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Proceedings Papers

Effect of Structural State of Austenitic 15-15 Ti Steel on Initiation and Propagation of Solution-Based Corrosion Attack in Flowing Liquid Pb-Bi Eutectic at 400 and 500 °C

Valentyn Tsisar, Carsten Schroer, Olaf Wedemeyer, Aleksandr Skrypnik, Jürgen Konys
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A056, July 2–6, 2017
Paper No: ICONE25-66634
DOI: https://doi.org/10.1115/ICONE25-66634
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Topics: Corrosion, Steel, Deformation, Diffusion (Physics), Electron backscatter diffraction, Grain boundaries, Liquid metals
Proceedings Papers

Microstructure and Properties of New Zirconium Alloys for CAP1400 Fuel Assembly

Qifeng Zeng, Libing Zhu, Gaihuan Yuan, Lian Wang, Guocheng Sun, Junqiang Lu
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A037, July 2–6, 2017
Paper No: ICONE25-66951
DOI: https://doi.org/10.1115/ICONE25-66951
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Topics: Fuels, Manufacturing, Zirconium alloys, Alloys, Corrosion resistance, Creep, Mechanical properties, Design, Temperature, Water chemistry
Proceedings Papers

Orientation Relationships of Delta Hydrides in Zirconium and Zircaloy-4

Anton Pshenichnikov, Juri Stuckert
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A006, June 26–30, 2016
Paper No: ICONE24-60061
DOI: https://doi.org/10.1115/ICONE24-60061
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Topics: Zirconium, Diffraction, Electron backscatter diffraction, Electrons, Grain boundaries, Spectra (Spectroscopy)
Proceedings Papers

Investigation of the Effects of Hydrogen Atoms Concentration on the Tungsten Sigma 5 (310) Symmetric Tilt Grain Boundary

Kabiru Atiku, Xue Yang
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A030, June 26–30, 2016
Paper No: ICONE24-60450
DOI: https://doi.org/10.1115/ICONE24-60450
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Topics: Atoms, Grain boundaries, Hydrogen, Tungsten, Computer software, Isotopes, Modeling, Molecular dynamics, Nuclear fusion, Simulation
Proceedings Papers

Effects of Carbide Precipitate Formation on the Change in Ultrasonic Velocity in Austenitic Stainless Steels

Taira Okita, Junji Etoh, Mitsuyuki Sagisaka, Takashi Matsunaga, Yoshihiro Isobe
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T02A019, July 7–11, 2014
Paper No: ICONE22-30859
DOI: https://doi.org/10.1115/ICONE22-30859
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Topics: Stainless steel, Annealing, Carbon, Grain boundaries, Precipitation, Temperature, Ultrasonic testing
Proceedings Papers

Ultrasonic NDE for Irradiation-Induced Material Degradations

Yoshihiro Isobe, Junji Etoh, Mitsuyuki Sagisaka, Takashi Matsunaga, Paula Freyer, Frank Garner, Taira Okita
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A048, July 29–August 2, 2013
Paper No: ICONE21-16850
DOI: https://doi.org/10.1115/ICONE21-16850
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Topics: Irradiation (Radiation exposure), Materials degradation, Nondestructive evaluation, Ultrasonic waves, Dislocations, Grain boundaries, Signals, Stainless steel
Proceedings Papers

Behavior of the Ag-In-Cd Alloy Control Rod Under Irradiation

Hongxing Xiao, Chongsheng Long, Le Chen, Bo Liang
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A027, July 29–August 2, 2013
Paper No: ICONE21-15857
DOI: https://doi.org/10.1115/ICONE21-15857
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Topics: Alloys, Irradiation (Radiation exposure), Creep, Temperature, Electrical conductivity, Pressurized water reactors, Stress, Thermal conductivity, Thermal diffusivity, Damage
Proceedings Papers

A Computational Modeling Tool for Welding Repair of Irradiated Materials

Zhili Feng, Ken Wolfe, Eric Willis
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T01A038, July 29–August 2, 2013
Paper No: ICONE21-16472
DOI: https://doi.org/10.1115/ICONE21-16472
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Topics: Computer simulation, Cracking (Materials), Fracture (Process), Helium, Maintenance, Welding, Bubbles, Fracture (Materials), Heat, Stress
Proceedings Papers

Finite Element Models of Progressive Failure of Grain Boundaries

Mihaela Irina Uplaznik, Leon Cizelj, Igor Simonovski
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 545-550, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-55191
DOI: https://doi.org/10.1115/ICONE20-POWER2012-55191
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Topics: Failure, Finite element model, Grain boundaries, Computational methods, Damage, Modeling, Stress corrosion cracking, Alloys, Anisotropy, Cracking (Materials)
Proceedings Papers

