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Proceedings Papers

High Temperature Gas Cooled Reactor Steam Generator Research on Stress-Rupture Test of High Temperature Materials and Welded Joints

Shimei Bao
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A039, August 8–12, 2022
Paper No: ICONE29-92956
DOI: https://doi.org/10.1115/ICONE29-92956
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Topics: Boilers, Gas cooled reactors, High temperature, High temperature materials, Rupture, Stress, Very high temperature reactors, Welded joints
Proceedings Papers

Radiographic Examination of Electric Heater Tube Weld for HPR1000 Pressurizer

Jintao Yu, Dandan Lu, Jianlei Zhang
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A040, August 8–12, 2022
Paper No: ICONE29-92958
DOI: https://doi.org/10.1115/ICONE29-92958
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Topics: China, Heating, Intellectual property, Nuclear power, Nuclear power stations, Welded joints
Proceedings Papers

Non-Destructive Examination of PWR Steam Generator Tube-Tube Plate Welds After Repairing Melting Damage

Yan Zhang, JianLei Zhang, Zhonghe Cheng
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A045, August 8–12, 2022
Paper No: ICONE29-92978
DOI: https://doi.org/10.1115/ICONE29-92978
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Topics: Boilers, Damage, Maintenance, Melting, Nondestructive evaluation, Pressurized water reactors, Welded joints
Proceedings Papers

Root Cause Analysis of Nonrelevant Indication of Magnetic Particle Test on 18MND5 Steel Welded Joints in the Steam Generator of a Nuclear Power Project

Yanbing Guo, Yanhong Lu, Wang Zhang, Miaosen Yang, Xiyang Liu, Binfeng Lu
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A029, August 8–12, 2022
Paper No: ICONE29-92313
DOI: https://doi.org/10.1115/ICONE29-92313
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Topics: Boilers, Magnetic particles, Nuclear power, Root cause analysis, Steel, Welded joints
Proceedings Papers

Simulation of Severe Accident Progression Using ROSHNI: A New Integrated Simulation Code for PHWR Severe Accidents

Sunil Nijhawan, YongMann Song
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, V001T01A014, August 4–5, 2020
Paper No: ICONE2020-16633
DOI: https://doi.org/10.1115/ICONE2020-16633
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Topics: Accidents, Heavy water reactors, Simulation, Fuels, Design, Modeling, Vessels, Damage, Failure, Fluids
Proceedings Papers

Nuclear Pressure Vessel Manufacture Using the Hot Isostatic Pressing (HIP) Process

John Sulley, Phil Wallace, Ted Warner, Gary Jones
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, V001T06A002, August 4–5, 2020
Paper No: ICONE2020-16035
DOI: https://doi.org/10.1115/ICONE2020-16035
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Topics: Hot pressing, Reactor vessels, Vessels, Nuclear power stations, Pressure vessels, Welding, Alloy steel, Electron beam welding, Energy generation, Fillers (Materials)
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
Paper No: ICONE2020-16897
DOI: https://doi.org/10.1115/ICONE2020-16897
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Topics: Leakage, Pipes, Probability, Rupture, Stress, Fracture (Materials), Accounting, Flow (Dynamics), Fracture toughness, Nuclear power stations
Proceedings Papers

CFD Thermal Analysis of ITER Pressure Suppression Tanks

Lorenzo Basili, Rosa Lo Frano, Marco Olcese, Igor Sekachev, Donato Aquaro
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A095, July 22–26, 2018
Paper No: ICONE26-82550
DOI: https://doi.org/10.1115/ICONE26-82550
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Topics: Computational fluid dynamics, Pressure, Thermal analysis, Stress, Thermal insulation, Vacuum, Vessels, Design, Fatigue, Fusion reactors
Proceedings Papers

Welded Joint Evaluation for Chromium Controlled Carbon Steel Piping to Improve FAC Resistance

Yoshio Uemoto, Takahiro Kawabe, Hiroyuki Shibata, Shoh Tarasawa, Hiroshi Asano, Junya Kaneda
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A022, July 22–26, 2018
Paper No: ICONE26-81913
DOI: https://doi.org/10.1115/ICONE26-81913
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Topics: Carbon steel, Pipes, Welded joints, Welding, Alloy steel, Alloys, Condensed matter, Construction, Corrosion, Feedwater
Proceedings Papers

Application of Joint Boring Technique in Solving RCL Wall Thickness Problem

Huadong Zhu
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, V001T01A002, July 2–6, 2017
Paper No: ICONE25-66026
DOI: https://doi.org/10.1115/ICONE25-66026
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Topics: Wall thickness, Design, In-service inspection, Inspection, Nuclear power, Nuclear power stations, Nuclear reactor coolants, Reactor vessels, Welded joints, Boilers
Proceedings Papers

