ICONE18-29390 Stress Corrosion Cracking Incidents and Repair Technologies on PWR Dissimilar Weld Metal Joints in Japan (English)
- New search for: Chigusa, N.
- New search for: Hirano, S.
- New search for: Sera, T.
- New search for: Kaguchi, H.
- New search for: Mukai, M.
- New search for: Yoshida, Y.
- New search for: Chigusa, N.
- New search for: Hirano, S.
- New search for: Sera, T.
- New search for: Kaguchi, H.
- New search for: Mukai, M.
- New search for: Yoshida, Y.
In:
Nuclear engineering
;
147-156
;
2010
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ISBN:
- Conference paper / Print
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Title:ICONE18-29390 Stress Corrosion Cracking Incidents and Repair Technologies on PWR Dissimilar Weld Metal Joints in Japan
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Contributors:Chigusa, N. ( author ) / Hirano, S. ( author ) / Sera, T. ( author ) / Kaguchi, H. ( author ) / Mukai, M. ( author ) / Yoshida, Y. ( author )
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Conference:International conference; 18th, Nuclear engineering ; 2010 ; Xi'an, China
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Published in:Nuclear engineering ; 147-156ICONE - PROCEEDINGS ; 5 ; 147-156
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Publisher:
- New search for: ASME
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Place of publication:New York
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Publication date:2010-01-01
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Size:10 pages
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Remarks:Includes bibliographical references and index
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ISBN:
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Type of media:Conference paper
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Type of material:Print
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Language:English
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Keywords:
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Source:
© Metadata Copyright the British Library Board and other contributors. All rights reserved.
Table of contents conference proceedings
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
- 1
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ICONE18-29013 Ageing Assessment, Condition Inspection and Lifetime Evaluation for Safety Related Fuse in Nuclear Power PlantShi, J. / Jin, X. / Liu, Z. / Shi, H. / Yao, J. / Tu, F. et al. | 2010
- 7
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ICONE18-29037 Fluid-Elastic Instability of Normal Square Tube Bundles in Two-Phase Cross FlowSim, W.G. / Park, M.Y. et al. | 2010
- 15
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ICONE18-29067 Iconic Representation Extension of Event Sequence Diagram Framework for Nuclear Power PlantXie, H. / Cai, Q. / Zhang, Y. et al. | 2010
- 23
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ICONE18-29076 Study of the Corrosion Behavior of Zr-xFe-yCr Alloys in 500^oC/10.3MPa SteamWang, J. / Ying, S. / Zhi, M. / Fan, H. et al. | 2010
- 27
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ICONE18-29107 Corrosion Resistance of Mo-Fe-Ti Alloy for Overpack in Simulating Underground EnvironmentNishimura, T. et al. | 2010
- 33
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ICONE18-29120 Preliminary Discussion on Comparison and Analysis on Nuclear Power Plant Materials Standards of ASME and RCC-MNing, D. / Wang, Y. / Li, H. / Bao, Z. et al. | 2010
- 43
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ICONE18-29128 Evaluation of Thermal Aging Embrittlement in Main Coolant Pipe Steel by Small Punch TestFei, X. / Yu, W. / Chen, X. / Liu, Y. / Shi, Z. / Shu, G. / Wang, X. et al. | 2010
- 47
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ICONE18-29132 Experimental Investigation of Copper/Stainless Steel Joints Formed by Vacuum BrazingYe, C. et al. | 2010
- 57
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ICONE18-29149 Material Surveillance Program Regulatory Guidance for Steam Generator Tubes Extracted From Canadian CANDU® ReactorsLiu, S. / Carroll, B. / Riznic, J. / Christodoulou, N. / Awad, R. et al. | 2010
- 65
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ICONE18-29169 Equilibrium Partition Coefficients of Cesium and Iodine Between Sodium Pool and the Inert Cover GasMiyahara, S. / Nishimura, M. / Nakagiri, T. et al. | 2010
- 71
