risk assessment
Seismic Fragility Study for High-Pressure Emergency Cooling Water Tanks of Loviisa Nuclear Power Plant
Jukka Ka¨hko¨nen, Pentti Varpasuo
ICONE 2010; 429-434https://doi.org/10.1115/ICONE18-29181
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Topics: Cooling , Emergencies , High pressure (Physics) , Nuclear power stations , Water , Probability , Failure , Nozzles , Pipes , Shapes
Fortum Participation in IAEA Benchmark for KKNPP7 RHR Piping Response NCO 2007 Event
Pentti Varpasuo, Jukka Ka¨hko¨nen
ICONE 2010; 435-441https://doi.org/10.1115/ICONE18-29229
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Topics: Pipes , Simulation , Heat , Earthquakes , Buckling , Computer simulation , Piping systems , Sloshing , Databases , Displacement measurement
The Application of Combination of Individual Modal Responses According to the Revised RG1.92
Shenghua Liu, Zufeng Xia
ICONE 2010; 443-448https://doi.org/10.1115/ICONE18-29293
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Topics: Finite element analysis , Nuclear industry , Nuclear power stations , Parametric design , Pipes
Development and Validation of an LS-DYNA Model for Simulating Vertical Drop Test of a Nuclear Fuel Shipping Package
W. Zhao, B. Hempy, J. Liu, W. Stilwell, R. Rochow
ICONE 2010; 449-455https://doi.org/10.1115/ICONE18-29313
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Topics: Nuclear fuels , Design , Finite element model , Fuels , Manufacturing , Accidents , Safety
On-Line Sequestration of Fission Product Gases in Operating Nuclear Reactors
Gary M. Sandquist, Jay F. Kunze
ICONE 2010; 457-462https://doi.org/10.1115/ICONE18-29326
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Topics: Gases , Nuclear fission , Nuclear reactors , Safety
Numerical Evaluation of Fluctuating Pressure at Stub Pipes in Actual BWR Main Steam Lines
Ryo Morita, Shiro Takahashi, Fumio Inada, Yukio Ogawa
ICONE 2010; 463-468https://doi.org/10.1115/ICONE18-29355
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Topics: Boiling water reactors , Pipes , Pressure , Steam , Resonance , Acoustics , Fluctuations (Physics) , Nuclear power stations , Power uprate , Evaluation methods
Fluctuating Pressure Generating in BWR Main Steam Lines Acoustic Excited by Safety Relief Valve Stub Pipes and Dead Legs
Shiro Takahashi, Keita Okuyama, Akinori Tamura, Masaya Ohtsuka, Masaaki Tsubaki, Mabuchi Yasuhiro, Teppei Kubota, Yukio Ogawa, Fumio Inada, Ryo Morita
ICONE 2010; 469-478https://doi.org/10.1115/ICONE18-29361
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Topics: Acoustics , Boiling water reactors , Pipes , Pressure , Relief valves , Safety , Steam , Resonance , Flow (Dynamics) , Finite element methods
Analysis of Thermal Stratification and Fatigue Stress for Pressurizer Surge Line
Xiaofei Yu, Yixiong Zhang
ICONE 2010; 479-486https://doi.org/10.1115/ICONE18-29366
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Topics: Fatigue , Stress , Surges , Thermal stratification
Prediction of Irradiation Embrittlement for Chinese Domestic A508-3 Steel
Feng Lu, Rongshan Wang, Ping Huang, Haiyang Qian
ICONE 2010; 487-491https://doi.org/10.1115/ICONE18-29389
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Topics: Embrittlement , Irradiation (Radiation exposure) , Steel , Nuclear power stations , Safety , Fluence (Radiation measurement) , Fracture toughness , Neutrons , Reactor vessels , Regulations
Three-Dimensional Seismic Analysis on Reactor Structure
Naibin Jiang, Feng-gang Zang, Li-min Zhang, Chuan-yong Zhang
ICONE 2010; 493-498https://doi.org/10.1115/ICONE18-29448
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Topics: Seismic analysis , Computer software , Dynamic analysis , Earthquakes , Excitation , Finite element analysis , Finite element methods , Finite element model , Hardware , Nuclear engineering
Computational Method for Crack-Opening-Area of Nuclear Pressure Pipe With Circumferential Through-Wall Crack
Jun Liu, Bo Yan, Naibin Jiang
ICONE 2010; 499-503https://doi.org/10.1115/ICONE18-29450
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Topics: Computational methods , Fracture (Materials) , Numerical analysis , Pressure pipes
Quantitative Evaluation of Hydrogen Micro-Damage in 316L Austenitic Stainless Steel
J. Toribio, F. J. Ayaso
ICONE 2010; 505-515https://doi.org/10.1115/ICONE18-29462
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Topics: Damage , Hydrogen , Stainless steel , Fracture (Process) , Microscale devices , Embrittlement , Fractography , Geometry , Hydrogen embrittlement , Surface roughness
Development and Demonstration of a New Testing Capability for Simulating Multiple Fuel Assembly Impact During a Seismic Event
W. Zhao, Y. C. Lee, H. Kunishi, Z. Karoutas, A. Doan