Structural Integrity Assessment to Justify Increase in Upper Operating Temperature Limit of AGR Dome

Antony M. Hurst
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A067, July 2–6, 2017
Paper No: ICONE25-66859
DOI: https://doi.org/10.1115/ICONE25-66859
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Topics: Domes (Structural elements), Operating temperature, Temperature, Failure, Creep, Safety, Welded joints, Diaphragms (Mechanical devices), Diaphragms (Structural), Failure mechanisms
Proceedings Papers

Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regard to Primary Water Stress Corrosion Cracking

Akihiro Mano, Yoshihito Yamaguchi, Jinya Katsuyama, Yinsheng Li
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A014, July 2–6, 2017
Paper No: ICONE25-66145
DOI: https://doi.org/10.1115/ICONE25-66145
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Topics: Fracture mechanics, Stress corrosion cracking, Water, Failure, Pipes, Probability, Fracture (Materials), Pressurized water reactors, Alloys, Boiling water reactors
Proceedings Papers

Thermal Fatigue Test on Dissimilar Welded Joint Between Gr.91 and 304SS

Takashi Wakai, Sumio Kobayashi, Shoichi Kato, Masanori Ando, Hideki Takasho
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A008, July 2–6, 2017
Paper No: ICONE25-66099
DOI: https://doi.org/10.1115/ICONE25-66099
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Topics: Fatigue testing, Welded joints, Steel, Fatigue damage, Creep, Evaluation methods, Fatigue, Fatigue cracks, Finite element analysis, Alloys
Proceedings Papers

Qualification of Ultrasonic Examination for RPV Nozzle to Shell Welds of EPR Nuclear Power Plant

WeiQiang Wang, Zhe Yu, Xin Ye, HuaiDong Chen, GuanBing Ma
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A098, July 2–6, 2017
Paper No: ICONE25-67433
DOI: https://doi.org/10.1115/ICONE25-67433
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Topics: Nozzles, Nuclear power stations, Shells, Ultrasonic testing, Welded joints, Reactor vessels, China, Circuits, Construction, European pressurized reactors
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
Paper No: ICONE25-67243
DOI: https://doi.org/10.1115/ICONE25-67243
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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

Research on Flow Characteristics of Top and Vertical Containment Surface With Different Structures

Pan Xinxin, Liu Jie
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A027, July 2–6, 2017
Paper No: ICONE25-66323
DOI: https://doi.org/10.1115/ICONE25-66323
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Topics: Containment, Flow (Dynamics), Water, Computational fluid dynamics, Accidents, Design, Film flow, Heat, Welded joints, Coating processes
Proceedings Papers

Predictive Methods in the Assessment of Alloy 600 PWSCC Failures in Operating Pressurized Water Reactors

Gutti V. Rao
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, V001T03A037, June 26–30, 2016
Paper No: ICONE24-61141
DOI: https://doi.org/10.1115/ICONE24-61141
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Topics: Alloys, Failure, Pressurized water reactors, Manufacturing, Base metals, Grain size, Indium alloys, Residual stresses, Stress, Temperature
Proceedings Papers

Electron Beam Weldability of AA6061-T6 Aluminum Straps for U-Mo Follower Fuel Assembly Manufacturing

Soo-sung Kim, Yong-jin Jeong, Jong-man Park, Yoon-sang Lee, Chong-tak Lee
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, V001T02A002, June 26–30, 2016
Paper No: ICONE24-60041
DOI: https://doi.org/10.1115/ICONE24-60041
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Topics: Aluminum, Cathode ray oscilloscopes, Electron beams, Fuels, Manufacturing, Exploding wires, Die cutting, Fillers (Materials), Shearing (Deformation), Welding
Proceedings Papers

Seismic Analysis and Design Upgrade of Condensate Storage Tanks

Daniel Moreno, John O’Sullivan, Tsiming Tseng
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, V004T13A016, June 26–30, 2016
Paper No: ICONE24-60741
DOI: https://doi.org/10.1115/ICONE24-60741
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Topics: Condensed matter, Design, Seismic analysis, Storage tanks, Earthquakes, Nuclear power stations, Stress, Shear (Mechanics), Anchor bolts, Anchorage
Proceedings Papers

Evaluation of Fatigue Strength of Similar and Dissimilar Welded Joints of Modified 9Cr-1Mo Steel

Shigeru Takaya
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, V001T02A002, July 7–11, 2014
Paper No: ICONE22-30022
DOI: https://doi.org/10.1115/ICONE22-30022
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Topics: Fatigue strength, Steel, Welded joints, Fatigue life, Base metals, Breeder reactors, Evaluation methods, Failure, Fatigue, Mechanical properties