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Proceedings Papers

Comparison of K-Solutions of Rectangular Flaw With Semi-Elliptical Flaw for PWSCC Growth Analysis

Kiminobu Hojo, David Rudland
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T06A009, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136517
https://doi.org/10.1115/ICONE31-136517
View Paper titled, Comparison of K-Solutions of Rectangular Flaw With Semi-Elliptical Flaw for PWSCC Growth Analysis
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Topics: ASME Standards, Coolants, Fracture (Materials), Japan Society of Mechanical Engineers, JSME Standards, Metals, Pipes, Shapes, Stress corrosion cracking, Surges
Proceedings Papers

Stress Intensity Factor Solutions for Circumferential Through-Wall Cracks Applicable to Pool Type Sodium Cooled Fast Reactors

Hiroki Yada, Shigeru Takaya, Hideo Machida
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A010, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134552
https://doi.org/10.1115/ICONE31-134552
View Paper titled, Stress Intensity Factor Solutions for Circumferential Through-Wall Cracks Applicable to Pool Type Sodium Cooled Fast Reactors
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Topics: Cylinders, Fast neutron reactors, Finite element analysis, Fracture (Materials), Sodium, Stress
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 of Iodine-Induced Stress Corrosion Cracking of CZ2 Alloy

Lin Shi, Changyuan Gao, Guoliang Zhang, Guocheng Sun, Xu Wang, Liutao Chen, Jun Tan
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A091, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93835
https://doi.org/10.1115/ICONE29-93835
View Paper titled, Study of Iodine-Induced Stress Corrosion Cracking of CZ2 Alloy
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Topics: Alloys, Fracture (Materials), Fracture (Process), Stress corrosion cracking
Proceedings Papers

A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant

Zihao Zheng, Wenxin Qiu, Yang Dai, Jiesheng Min
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A064, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93082
https://doi.org/10.1115/ICONE29-93082
View Paper titled, A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant
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Topics: Brittle fracture, Finite element methods, Fracture (Materials), Fracture (Process), Nuclear power stations, Pipes, Radiation (Physics), Computer software, Engineering standards, Engineers
Proceedings Papers

Research on the Technology Accuracy of the On-Line Fracture Assessment of Cracked Pipe in NPPs

Mingya Chen, Min Yu, Hongbo Gao, Shuang Qi, Lei Lin, Decheng Xu, Weiqiang Wang, Jinhua Shi, Qunjia Peng, Guodong Zhang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A003, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89057
https://doi.org/10.1115/ICONE29-89057
View Paper titled, Research on the Technology Accuracy of the On-Line Fracture Assessment of Cracked Pipe in NPPs
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Topics: Computer software, Fracture (Materials), Fracture (Process), Nuclear power stations, Pipes
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

Research on Crack Resistance of Nuclear Grade Nickel-Based Alloy Welding Materials

Ying Ao, Changzheng Xu, Guo He, Zhanpeng Lv, Ping Zhu, Maolong Zhang, Jiasheng Zou
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A004, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89321
https://doi.org/10.1115/ICONE29-89321
View Paper titled, Research on Crack Resistance of Nuclear Grade Nickel-Based Alloy Welding Materials
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Topics: Alloys, Crystals, Ductility, Fracture (Materials), Fracture (Process), Nickel, Stress corrosion cracking, Welding
Proceedings Papers

Further Study on Real-Time Positioning of Fuel Failures Method in HFETR

Shouhua Sun, Jian Li
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A009, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64210
https://doi.org/10.1115/ICONE28-64210
View Paper titled, Further Study on Real-Time Positioning of Fuel Failures Method in HFETR
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Topics: Failure, Fuels, Radioisotopes, Chain, Cladding systems (Building), Coolants, Corrosion, Damage, Fracture (Materials), Manufacturing
Proceedings Papers

Cause Analysis and Influence Evaluation of Cracks in Thick Slab Construction

Yi Guixiang, Li Liang
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A021, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64548
https://doi.org/10.1115/ICONE28-64548
View Paper titled, Cause Analysis and Influence Evaluation of Cracks in Thick Slab Construction
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Topics: Construction, Fracture (Materials), Slabs
Proceedings Papers

Development of Digital Twins of PWR Steam Generators: Description of Two Maintenance-Oriented Use Cases

