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Proceedings Papers

Study on Out-Pile Performance of CZ Zirconium Alloy Guide Tube

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Changyuan Gao, Lin Shi, Guoliang Zhang, Yang Xu, Minli Chen, Liutao Chen, Jun Tan
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A089, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93816
https://doi.org/10.1115/ICONE29-93816
View Paper titled, Study on Out-Pile Performance of CZ Zirconium Alloy Guide Tube
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Topics: Corrosion, Creep, Zirconium alloys, Alloys, Zirconium, Corrosion resistance, Stress, Temperature, Mechanical testing, Particulate matter
Proceedings Papers

Study on the Manufacturing Process of Large Super Alloy X-750 Forgings for Nuclear Equipment

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Mei-fang Chen, Sheng-qiang Cao, Kai Dong
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A019, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91791
https://doi.org/10.1115/ICONE29-91791
View Paper titled, Study on the Manufacturing Process of Large Super Alloy X-750 Forgings for Nuclear Equipment
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Topics: Alloys, Forging, Forgings (Products), Manufacturing, Springs, Temperature, Grain size, Annealing, Creep, Fracture (Materials)
Proceedings Papers

Probability of Rupture for WWER-1000 Main Piping

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Yaroslav Dubyk, Maksym Zarazovskii, Sergii Ageiev, Vladislav Filonov
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A014, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16897
https://doi.org/10.1115/ICONE2020-16897
View Paper titled, Probability of Rupture for WWER-1000 Main Piping
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Topics: Leakage, Pipes, Probability, Rupture, Stress, Fracture (Materials), Accounting, Flow (Dynamics), Fracture toughness, Nuclear power stations
Proceedings Papers

The Fracture Behavior of Hydrogen-Charged A508III Low Alloy Steel in the Process of Natural Hydrogen-Escaping

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Qian Xiao, Zhanpeng Lu, Junjie Chen, Hao Peng
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A088, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67246
https://doi.org/10.1115/ICONE25-67246
View Paper titled, The Fracture Behavior of Hydrogen-Charged A508III Low Alloy Steel in the Process of Natural Hydrogen-Escaping
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Topics: Alloy steel, Fracture (Materials), Fracture (Process), Hydrogen, Brittle fracture, Steel, Tensile strength, Brittleness, Current density, Dislocation density
Proceedings Papers

Small Punch Test on Mechanical Properties of Molybdenum Single Crystal Weld

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Yan Ma, Jianju Wang, Jinyun Lei
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A033, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66824
https://doi.org/10.1115/ICONE25-66824
View Paper titled, Small Punch Test on Mechanical Properties of Molybdenum Single Crystal Weld
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Topics: Crystals, Mechanical properties, Molybdenum, Displacement, Stress, Yield strength, Brittleness, Creep, Electron beam welding, Embrittlement
Proceedings Papers

Effects of Neutron Irradiation on the Mechanical and Electromagnetic Properties of Reactor Pressure Vessel Steels

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Li Chengliang, Shu Guogang, Chen Jun, Liu Yi, Liu Wei, Hu Yichuan, Duan Yuangang, Liu Feihua
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A013, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66464
https://doi.org/10.1115/ICONE25-66464
View Paper titled, Effects of Neutron Irradiation on the Mechanical and Electromagnetic Properties of Reactor Pressure Vessel Steels
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Topics: Irradiation (Radiation exposure), Neutrons, Reactor vessels, Steel, Damage, Electrical resistivity, Ductility, Failure mechanisms, Fracture toughness, Magnetization
Proceedings Papers

Microstructures and Properties of 304L Steel CAP1400 Fuel Bottom Nozzles Prepared by Additive Manufacturing Technology

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Li Zongshu, Liu Wentao, Yang Songtao, Hao Ruotong
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A046, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67213
https://doi.org/10.1115/ICONE25-67213
View Paper titled, Microstructures and Properties of 304L Steel CAP1400 Fuel Bottom Nozzles Prepared by Additive Manufacturing Technology
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Topics: Additive manufacturing, Fuels, Nozzles, Steel, Manufacturing, Lasers, Fracture (Materials), Fracture (Process), Ferrites (Magnetic materials), Mechanical properties
Proceedings Papers