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ICONE18-29171 Prediction of Radioactive Corrosion Product Transfer in Primary Systems of Japanese Prototype Fast Breeder Reactor MONJUMatuo, Y. / Hasegawa, M. / Maegawa, Y. / Miyahara, S. et al. | 2010
- 79
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ICONE18-29212 Threshold Stress Intensity Factor for Delayed Hydride Cracking of a Recrystallized N18 Alloy Plate Along the Rolling DirectionSun, C. / Ying, S.H. / Tan, J. / Peng, Q. / Dai, X. et al. | 2010
- 87
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ICONE18-29215 Applicability Study of Computed Radiography to NDE for Piping and Component in Nuclear Power PlantHasebe, T. / Tamai, N. / Tatsuno, S. / Itahashi, Y. / Tokunou, K. et al. | 2010
- 93
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ICONE18-29240 Irradiation-Embrittlement of Reactor Pressure Vessel SteelLi, G. / Wu, Y. / Jiang, G. / Huang, J. / Zhang, H. et al. | 2010
- 97
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ICONE18-29269 Study of Weld Residual Stress Field in the Girth Seam H6A of Core Shroud of Boiling Water ReactorLi, Y. / Kaji, Y. / Igarashi, T. et al. | 2010
- 103
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ICONE18-29270 The Improvement Research of Accident Generation Mechanism of Dynamic Event TreeZhang, Y. / Tong, J. / Zhou, Y. et al. | 2010
- 113
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ICONE18-29281 Corrosion Test of 304 Stainless Steel in Hydrazine and Methanol Solutions at 320^oC Under Gamma-Irradiation and Gamma Radiolysis of Hydrazine and MethanolDomae, M. / Kawamura, H. / Akutagawa, D. / Hisamune, K. / Katsumura, Y. / Muroya, Y. et al. | 2010
- 123
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ICONE18-29291 Synergistic Effect of Neutron and Gamma Irradiation on CMOS Integrated CircuitsLiu, Y. / Jin, X. / Chen, W. / Lin, D. / Yang, S. et al. | 2010
- 129
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ICONE18-29337 Multiphysics Modeling and Simulation for Stress Corrosion Cracking Considering Oxygen Atom Diffusion Along Grain BoundaryIgarashi, T. / Aoyagi, Y. / Kaji, Y. et al. | 2010
- 135
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ICONE18-29339 The Effect of Fabrication Process on Microstructure Evolution of N18 Alloy SheetsDai, X. / Liu, H. / Jiang, H. / Wang, Y. et al. | 2010
- 141
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ICONE18-29364 Thermal Aging Effect of CDSS on the Integrity of the PWR Primary Pipe With Damage Tolerance MethodWang, Z.-X. / Xue, F. / Shi, H.-J. / Yu, W.-w. / Shu, G.-g. et al. | 2010
- 147
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ICONE18-29390 Stress Corrosion Cracking Incidents and Repair Technologies on PWR Dissimilar Weld Metal Joints in JapanChigusa, N. / Hirano, S. / Sera, T. / Kaguchi, H. / Mukai, M. / Yoshida, Y. et al. | 2010
- 157
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ICONE18-29391 The Reliability Analysis of Bearing in Large Blower SystemZhao, J. / Zhang, Q. / Tong, J. / Wang, H. et al. | 2010
- 165
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ICONE18-29405 Parameters Influencing the Secondary Hydrogenation of Zr-Sn and Zr-Nb Alloys During Steam Oxidation Under LOCA and Severe Accident ConditionsGrosse, M.K. / Steinbrueck, M. / Stuckert, J. et al. | 2010
- 173
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ICONE18-29435 Quality Control of Interface Between Tungsten Coating and Cu Alloy Heat Sink of PFC for EAST Tokamak by Infrared ThermographyQi, P. / Luo, G. / Li, Q. / Kuang, X. / Zhou, H. et al. | 2010
- 179
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ICONE18-29503 Study on the Hydrogen Effect on the Temper Embrittlement of 2.25Cr-1Mo SteelZhang, X. / Zhou, C. et al. | 2010
- 185
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ICONE18-29705 The Mechanical Properties and Friction and Wear Behavior of C/C-SICWen, G. / Long, C. / Rui, T. / Wang, J. et al. | 2010
- 191
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ICONE18-29714 Chemico-Physical Causes of Radiation-Induced ``Long Cell'' Action Corrosion in Water Cooled ReactorsSaji, G. et al. | 2010
- 207
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ICONE18-29726 Aspects of Minimizing Steel Corrosion in Liquid Lead-Alloys by Addition of OxygenSchroer, C. / Wedemeyer, O. / Konys, J. et al. | 2010
- 219
