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Proceedings Papers

Oxidation Behavior and Tensile Property of Inconel 617 in the Simulation Environment of the Very-High-Temperature Reactor

Bin Du, Zhiyong Liu, Huaqiang Yin, Penghui Xiao, Huang Zhang, Xuedong He, Tao Ma
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A002, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-130256
https://doi.org/10.1115/ICONE31-130256
View Paper titled, Oxidation Behavior and Tensile Property of Inconel 617 in the Simulation Environment of the Very-High-Temperature Reactor
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Topics: Helium, Oxidation, Simulation, Tensile strength, Very high temperature reactors
Proceedings Papers

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

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

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

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

The Effect of Specimen Size and Surface Roughness on Tensile Strength of Nuclear Graphite

Yuxin Guan, Yingjie Zhan, Shuiyong Wang, Qingwu Wang, Wenxin Ti, Bing Gong
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A028, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91966
https://doi.org/10.1115/ICONE29-91966
View Paper titled, The Effect of Specimen Size and Surface Roughness on Tensile Strength of Nuclear Graphite
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Topics: Graphite, Size effect, Surface roughness, Tensile strength
Proceedings Papers

Experimental Study on Dynamic Tensile Strength of Graphite

Dongqing Tian, Li Shi, Libin Sun, Ke Shen, Kun Xu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A019, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90670
https://doi.org/10.1115/ICONE29-90670
View Paper titled, Experimental Study on Dynamic Tensile Strength of Graphite
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Topics: Graphite, Stress-strain curves, Tensile strength
Proceedings Papers

Point Defect Effects on Tensile Strength of BCC-Fe Studied by Molecular Dynamics

Pandong Lin, Junfeng Nie, Meidan Liu
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A008, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16162
https://doi.org/10.1115/ICONE2020-16162
View Paper titled, Point Defect Effects on Tensile Strength of BCC-Fe Studied by Molecular Dynamics
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Topics: Molecular dynamics, Tensile strength
Proceedings Papers

Irradiation Induced Crosslinking in “Green” Polylactic-Acid (PLA) Polymers for Enhanced Strength and Elevated Temperature Applications

W. Jiang, A. Bakken, R. P. Taleyarkhan
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A044, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16767
https://doi.org/10.1115/ICONE2020-16767
View Paper titled, Irradiation Induced Crosslinking in “Green” Polylactic-Acid (PLA) Polymers for Enhanced Strength and Elevated Temperature Applications
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Topics: Adhesives, Irradiation (Radiation exposure), Polymers, Temperature, Photons, Testing, Accidents, Bond strength, Bonding, Construction
Proceedings Papers

A Systematic Study of the Material Performance of Hot Isostatically Pressed Type 316L Stainless Steel Powder for the Civil Nuclear Sector

William Kyffin, David Gandy, Barry Burdett
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A017, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81438
https://doi.org/10.1115/ICONE26-81438
View Paper titled, A Systematic Study of the Material Performance of Hot Isostatically Pressed Type 316L Stainless Steel Powder for the Civil Nuclear Sector
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Topics: Stainless steel, Manufacturing, Materials properties, Oxygen, ASTM International, Collaboration, Cycles, Defense industry, Electricity (Physics), Hot pressing
Proceedings Papers

Study on Forging Cracks and Manufacturing Process of 022Cr19Ni10N Austenitic Stainless Steel Rod Travel Housing Forging for Control Rod Drive Mechanism

Chen Mei-fang, Cao Sheng-qiang, Tao Zhi-yong
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A093, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67286
https://doi.org/10.1115/ICONE25-67286
View Paper titled, Study on Forging Cracks and Manufacturing Process of 022Cr19Ni10N Austenitic Stainless Steel Rod Travel Housing Forging for Control Rod Drive Mechanism
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Topics: Forging, Fracture (Materials), Manufacturing, Stainless steel, Ferrites (Magnetic materials), Grain size, Low temperature, Temperature, Nitrogen, Plasticity
Proceedings Papers