Methodology for Fragility Evaluation of a Seawall Against Tsunami Effects: Part 1 — Overflow and Physical Damage Associated With Tsunami Wave Pressure

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Hideki Kaida, Yoshinori Miyagawa, Naoto Kihara
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T07A013, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60927
https://doi.org/10.1115/ICONE24-60927
View Paper titled, Methodology for Fragility Evaluation of a Seawall Against Tsunami Effects: Part 1 — Overflow and Physical Damage Associated With Tsunami Wave Pressure
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Topics: Damage, Pressure, Seawalls, Tsunamis, Waves, Nuclear power stations, Accidents, Compressive strength, Concretes, Density
Proceedings Papers

Design of SC Walls and Connections in Nuclear Facilities

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Amit H. Varma, Saahastaranshu R. Bhardwaj, Sanjeev R. Malushte
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, V001T03A029, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60962
https://doi.org/10.1115/ICONE24-60962
View Paper titled, Design of SC Walls and Connections in Nuclear Facilities
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Topics: Design, Nuclear power stations, Steel, Failure, Quality control, Shear (Mechanics), Stress, Wall panels, Accidents, Buckling
Proceedings Papers

Japanese Codes and Standards for Dual Purpose Metal Casks for Spent Nuclear Fuel

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Toshiari Saegusa, Makoto Hirose, Norikazu Irie, Masashi Shimizu
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, V001T07A009, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30696
https://doi.org/10.1115/ICONE22-30696
View Paper titled, Japanese Codes and Standards for Dual Purpose Metal Casks for Spent Nuclear Fuel
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Topics: Engineering standards, Metals, Spent nuclear fuels, Storage, Stress, Containment vessels, Japan Society of Mechanical Engineers, Safety, Design, Nuclear power stations
Proceedings Papers

Effects of Prior-Deformation and Water Chemistry on Stress Corrosion Cracking of Austenitic Alloys in High Temperature Water

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Zhanpeng Lu, Tetsuo Shoji, Shuang Xia, Meiyi Yao, Bangxin Zhou
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, V001T02A036, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16328
https://doi.org/10.1115/ICONE21-16328
View Paper titled, Effects of Prior-Deformation and Water Chemistry on Stress Corrosion Cracking of Austenitic Alloys in High Temperature Water
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Topics: Alloys, Deformation, High temperature, Stress corrosion cracking, Water, Water chemistry, Electrodes, Coolants, Equilibrium (Physics), Fracture (Materials)
Proceedings Papers

Effect of Mo and Bi on Mechanical Properties of Zr-Fe-Cr Alloy at Room Temperature

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B. F. Luan, L. Q. Yang, T. G. Wei, K. L. Murty, C. S. Long, Q. Liu
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, V001T02A010, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15325
https://doi.org/10.1115/ICONE21-15325
View Paper titled, Effect of Mo and Bi on Mechanical Properties of Zr-Fe-Cr Alloy at Room Temperature
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Topics: Alloys, Mechanical properties, Temperature, Zirconium, Annealing, Tensile strength, Electrons, Elongation, Equipment performance, Heat
Proceedings Papers

Structural Integrity of a Reactor Vessel Lower Head Under In-Vessel Steam Explosion Loads

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Guohong Xue, Yinbiao He, Ming Cao, Hao Yu, Yongjian Gao
Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T15A013, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15831
https://doi.org/10.1115/ICONE21-15831
View Paper titled, Structural Integrity of a Reactor Vessel Lower Head Under In-Vessel Steam Explosion Loads
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Topics: Blast effect, Reactor vessels, Steam, Vessels, Cooling, Explosions, Explosives, Pressure, Water, Accidents
Proceedings Papers

Thermal Aspects of Using Thorium Dioxide as Alternative Nuclear Fuel in SuperCritical Water-Cooled Reactors