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ICONE18-29854 Assesment of ODS Ferritic Alloy for Advanced Nuclear Energy SystemZhou, Z. / Li, M. / Liao, L. / He, P. / Xu, Y. et al. | 2010
- 223
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ICONE18-29893 Development of Electrical Resistivity Measurement Systems for Inspecting Void Swelling in Irradiated Microscopy DiscsSagisaka, M. / Isobe, Y. / Garner, F. / Fujita, S. / Okita, T. et al. | 2010
- 229
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ICONE18-29927 Corrosion Properties of Welded Ferritic-Martensitic Steels in Liquid Lead-Bismuth at 600CMustari, A.P.A. / Takahashi, M. et al. | 2010
- 237
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ICONE18-29973 Rupture Frequency of CANDU® Large-Diameter Primary Heat Transport Piping Estimated Using Probabilistic Fracture Mechanics CodesMcLean, R. / Duan, X. / Kozluk, M.J. et al. | 2010
- 247
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ICONE18-30045 Dynamic Analysis of Core Magnetic Circuit of Direct Action Solenoid ValveLiu, Q. / Bo, H. / Qin, B. et al. | 2010
- 255
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ICONE18-30049 Irradiation Damage and Embrittlement in RPV Steels Under the Aspect of Long Term Operation: Overview of the FP7 Project LONGLIFEAltstadt, E. / Bergner, F. / Hein, H. et al. | 2010
- 265
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ICONE18-30068 Effect of Temperature in the Preparation of Zirconium HydrideWang, L. / Zhang, L. / Luo, Y. / Chen, W. / Wang, J. et al. | 2010
- 269
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ICONE18-30088 The Welding Deformations of Stainless Steel Pipes With Thick Wall by Narrow Gap Gas Tungsten Arc WeldingZhang, J. / Liu, C. / Niu, J. et al. | 2010
- 275
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ICONE18-30094 Proactive Aging Management: PAM 2.0Perdue, R.K. / Kelley, M.H. / O Rourke, R.E. / Woodcock, J. / Zhang, M. / Zheng, H. et al. | 2010
- 283
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ICONE18-30120 Effect of Hazardous Impurities on Steam Generator Tube DegradationLu, Y. et al. | 2010
- 293
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ICONE18-30121 Irradiation-Induced Embrittlement of INCONEL 600 Flux Detectors in CANDU® ReactorsGriffiths, M. / Bickel, G.A. / Douglas, S.R. et al. | 2010
- 299
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ICONE18-30130 An Accurate Probabilistic Model for Estimating the Life Cycle Cost of Degrading Components in Nuclear Power PlantsCheng, T. / Pandey, M.D. / Xie, W.C. et al. | 2010
- 309
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ICONE18-30169 The Prediction of Long-Term and Emergency Sealability of Silicone and EPDM GasketsNakano, M. / Sasaki, H. / Hanashima, K. et al. | 2010
- 317
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ICONE18-30197 Application of Extra High Purity Austenitic Stainless Steel to Weld OverlayIoka, I. / Suzuki, J. / Kiuchi, K. / Nakayama, J. et al. | 2010
- 323
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ICONE18-30207 High Temperature Aging and Corrosion Study on Alloy 617 and Alloy 230Mo, K. / Lovicu, G. / Tung, H.-M. / Chen, X. / Stubbins, J.F. et al. | 2010
- 333
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ICONE18-30218 Pressurized Water Reactor Core Crud MappingByers, W.A. et al. | 2010
- 341
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ICONE18-30232 State of the Art NDT Mechanized Equipment Used in PWR Reactor Vessel InspectionLi, M. / Chen, H. / Xiao, X. / Lv, T. / Yu, Z. et al. | 2010
- 347
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ICONE18-30249 Bruce Power Aging Obsolescence ProgramCruchley, I. / Dam, R. / Gold, R. / Ferguson, B. et al. | 2010
- 357
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ICONE18-30253 Introduction of Hot Isostatically Pressed, Reactor Coolant System Components in PWR PlantSulley, J.L. / Hookham, I. / Burdett, B. / Bridger, K. et al. | 2010
- 369
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ICONE18-30258 Surveillance Specimen Program for Lifetime Extension of RPVBrumovsky, M. / Kytka, M. et al. | 2010
- 375
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ICONE18-30279 Steam Generator Ageing Management DatabaseChen, J. / Xue, F. / Liu, P. / Zhou, L. / Lin, L. / Ti, W. et al. | 2010
- 379
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ICONE18-30357 Progress of the Study on Corrosion Behavior of Graphite in HTGRsWang, P. / Yu, X. / Yu, S. et al. | 2010
- 387