ICONE 2010; 517-522https://doi.org/10.1115/ICONE18-29468
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Topics: Earthquakes , Fuels , Manufacturing , Testing , Engineering prototypes , Pendulums , Deformation , Displacement , Mechanical testing , Model development
Creep Stress Analyses Affected by Defect Geometries on P91 Pipe With Local Wall Thinning Under High Temperature
Jilin Xue, Changyu Zhou, Jian Peng
ICONE 2010; 523-528https://doi.org/10.1115/ICONE18-29560
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Topics: Creep , High temperature , Pipes , Stress analysis (Engineering) , Stress , Finite element analysis , Manufacturing , Nuclear power stations , Power stations , Pressure
Experimental and Numerical Simulation of Radiolysis Gas Detonations and Mechanical Response of BWR Exhaust Pipes
M. Kuznetsov, R. Redlinger, W. Breitung, J. Grune, K. Sempert, A. Friedrich
ICONE 2010; 529-537https://doi.org/10.1115/ICONE18-29697
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Topics: Boiling water reactors , Computer simulation , Exhaust systems , Explosions , Steam , Pipes , Pressure , Valves , Condensation , Damage
Sensitivity Analyses of Finite Element Method for Computing Residual Stress of Dissimilar Metal Multi-Pass Weld
YaoLong Tsai, ChaoJen Li, TaiPing Tsai, Li-Hua Wang, TeWei Fan, ChangPin Chou
ICONE 2010; 539-547https://doi.org/10.1115/ICONE18-29720
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Topics: Finite element methods , Metals , Sensitivity analysis , Stress , Computation , Computer software , Finite element analysis , Finite element model , Fracture (Materials) , Nozzles
Dynamic Analysis of Including New Loads on Spent Fuel Storage Rack
YaoLong Tsai, TaiPing Tsai, ChaoJen Li, Li-Hua Wang, TeWei Fan, ChangPin Chou
ICONE 2010; 549-552https://doi.org/10.1115/ICONE18-29721
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Topics: Dynamic analysis , Spent fuel storage , Stress , Safety , Accidents , Coolants , Degrees of freedom , Fuels , Regulations , Relief valves
Studies on the Correlation Between Natural Magnetization and Mechanical Damages of an Austenitic Stainless Steel
Hongmei Li, Zhenmao Chen, Tianfei Zhao
ICONE 2010; 553-557https://doi.org/10.1115/ICONE18-29770
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Topics: Damage , Magnetization , Stainless steel , Magnetic fields , Nuclear power stations , Fracture (Materials) , Cycles , Metal magnetic memory testing , Nondestructive evaluation , Safety
Effect of Hydrogen Isotope and Concentration on Delayed Hydride Crack Growth Rates in Zr-2.5Nb Pressure Tubes
Gordon K. Shek, Harry Seahra
ICONE 2010; 559-569https://doi.org/10.1115/ICONE18-29786
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Topics: Fracture (Materials) , Hydrogen , Isotopes , Pressure , Zirconium , Temperature , Fracture (Process) , Cracking (Materials) , Diffusion (Physics) , Leakage
Development of Leak Rate Model for Helium Flow in Elliptically Converging Through Wall Crack
Sheng Zhou, Zhengming Zhang, Pierre Lamagnere, Thierry Cadiou, Jean-luc Berton, Marc Grandotto-Biettoli
ICONE 2010; 571-576https://doi.org/10.1115/ICONE18-29814
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Topics: Flow (Dynamics) , Fracture (Materials) , Helium , Leakage , Computational fluid dynamics , Geometry , Pressure , Very high temperature reactors , Leak-before-break , Nuclear power stations
Signal Processing Schemes for Defect Identification and Sizing From Signal of Eddy Current Testing in Nuclear Power Plant
Shuxia Tian, Zhenmao Chen, Dongli Zhang, Qiang Geng
ICONE 2010; 577-584https://doi.org/10.1115/ICONE18-29825
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Topics: Eddy current testing , Nuclear power stations , Signal processing , Signals , Noise (Sound) , Artificial neural networks , Boilers , Design , In-service inspection , Plates (structures)
PCI Risk Assessment Model
Dmitry Paramonov
ICONE 2010; 585-591https://doi.org/10.1115/ICONE18-29838
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Topics: Cladding systems (Building) , Failure , Fuels , Monitoring systems , Pressure , Pressurized water reactors , Probability , Risk , Risk assessment , Temperature
Time Dependent Leak Rate Change in SCC Degraded SG Tubes of PWRs
Seong S. Hwang, Jangyul Park, Man K. Jung, Hong P. Kim
ICONE 2010; 593-596https://doi.org/10.1115/ICONE18-29872
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Topics: Leakage , Pressurized water reactors , Fracture (Materials) , Pressure , Alloys , Stress corrosion cracking , Water , Boilers , Corrosion , Maintenance
The Effect of Load Reduction on Crack Initiation Behavior of Hydrides From Flaws in Zr-2.5Nb Pressure Tube Material
Jun Cui, Gordon K. Shek
