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Proceedings Papers

Sigma Embrittlement Evaluation Test for Dissimilar Welding Between F6NM and FXM-19

Ryoji Osafune, Yoshihiro Tanabe, Daisuke Yagi, Daisuke Koike
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T10A009, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135920
https://doi.org/10.1115/ICONE31-135920
View Paper titled, Sigma Embrittlement Evaluation Test for Dissimilar Welding Between F6NM and FXM-19
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Topics: Embrittlement, Welded joints, Welding
Proceedings Papers

Research and Development of SA508Gr.4N Steel Ultra-Thick Forgings With High Strength and Toughness for Nuclear Engineering

Dongxu Du, Deli Zhao, Liguo Ren, Wenhui Zhang, Jiaju Li, Xikou He
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A031, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92329
https://doi.org/10.1115/ICONE29-92329
View Paper titled, Research and Development of SA508Gr.4N Steel Ultra-Thick Forgings With High Strength and Toughness for Nuclear Engineering
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Topics: Embrittlement, Forgings (Products), Fracture toughness, Industrial research, Irradiation (Radiation exposure), Nuclear engineering, Steel
Proceedings Papers

Comparison Of Radiation Embrittlement Prediction Models for Reactor Pressure Vessel

Kexin Cai, Ping Huang, Wangjie Qian, Minyu Fan, Shuang Qi, Guodong Zhang, Yanwei Zhang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A044, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92513
https://doi.org/10.1115/ICONE29-92513
View Paper titled, Comparison Of Radiation Embrittlement Prediction Models for Reactor Pressure Vessel
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Topics: Embrittlement, Radiation (Physics), Reactor vessels
Proceedings Papers

Modelling the Brittle-Ductile Transition Temperature of Irradiated A508-3 Steel With CPFEM

Pandong Lin, Junfeng Nie, Meidan Liu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A035, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90986
https://doi.org/10.1115/ICONE29-90986
View Paper titled, Modelling the Brittle-Ductile Transition Temperature of Irradiated A508-3 Steel With CPFEM
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Topics: Brittleness, Embrittlement, Irradiation (Radiation exposure), Modeling, Phase transition temperature, Steel
Proceedings Papers

Numerical Study of the Effect of δ-Ferrite on Crack-Tip Mechanical Field

Yule Wu, Lefu Zhang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A060, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92656
https://doi.org/10.1115/ICONE29-92656
View Paper titled, Numerical Study of the Effect of δ-Ferrite on Crack-Tip Mechanical Field
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Topics: Ferrites (Magnetic materials), Fracture (Materials), Stress, Cracking (Materials), Fracture (Process), Embrittlement, Finite element analysis, Finite element methods, Finite element model, High temperature
Proceedings Papers

Research on Compliance Between Large Break LOCA of HPR1000 and New LOCA Acceptance Criterion 10CFR50.46c

Wang Weiwei, Yang Jiang, Lin Zhikang, Lu Xianghui, Zhang Ying, Shen Ting
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A010, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89155
https://doi.org/10.1115/ICONE29-89155
View Paper titled, Research on Compliance Between Large Break LOCA of HPR1000 and New LOCA Acceptance Criterion 10CFR50.46c
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Topics: Cladding systems (Building), Embrittlement, Fracture (Materials), Fracture (Process), Fuels, Hydrogen, Nuclear power stations, Oxidation, Oxygen, Safety
Proceedings Papers

Evaluation of Irradiation Embrittlement of the Weld Metals in the Chinese RPV

Yupeng Cao, Yinbiao He, Yifeng Huang, Binxi Wang, Yan Yu, Hui Li, Hu Hui
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T09A003, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16261
https://doi.org/10.1115/ICONE2020-16261
View Paper titled, Evaluation of Irradiation Embrittlement of the Weld Metals in the Chinese RPV
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Topics: Embrittlement, Irradiation (Radiation exposure), Metals, Forging, Mechanical properties, China, Damage, Design, Fluence (Radiation measurement), Fracture toughness
Proceedings Papers