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

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

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

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

Microstructure and Properties Analysis of Inner Cladding Tube and End Plug Girth Weld of Annular Fuel Element

Ji Pengbo, Lu Hanghang, Wang Zhaosong, Zhang Zhoufeng, Liu Bin
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A048, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67243
https://doi.org/10.1115/ICONE25-67243
View Paper titled, Microstructure and Properties Analysis of Inner Cladding Tube and End Plug Girth Weld of Annular Fuel Element
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Topics: Cladding systems (Building), Fuels, Welding, Fracture (Materials), Fracture (Process), Microhardness, Heat, Pressurized water reactors, Tensile strength, Welded joints
Proceedings Papers

Design of SC Walls and Connections in Nuclear Facilities

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

The Assessment of Containment Functional Failure Frequency in the Revised Level 2 PRA Standard in Japan

Ryoichi Hamazaki, Kazunori Hashimoto, Takayoshi Kusunoki, Chikahiro Satou
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T14A020, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-61019
https://doi.org/10.1115/ICONE24-61019
View Paper titled, The Assessment of Containment Functional Failure Frequency in the Revised Level 2 PRA Standard in Japan
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Topics: Containment, Failure, Accidents, Probability, Explosions, Stress, Damage, Failure mechanisms, Hazards, Steam
Proceedings Papers

Research on Tensile Properties of Ni-Base Super Alloy GH3128

Xi Zhao, Yu Zhou, Kun Yuan
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, V001T03A010, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60174
https://doi.org/10.1115/ICONE24-60174
View Paper titled, Research on Tensile Properties of Ni-Base Super Alloy GH3128
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Topics: Alloys, Tensile strength, Fracture (Materials), Fracture (Process), Plasticity, Temperature, Tension, Very high temperature reactors, Ductile fracture, Heat exchangers
Proceedings Papers

A Comparison of Creep-Fatigue Assessment and Modelling Methods

Rami H. Pohja, Stefan B. Holmström
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, V001T07A007, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30640
https://doi.org/10.1115/ICONE22-30640
View Paper titled, A Comparison of Creep-Fatigue Assessment and Modelling Methods
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Topics: Creep, Fatigue, Modeling, Damage, Design, Cycles, Fatigue damage, Rupture, Steel, Tensile strength
Proceedings Papers

Study on Comparison Between Inconel 617 and GH3128 as Structural Material Candidates for Intermediate Heat Exchanger

Yunbai Shi, Kun Yuan, Xi Zhao, Yannan Wu
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A036, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15948
https://doi.org/10.1115/ICONE21-15948
View Paper titled, Study on Comparison Between Inconel 617 and GH3128 as Structural Material Candidates for Intermediate Heat Exchanger
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Topics: Heat exchangers, Alloys, Heat, High temperature, Nickel, Very high temperature reactors, China, Creep, Temperature, Tensile strength
Proceedings Papers

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

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

Microstructure and Performance of Zr-1.0Cr-0.4Fe-xMo Alloys

T. G. Wei, C. S. Long, B. F. Luan, Z. Miao, W. Wang, L. Chen
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, V001T02A031, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15920
https://doi.org/10.1115/ICONE21-15920
View Paper titled, Microstructure and Performance of Zr-1.0Cr-0.4Fe-xMo Alloys
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Topics: Alloys, Zirconium, Corrosion resistance, Hydrogen, Corrosion, Fracture (Materials), Tensile strength, Atoms, Density, Melting
Proceedings Papers

Development of Co-Reduced Valve Seat for Nuclear Power Plants

Toshiyuki Tazawa, Masahiro Saito, Nobuo Kojima
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, V001T02A045, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16714
https://doi.org/10.1115/ICONE21-16714
View Paper titled, Development of Co-Reduced Valve Seat for Nuclear Power Plants
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Topics: Nuclear power stations, Valves, Alloys, Overlays (Materials engineering), Abrasion, Radiation (Physics), Boiling water reactors, Hardness (Materials), Leakage, Mechanical testing