Enrico Deri, Christophe Varé, Matthieu Wintergerst
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T01A002, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63246
https://doi.org/10.1115/ICONE28-63246
View Paper titled, Development of Digital Twins of PWR Steam Generators: Description of Two Maintenance-Oriented Use Cases
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Topics: Boilers, Maintenance, Pressurized water reactors, Computation, Design, Emergency preparedness, Engineering disciplines, Fracture (Materials), Inspection, Instrumentation
Proceedings Papers

Effects of Pre-Crack Depth and Hydrogen Absorption on the Failure Strain of Zircaloy-4 Cladding Tubes Under Biaxial Strain Conditions

Feng Li, Takeshi Mihara, Yutaka Udagawa, Masaki Amaya
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A052, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16738
https://doi.org/10.1115/ICONE2020-16738
View Paper titled, Effects of Pre-Crack Depth and Hydrogen Absorption on the Failure Strain of Zircaloy-4 Cladding Tubes Under Biaxial Strain Conditions
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Topics: Absorption, Cladding systems (Building), Failure, Fracture (Materials), Hydrogen, Heat treating (Metalworking), Accidents, Fuels, Manufacturing, Metals
Proceedings Papers

IHSI Effectiveness for Crack Propagation Observed at Hamaoka PLR Piping

Hideki Yuya, Kouji Yamada, Takao Sasayama
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T06A004, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16090
https://doi.org/10.1115/ICONE2020-16090
View Paper titled, IHSI Effectiveness for Crack Propagation Observed at Hamaoka PLR Piping
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Topics: Crack propagation, Electromagnetic induction, Fracture (Materials), Heat, Pipes, Stress, Ultrasonic testing, Cutting, Plant construction
Proceedings Papers

Investigating Structural Response of Pressure Reducing Valve of Supercritical Steam Generator System Under Cyclic Moments, Thermal Transient, and Pressure Loadings

Nak-Kyun Cho, Pavitra Bansal, Antony M. Hurst
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T06A015, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16426
https://doi.org/10.1115/ICONE2020-16426
View Paper titled, Investigating Structural Response of Pressure Reducing Valve of Supercritical Steam Generator System Under Cyclic Moments, Thermal Transient, and Pressure Loadings
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Topics: Boilers, Pressure, Transients (Dynamics), Valves, Pipes, Temperature, Collapse, Engineers, Fatigue, Flow (Dynamics)
Proceedings Papers

Probability of Rupture for WWER-1000 Main Piping

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

A Theoretical Model of the Stress Intensity Factor Threshold of DHC for Fuel Cladding Tube

Liang Chen, Lili Liu, Xiaoming Song, Hua Pang
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A031, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81665
https://doi.org/10.1115/ICONE26-81665
View Paper titled, A Theoretical Model of the Stress Intensity Factor Threshold of DHC for Fuel Cladding Tube
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Topics: Cladding systems (Building), Fuels, Stress, Temperature, Fracture (Materials), Temperature gradient, Cracking (Materials), Diffusion (Physics), Fracture (Process), Hydrogen
Proceedings Papers

Study on Hydrogen Migration in Small Water Leak of Sodium-Cooled Fast Reactor

Xinjie Deng, Xuewu Cao
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A021, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81314
https://doi.org/10.1115/ICONE26-81314
View Paper titled, Study on Hydrogen Migration in Small Water Leak of Sodium-Cooled Fast Reactor
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Topics: Hydrogen, Sodium fast reactors, Water leakage, Sodium, Circuits, Water, Leakage, Boilers, Fracture (Materials), Heat
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

Effect of Subcooling and Nozzle Diameter on Heat Transfer Characteristics of Downward Facing Hot Surfaces Using Mist Jet

Avadhesh Kumar Sharma, Monika Meena, Anirudh Soni, Santosh K. Sahu
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A040, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82211
https://doi.org/10.1115/ICONE26-82211
View Paper titled, Effect of Subcooling and Nozzle Diameter on Heat Transfer Characteristics of Downward Facing Hot Surfaces Using Mist Jet
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Topics: Heat transfer, Nozzles, Subcooling, Heat flux, Cooling, Impingement cooling, Temperature, Compressed air, Drops, Ductility