Thermal Hydraulic Analysis of Pressurized Thermal Shock for Loviisa NPP Using Apros Simulation Code

Gintaras Žemulis, Pasi Junninen, Petri Kytömäki
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A051, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81558
https://doi.org/10.1115/ICONE26-81558
View Paper titled, Thermal Hydraulic Analysis of Pressurized Thermal Shock for Loviisa NPP Using Apros Simulation Code
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Topics: Nuclear power stations, Simulation, Thermal shock, Safety, Emergencies, Reactor vessels, Embrittlement, Heat, Boundary-value problems, Cooling
Proceedings Papers

Pressurized Thermal Shock (PTS) Transient Scenarios Screening Analysis With TRACE

Roman Mukin, Ivor Clifford, Hakim Ferroukhi, Markus Niffenegger
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A069, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81749
https://doi.org/10.1115/ICONE26-81749
View Paper titled, Pressurized Thermal Shock (PTS) Transient Scenarios Screening Analysis With TRACE
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Topics: Thermal shock, Transients (Dynamics), Nuclear power stations, Vessels, Cooling, Reactor vessels, Accidents, Emergency core cooling systems, Pressure, Pressurized water reactors
Proceedings Papers

Calculational-Experimental Monitoring of Radiation Damage Parameters on VVER Equipment and Their Application During Equipment Residual Life-Time Estimation

Pavel Borodkin, Azamat Gazetdinov, Nikolay Khrennikov
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T01A009, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81708
https://doi.org/10.1115/ICONE26-81708
View Paper titled, Calculational-Experimental Monitoring of Radiation Damage Parameters on VVER Equipment and Their Application During Equipment Residual Life-Time Estimation
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Topics: Damage, Embrittlement, Fluence (Radiation measurement), Metals, Neutrons, Nuclear power stations, Radiation (Physics), Radiation damage, Reactor vessels, Reliability
Proceedings Papers

Observation of the Transformation in Microstructure and Vickers Hardness of Ferrous Model Alloy by Electromagnetic Induction Heating to Form a High Temperature Gradient

Changqing Ye, Qiulin Li, Ping Wu, Guoyi Tang, Wei Liu
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A013, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66144
https://doi.org/10.1115/ICONE25-66144
View Paper titled, Observation of the Transformation in Microstructure and Vickers Hardness of Ferrous Model Alloy by Electromagnetic Induction Heating to Form a High Temperature Gradient
Open the PDF for Observation of the Transformation in Microstructure and Vickers Hardness of Ferrous Model Alloy by Electromagnetic Induction Heating to Form a High Temperature Gradient in another window
Topics: Alloys, Electromagnetic induction, Heating, High temperature, Vickers hardness testing, Steel, Copper, Embrittlement, Hardening, Nuclear power
Proceedings Papers

RPV Structure Integrity Assessment With Surface Cracks Under PTS

Wei Lu, Zheng He
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A048, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66447
https://doi.org/10.1115/ICONE25-66447
View Paper titled, RPV Structure Integrity Assessment With Surface Cracks Under PTS
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Topics: Surface cracks, Stress, Transients (Dynamics), Fracture toughness, Cladding systems (Building), Fracture (Materials), Stress concentration, Temperature, Cooling, Finite element methods
Proceedings Papers

Verification of Probabilistic Fracture Mechanics Analysis Code PASCAL

Yinsheng Li, Genshichiro Katsumata, Koichi Masaki, Shotaro Hayashi, Yu Itabashi, Masaki Nagai, Masahide Suzuki, Yasuhiro Kanto
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A050, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66468
https://doi.org/10.1115/ICONE25-66468
View Paper titled, Verification of Probabilistic Fracture Mechanics Analysis Code PASCAL
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Topics: Fracture mechanics, Fracture (Process), Embrittlement, Irradiation (Radiation exposure), Light water reactors, Neutrons, Nuclear power, Nuclear power stations, Pressure, Reactor vessels
Proceedings Papers