ICONE 2010; 597-606https://doi.org/10.1115/ICONE18-29880
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Topics: Fracture (Materials) , Pressure , Stress , Zirconium , Fracture (Process) , Hydrogen , Alloys , Diffusion (Physics) , Finite element analysis , Nuclear reactors
Dynamic Response of a Nuclear Power Plant Subjected to External Accident Event
Rosa Lo Frano, Giuseppe Forasassi
ICONE 2010; 607-615https://doi.org/10.1115/ICONE18-29896
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Topics: Accidents , Dynamic response , Nuclear power stations , Design , Containment , Safety , Aircraft , Containment systems , Finite element methods , Finite element model
Investigations on Optimal Design of a U-Tube Steam Generator
Hui-min Qin, Chang-qi Yan, Meng Wang, Shi-jing He
ICONE 2010; 617-624https://doi.org/10.1115/ICONE18-29930
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Topics: Boilers , Design
Thermal Ageing Embrittlement of Casting Duplex Stainless Steels for Nuclear Power Plant
Yuhong Yao, Jianfeng Wei, Jiangnan Liu, Zhengpin Wang, Yu Wang
ICONE 2010; 625-630https://doi.org/10.1115/ICONE18-29982
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Topics: Casting , Embrittlement , Nuclear power stations , Stainless steel
Three-Dimensional Earthquake Responses of Nuclear Containment Building Installed in Water-Saturated Soil Strata
Jin Ho Lee, Jae Kwan Kim, Jeong-Soo Ryu
ICONE 2010; 631-638https://doi.org/10.1115/ICONE18-30028
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Topics: Containment buildings , Earthquakes , Soil , Water , Finite element analysis , Porous materials , Computer simulation , Elastic waves , Modeling , Overlays (Materials engineering)
Reactor Coolant System Branch Line Pipe Break Analysis for Shin-Kori Units 3 and 4
Young Jin Byun, Young Sil Sul, Kwang Won Lee, Jong Tae Seo
ICONE 2010; 639-645https://doi.org/10.1115/ICONE18-30066
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Topics: Nuclear reactor coolants , Pipes , Steam , Feedwater , Nozzles , Boilers , Construction , Dynamic response , Excitation , Mechanical properties
Residual Life Prediction of Corroded Pipeline Based on Electrochemical Model
Wen-he Wang, Jun Yi, Ai-xia Ma, Shi-ming Shen, Xiao-chun Yu
ICONE 2010; 647-651https://doi.org/10.1115/ICONE18-30101
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Topics: Pipelines , Corrosion , Electrolytic corrosion , Failure
Stratified Flows in Pipes: A Parametric Study Towards Fatigue Relevance
Leon Cizelj, Igor Simonovski
ICONE 2010; 653-659https://doi.org/10.1115/ICONE18-30122
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Topics: Fatigue , Pipes , Stratified flow , Hot water , Stress , ASME Boiler and Pressure Vessel Code , Design , Finite element analysis , Fluids , Heat transfer
A Stochastic Approach to Nonlinear Seismic Design Spectra
Malek Brahimi
ICONE 2010; 661-670https://doi.org/10.1115/ICONE18-30146
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Topics: Earthquake resistant design , Spectra (Spectroscopy) , Earthquakes , Stiffness , Damping , Design , Yield strength , Degrees of freedom
Experiences From Structural Dynamic Analysis Projects of BWR Plants Within the Scope of Power Uprate Projects Using FEA
Bjo¨rn Sva¨rd, Jan-Anders Larsson, Philip Ma˚rtensson, Bjo¨rn Lundin
ICONE 2010; 671-677https://doi.org/10.1115/ICONE18-30189
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Topics: Boiling water reactors , Finite element analysis , Power uprate , Structural dynamics , Containment , Dynamic analysis , Fluids , Reactor vessels , Safety , Stress
Estimation of the Fluidelastic Instability Boundary for Steam-Generator Tubes Subjected to Two-Phase Flows
Njuki W. Mureithi, Teguewinde P. Sawadogo, Affoua Amenan C. Grie
ICONE 2010; 679-690https://doi.org/10.1115/ICONE18-30241
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Topics: Boilers , Two-phase flow , Excitation , Fluids , Vibration , Wear , Force measurement , Stability , Stress , Water
Stress Analysis and Evaluation of Mussel Trap for Nuclear Power Plant
Hongxin Tao, Feiyun Zhao
ICONE 2010; 691-696https://doi.org/10.1115/ICONE18-30255
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Topics: Nuclear power stations , Stress , Stress analysis (Engineering)
Effect of Irradiation Deformation and Graphite Varieties on the Irradiation Equivalent Stress and Life of Nuclear Graphite
Xiang Fang, Haitao Wang, Suyuan Yu
ICONE 2010; 697-700https://doi.org/10.1115/ICONE18-30359
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Topics: Deformation , Graphite , Irradiation (Radiation exposure) , Stress , Creep , High temperature , Finite element analysis , Mechanical properties , Neutrons , Thermal properties
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