Neutron Diffraction and SEM Study on CaO-Al 2 O 3 -SiO 2 (ZnO-BaO-Na 2 O) Glass-Ceramics Prepared Under Different Cooling Conditions

Liping Guo, Jun Xie, Kai Sun, Zheng Yang, Shuoxue Jin, Guoliang Peng, Yami Fang
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 259-264, May 17–21, 2010
Paper No: ICONE18-30275
DOI: https://doi.org/10.1115/ICONE18-30275
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Topics: Cooling, Glass ceramics, Neutron diffraction, Crystals, Temperature, Diffraction, Fracture (Materials), Fracture (Process), Glass, Microcracks
Proceedings Papers

Study on the Hydrogen Effect on the Temper Embrittlement of 2.25Cr-1Mo Steel

Xiliang Zhang, Changyu Zhou
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 179-184, May 17–21, 2010
Paper No: ICONE18-29503
DOI: https://doi.org/10.1115/ICONE18-29503
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Topics: Embrittlement, Hydrogen, Steel, Grain boundaries, Hydrogen embrittlement, Testing, Augers, Electrons
Proceedings Papers

Multiphysics Modeling and Simulation for Stress Corrosion Cracking Considering Oxygen Atom Diffusion Along Grain Boundary

Takahiro Igarashi, Yoshiteru Aoyagi, Yoshiyuki Kaji
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 129-133, May 17–21, 2010
Paper No: ICONE18-29337
DOI: 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
Proceedings Papers

High Temperature Aging and Corrosion Study on Alloy 617 and Alloy 230

Kun Mo, Gianfranco Lovicu, Hsiao-Ming Tung, Xiang Chen, James F. Stubbins
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 323-332, May 17–21, 2010
Paper No: ICONE18-30207
DOI: 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
Proceedings Papers

The Effect of Fabrication Process on Microstructure Evolution of N18 Alloy Sheets

Xun Dai, Hong Liu, Hongman Jiang, Ying Wang
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 135-140, May 17–21, 2010
Paper No: ICONE18-29339
DOI: 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
Proceedings Papers

Corrosion Resistance of Mo-Fe-Ti Alloy for Overpack in Simulating Underground Environment

Toshiyasu Nishimura
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 27-32, May 17–21, 2010
Paper No: ICONE18-29107
DOI: https://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
Proceedings Papers

Study of Weld Residual Stress Field in the Girth Seam H6A of Core Shroud of Boiling Water Reactor

Yongkui Li, Yoshiyuki Kaji, Takahiro Igarashi
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 97-102, May 17–21, 2010
Paper No: ICONE18-29269
DOI: 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
Proceedings Papers

Influence of Impurities on Intergranular Corrosion of Extra High Purity Austenitic Stainless Steels

Ikuo Ioka, Jun Suzuki, Takafumi Motoka, Kiyoshi Kiuchi, Junpei Nakayama
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 563-567, July 12–16, 2009
Paper No: ICONE17-75531
DOI: https://doi.org/10.1115/ICONE17-75531
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Topics: Corrosion, Stainless steel, Alloys, Ions, Boiling, Grain boundaries, High temperature, Melting, Nuclear fuels, Regression analysis
Proceedings Papers

Weldability of Neutron Irradiated Stainless Steels by YAG Laser and Low-Heat-Input TIG Welding Techniques

Masatoshi Sato, Kiyotomo Nakata, Masayoshi Ozawa
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 727-734, July 12–16, 2009
Paper No: ICONE17-75912
DOI: https://doi.org/10.1115/ICONE17-75912
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Topics: Gas tungsten arc welding, Heat, Lasers, Neutrons, Stainless steel, Welding, Fracture (Materials), Cavities, Cracking (Materials), Fracture (Process)
Proceedings Papers

Susceptibility of Intergranular Corrosion for Extra High Purity Austenitic Stainless Steel in Nitric Acid

Ikuo Ioka, Chiaki Kato, Kiyoshi Kiuchi, Junpei Nakayama
Proc. ASME. ICONE16, Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues, 703-707, May 11–15, 2008
Paper No: ICONE16-48776
DOI: https://doi.org/10.1115/ICONE16-48776
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Topics: Corrosion, Stainless steel, Alloys, Boiling, Boron, Corrosion resistance, Etching, Grain boundaries, Ions, Melting
Proceedings Papers

Simulations of Metal Oxidation in LBE at a Mesoscopic Level

Taide Tan, Yitung Chen
Proc. ASME. ICONE16, Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues, 389-403, May 11–15, 2008
Paper No: ICONE16-48025
DOI: https://doi.org/10.1115/ICONE16-48025
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Topics: Engineering simulation, Mesoscopic systems, Metals, Oxidation, Simulation, Diffusion (Physics), Diffusion processes, Grain boundaries, Ionization, Ions