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ICONE18-30374 Development of a Large Diameter Electromagnetic Pump for 4SAizawa, R. / Fujiwara, S. / Oyamatsu, Y. / Katsuki, K. / Funato, M. / Ota, H. et al. | 2010
- 393
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ICONE18-29087 Dynamic Motion of RC Beams and One-Way Slabs Impacted by a Missile at Medium Velocity: Models for Spreadsheet ApplicationRambach, J.-M. et al. | 2010
- 403
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ICONE18-29140 Random Seismic Response Analysis of Coupling Structure Interconnected by Hysteretic DampersHuang, Q. / Zang, F. / Zhang, Y. et al. | 2010
- 413
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ICONE18-29142 Using Microplane Material Model for Concrete in Soft Missile Impact AnalysisKahkonen, J. / Varpasuo, P. et al. | 2010
- 423
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ICONE18-29174 Floor Response Spectra of Loviisa Nuclear Power Plant Reactor BuildingsKahkonen, J. / Varpasuo, P. et al. | 2010
- 429
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ICONE18-29181 Seismic Fragility Study for High-Pressure Emergency Cooling Water Tanks of Loviisa Nuclear Power PlantKahkonen, J. / Varpasuo, P. et al. | 2010
- 435
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ICONE18-29229 Fortum Participation in IAEA Benchmark for KKNPP7 RHR Piping Response NCO 2007 EventVarpasuo, P. / Kahkonen, J. et al. | 2010
- 443
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ICONE18-29293 The Application of Combination of Individual Modal Responses According to the Revised RG1.92Liu, S. / Xia, Z. et al. | 2010
- 449
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ICONE18-29313 Development and Validation of an LS-DYNA Model for Simulating Vertical Drop Test of a Nuclear Fuel Shipping PackageZhao, W. / Hempy, B. / Liu, J. / Stilwell, W. / Rochow, R. et al. | 2010
- 457
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ICONE18-29326 On-Line Sequestration of Fission Product Gases in Operating Nuclear ReactorsSandquist, G.M. / Kunze, J.F. et al. | 2010
- 463
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ICONE18-29355 Numerical Evaluation of Fluctuating Pressure at Stub Pipes in Actual BWR Main Steam LinesMorita, R. / Takahashi, S. / Inada, F. / Ogawa, Y. et al. | 2010
- 469
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ICONE18-29361 Fluctuating Pressure Generating in BWR Main Steam Lines Acoustic Excited by Safety Relief Valve Stub Pipes and Dead LegsTakahashi, S. / Okuyama, K. / Tamura, A. / Ohtsuka, M. / Tsubaki, M. / Yasuhiro, M. / Kubota, T. / Ogawa, Y. / Inada, F. / Morita, R. et al. | 2010
- 479
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ICONE18-29366 Analysis of Thermal Stratification and Fatigue Stress for Pressurizer Surge LineYu, X. / Zhang, Y. et al. | 2010
- 487
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ICONE18-29389 Prediction of Irradiation Embrittlement for Chinese Domestic A508-3 SteelLu, F. / Wang, R. / Huang, P. / Qian, H. et al. | 2010
- 493
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ICONE18-29448 Three-Dimensional Seismic Analysis on Reactor StructureJiang, N.-b. / Zang, F.-g. / Zhang, L.-m. / Zhang, C.-y. et al. | 2010
- 499
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ICONE18-29450 Computational Method for Crack-Opening-Area of Nuclear Pressure Pipe With Circumferential Through-Wall CrackJun, L. / Bo, Y. / Jiang, N. et al. | 2010
- 505
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ICONE18-29462 Quantitative Evaluation of Hydrogen Micro-Damage in 316L Austenitic Stainless SteelToribio, J. / Ayaso, F.J. et al. | 2010
- 517
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ICONE18-29468 Development and Demonstration of a New Testing Capability for Simulating Multiple Fuel Assembly Impact During a Seismic EventZhao, W. / Lee, Y.C. / Kunishi, H. / Karoutas, Z. / Doan, A. et al. | 2010
- 523
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ICONE18-29560 Creep Stress Analyses Affected by Defect Geometries on P91 Pipe With Local Wall Thinning Under High TemperatureXue, J. / Zhou, C. / Peng, J. et al. | 2010
- 529
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ICONE18-29697 Experimental and Numerical Simulation of Radiolysis Gas Detonations and Mechanical Response of BWR Exhaust PipesKuznetsov, M. / Redlinger, R. / Breitung, W. / Grune, J. / Sempert, K. / Friedrich, A. et al. | 2010
- 539