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Hemal Patel, Ashley Milner, Caleb Pascoe, Wargha Peiman, Graham Richards, Lisa Grande, Igor Pioro
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 775-781, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29975
https://doi.org/10.1115/ICONE18-29975
View Paper titled, Thermal Aspects of Using Thorium Dioxide as Alternative Nuclear Fuel in SuperCritical Water-Cooled Reactors
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Topics: Nuclear fuels, Water, Fuels, Temperature, Nuclear power stations, Supercritical water reactors, Steam, Cycles, Boilers, Circuits
Proceedings Papers

A Stochastic Approach to Nonlinear Seismic Design Spectra

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Malek Brahimi
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 661-670, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30146
https://doi.org/10.1115/ICONE18-30146
View Paper titled, A Stochastic Approach to Nonlinear Seismic Design Spectra
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Topics: Earthquake resistant design, Spectra (Spectroscopy), Earthquakes, Stiffness, Damping, Design, Yield strength, Degrees of freedom
Proceedings Papers

Selection of Metal Electrodes for and Effect of Welding Treatment on Hardness and Microstructure of Some Type of Austenitic Stainless Steels

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M. M. Ibrahim, H. G. Mohamed, Y. E. Tawfik
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 481-491, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75378
https://doi.org/10.1115/ICONE17-75378
View Paper titled, Selection of Metal Electrodes for and Effect of Welding Treatment on Hardness and Microstructure of Some Type of Austenitic Stainless Steels
Open the PDF for Selection of Metal Electrodes for and Effect of Welding Treatment on Hardness and Microstructure of Some Type of Austenitic Stainless Steels in another window
Topics: Electrodes, Metals, Stainless steel, Welding, Mechanical properties, Pressure vessels, Brittleness, Corrosion resistance, Ductility, Exhaust systems
Proceedings Papers

Analytical Investigation of Deaerator Steam Inlet Nozzle Corrosion Allowance in a CANDU Station

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Ali Keshavarz, Andrew K. Ali, Randy K. Lall
Proc. ASME. ICONE17, Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 187-195, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75617
https://doi.org/10.1115/ICONE17-75617
View Paper titled, Analytical Investigation of Deaerator Steam Inlet Nozzle Corrosion Allowance in a CANDU Station
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Topics: Clearances (Engineering), Corrosion, Nozzles, Steam, Metals, Stress, Stress analysis (Engineering), Carbon steel, Design, Errors
Proceedings Papers

Effect of Orientation on Mechanical Behavior of an Extruded Al Alloy

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M. A. Malik, I. Salam, W. Muhammad
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, 641-647, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48548
https://doi.org/10.1115/ICONE16-48548
View Paper titled, Effect of Orientation on Mechanical Behavior of an Extruded Al Alloy
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Topics: Aluminum alloys, Extruding, Mechanical behavior, Mechanical properties, Reliability, Yield strength, Cylinders, Elongation, Fracture (Materials), Fracture (Process)
Proceedings Papers

Evaluation of Cross-Weld Properties of Austenitic Stainless Steels Before and After PWHT

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M. M. Ibrahim, H. G. Mohamed, Y. E. Tawfik, Ibrahim Taha
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, 405-414, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48043
https://doi.org/10.1115/ICONE16-48043
View Paper titled, Evaluation of Cross-Weld Properties of Austenitic Stainless Steels Before and After PWHT
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Topics: Stainless steel, Tensile strength, Ductility, Gas tungsten arc welding, Heat treating (Metalworking), Piping systems, Plates (structures), Residual stresses, Steel, Temperature
Proceedings Papers

Corrosion Resistant Cladding by YAG Laser Welding in Underwater Environment

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Tsutomu Kochi, Toshio Kojima, Suemi Hirata, Ichiro Morita, Katsura Ohwaki
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 85-107, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22327
https://doi.org/10.1115/ICONE10-22327
View Paper titled, Corrosion Resistant Cladding by YAG Laser Welding in Underwater Environment
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Topics: Cladding systems (Building), Corrosion, Laser welding, Water, Lasers, Nozzles, Stress, Welding, Alloys, Drainage