Small Punch Test on Mechanical Properties of Molybdenum Single Crystal Weld

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

Effect of Element Segregation on Thermal Aging Behavior of 17-4PH Martensitic Stainless Steel for Nuclear Power Plant

Bing Bai, Hanxiao Wang, Changyi Zhang, Zhenfeng Tong, Wen Yang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A076, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66977
https://doi.org/10.1115/ICONE25-66977
View Paper titled, Effect of Element Segregation on Thermal Aging Behavior of 17-4PH Martensitic Stainless Steel for Nuclear Power Plant
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Topics: Nuclear power stations, Stainless steel, Steel, Valves, Atoms, Density, Ductile-brittle transition, Embrittlement, Ferrites (Magnetic materials), High temperature
Proceedings Papers

Simulation of the Delayed Hydride Cracking Velocity for Zirconium Alloy Materials Considering Irradiation Effects

Jingyu Zhang, Bingzhong Wang, Jiacheng Zhu, Shurong Ding, Liang Chen, Wenjie Li, Hua Pang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A055, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67410
https://doi.org/10.1115/ICONE25-67410
View Paper titled, Simulation of the Delayed Hydride Cracking Velocity for Zirconium Alloy Materials Considering Irradiation Effects
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Topics: Cracking (Materials), Irradiation (Radiation exposure), Simulation, Zirconium alloys, Embrittlement, Hardening, Traction, Anisotropy, Boundary-value problems, Computer simulation
Proceedings Papers

High Temperature Oxidation of Zry-4 in Oxygen-Nitrogen Atmospheres

Martin Negyesi, Masaki Amaya
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A035, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67609
https://doi.org/10.1115/ICONE25-67609
View Paper titled, High Temperature Oxidation of Zry-4 in Oxygen-Nitrogen Atmospheres
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Topics: High temperature, Nitrogen, Oxidation, Oxygen, Weight (Mass), Flow (Dynamics), Cladding systems (Building), Compression, Embrittlement, Fuels
Proceedings Papers

Neutron Embrittlement Analysis of Qinshan 320MWe RPV on OLE

Tao Hongxin, He Yinbiao, Cao Ming, Shen Rui
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A013, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66361
https://doi.org/10.1115/ICONE25-66361
View Paper titled, Neutron Embrittlement Analysis of Qinshan 320MWe RPV on OLE
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Topics: Embrittlement, Neutrons, Fracture (Materials), Fracture (Process), Irradiation (Radiation exposure), Pressurized water reactors, Safety, Service life (Equipment), Fracture mechanics, High pressure (Physics)
Proceedings Papers

Hafnium in Nuclear Fuel Cladding Used Both as Oxidation Protection and Burnable Absorber

Jiři Závorka, Radek Škoda
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A015, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60302
https://doi.org/10.1115/ICONE24-60302
View Paper titled, Hafnium in Nuclear Fuel Cladding Used Both as Oxidation Protection and Burnable Absorber
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Topics: Cladding systems (Building), Nuclear fuels, Oxidation, Fuels, Zirconium alloys, Heat, Hydrogen, Nuclear power stations, Zirconium, Accidents
Proceedings Papers

Investigation of Liquid Metal Embrittlement of AISI 316L Steels

L. Stefanini, Rosa Lo Frano, Erich Stergar
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A072, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60969
https://doi.org/10.1115/ICONE24-60969
View Paper titled, Investigation of Liquid Metal Embrittlement of AISI 316L Steels
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Topics: Embrittlement, Liquid metals, Steel, Coolants, Corrosion resistance, Electrical conductivity, Electromagnetic scattering, Fracture (Materials), Fracture (Process), Irradiation (Radiation exposure)