Volumes | International Conference on Nuclear Engineering | American Society of Mechanical Engineers Digital Collection

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; 33-42doi:https://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; 43-46doi:https://doi.org/10.1115/ICONE18-29128

Abstract

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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; 47-55doi:https://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; 57-64doi:https://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; 65-70doi:https://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; 71-78doi:https://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; 79-85doi:https://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; 87-91doi:https://doi.org/10.1115/ICONE18-29215

Abstract

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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; 93-96doi:https://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; 97-102doi:https://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; 103-111doi:https://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; 113-121doi:https://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; 123-127doi:https://doi.org/10.1115/ICONE18-29291

Abstract

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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; 129-133doi:https://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; 135-140doi:https://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; 141-145doi:https://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; 147-156doi:https://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; 157-163doi:https://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; 165-171doi:https://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; 173-178doi:https://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; 179-184doi:https://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; 185-190doi:https://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; 191-206doi:https://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; 207-218doi:https://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; 219-222doi:https://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; 223-228doi:https://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; 229-235doi:https://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; 237-246doi:https://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; 247-253doi:https://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; 255-263doi:https://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; 265-268doi:https://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; 269-274doi:https://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; 275-281doi:https://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; 283-291doi:https://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; 293-298doi:https://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; 299-308doi:https://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; 309-316doi:https://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; 317-322doi:https://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; 323-332doi:https://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; 333-339doi:https://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; 341-346doi:https://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; 347-356doi:https://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; 357-367doi:https://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; 369-374doi:https://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; 375-378doi:https://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; 379-385doi:https://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; 387-392doi:https://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; 393-402doi:https://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; 403-412doi:https://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; 413-421doi:https://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; 423-428doi:https://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; 429-434doi:https://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; 435-441doi:https://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; 443-448doi:https://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; 449-455doi:https://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; 457-462doi:https://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; 463-468doi:https://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; 469-478doi:https://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; 479-486doi:https://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; 487-491doi:https://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; 493-498doi:https://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; 499-503doi:https://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; 505-515doi:https://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; 517-522doi:https://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; 523-528doi:https://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; 529-537doi:https://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; 539-547doi:https://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; 549-552doi:https://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; 553-557doi:https://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; 559-569doi:https://doi.org/10.1115/ICONE18-29786

Abstract

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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; 571-576doi:https://doi.org/10.1115/ICONE18-29814

Abstract

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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; 577-584doi:https://doi.org/10.1115/ICONE18-29825

Abstract

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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; 585-591doi:https://doi.org/10.1115/ICONE18-29838

Abstract

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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; 593-596doi:https://doi.org/10.1115/ICONE18-29872

Abstract

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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; 597-606doi:https://doi.org/10.1115/ICONE18-29880

Abstract

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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; 607-615doi:https://doi.org/10.1115/ICONE18-29896

Abstract

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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; 617-624doi:https://doi.org/10.1115/ICONE18-29930

Abstract

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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; 625-630doi:https://doi.org/10.1115/ICONE18-29982

Abstract

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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; 631-638doi:https://doi.org/10.1115/ICONE18-30028

Abstract

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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; 639-645doi:https://doi.org/10.1115/ICONE18-30066

Abstract

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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; 647-651doi:https://doi.org/10.1115/ICONE18-30101

Abstract

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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; 653-659doi:https://doi.org/10.1115/ICONE18-30122

Abstract

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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; 661-670doi:https://doi.org/10.1115/ICONE18-30146

Abstract

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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; 671-677doi:https://doi.org/10.1115/ICONE18-30189

Abstract

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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; 679-690doi:https://doi.org/10.1115/ICONE18-30241

Abstract

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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; 691-696doi:https://doi.org/10.1115/ICONE18-30255

Abstract

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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; 697-700doi:https://doi.org/10.1115/ICONE18-30359

Abstract

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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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