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ICONE18-29720 Sensitivity Analyses of Finite Element Method for Computing Residual Stress of Dissimilar Metal Multi-Pass WeldTsai, Y. / Li, C. / Tsai, T. / Wang, L.-H. / Fan, T. / Chou, C. et al. | 2010
- 549
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ICONE18-29721 Dynamic Analysis of Including New Loads on Spent Fuel Storage RackTsai, Y. / Tsai, T. / Li, C. / Wang, L.-H. / Fan, T. / Chou, C. et al. | 2010
- 553
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ICONE18-29770 Studies on the Correlation Between Natural Magnetization and Mechanical Damages of an Austenitic Stainless SteelLi, H. / Chen, Z. / Zhao, T. et al. | 2010
- 559
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ICONE18-29786 Effect of Hydrogen Isotope and Concentration on Delayed Hydride Crack Growth Rates in Zr-2.5Nb Pressure TubesShek, G.K. / Seahra, H. et al. | 2010
- 571
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ICONE18-29814 Development of Leak Rate Model for Helium Flow in Elliptically Converging Through Wall CrackZhou, S. / Zhang, Z. / Lamagnere, P. / Cadiou, T. / Berton, J.-L. / Grandotto-Biettoli, M. et al. | 2010
- 577
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ICONE18-29825 Signal Processing Schemes for Defect Identification and Sizing From Signals of Eddy Current Testing in Nuclear Power PlantTian, S. / Chen, Z. / Zhang, D. / Geng, Q. et al. | 2010
- 585
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ICONE18-29838 PCI Risk Assessment ModelParamonov, D. et al. | 2010
- 593
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ICONE18-29872 Time Dependent Leak Rate Change in SCC Degraded SG Tubes of PWRSHwang, S.S. / Park, J. / Jung, M.K. / Kim, H.P. et al. | 2010
- 597
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ICONE18-29880 The Effect of Load Reduction on Crack Initiation Behavior of Hydrides From Flaws in Zr-2.5Nb Pressure Tube MaterialCui, J. / Shek, G.K. et al. | 2010
- 607
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ICONE18-29896 Dynamic Response of a Nuclear Power Plant Subjected to External Accident EventFrano, R.L. / Forasassi, G. et al. | 2010
- 617
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ICONE18-29930 Investigations on Optimal Design of a U-Tube Steam GeneratorQin, H.-m. / Yan, C.-q. / Wang, M. / He, S.-j. et al. | 2010
- 625
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ICONE18-29982 Thermal Ageing Embrittlement of Casting Duplex Stainless Steels for Nuclear Power PlantYao, Y. / Wei, J. / Liu, J. / Wang, Z. / Wang, Y. et al. | 2010
- 631
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ICONE18-30028 Three-Dimensional Earthquake Responses of Nuclear Containment Building Installed in Water-Saturated Soil StrataLee, J.H. / Kim, J.K. / Ryu, J.-S. et al. | 2010
- 639
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ICONE18-30066 Reactor Coolant System Branch Line Pipe Break Analysis for Shin-Kori Units 3&4Byun, Y.J. / Sul, Y.S. / Lee, K.W. / Seo, J.T. et al. | 2010
- 647
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ICONE18-30101 Residual Life Prediction of Corroded Pipeline Based on Electrochemical ModelWang, W.-h. / Yi, J. / Ma, A.-x. / Shen, S.-m. / Yu, X.-c. et al. | 2010
- 653
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ICONE18-30122 Stratified Flows in Pipes: A Parametric Study Towards Fatigue RelevanceCizelj, L. / Simonovski, I. et al. | 2010
- 661
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ICONE18-30146 A Stochastic Approach to Nonlinear Seismic Design SpectraBrahimi, M. et al. | 2010
- 671
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ICONE18-30189 Experiences From Structural Dynamic Analysis Projects of BWR Plants Within the Scope of Power Uprate Projects Using FEASvard, B. / Larsson, J.-A. / Martensson, P. / Lundin, B. et al. | 2010
- 679
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ICONE18-30241 Estimation of the Fluidelastic Instability Boundary for Steam-Generator Tubes Subjected to Two-Phase FlowsMureithi, N.W. / Sawadogo, T.P. / Grie, A.C. et al. | 2010
- 691
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ICONE18-30255 Stress Analysis and Evaluation of Mussel Trap for Nuclear Power PlantTao, H. / Zhao, F. et al. | 2010
- 697
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ICONE18-30359 Effect of Irradiation Deformation and Graphite Varieties on the Irradiation Equivalent Stress and Life of Nuclear GraphiteFang, X. / Wang, H. / Yu, S. et al. | 2010