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Proceedings Papers

Effect of Surface Machining on Stress Corrosion Cracking Sensitivity of 304L and 316L Austenite Stainless Steel

Huanchun Wu, Xinming Meng, Yaolei Han, Yanwei Zhang, Qunjia Peng

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A011, August 8–12, 2022

Paper No: ICONE29-90466

DOI: https://doi.org/10.1115/ICONE29-90466

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Topics: Deformation, High pressure (Physics), High temperature, Machining, Stainless steel, Stress corrosion cracking, Water

Proceedings Papers

Prediction and Uncertainty Analysis of Stress Corrosion Fraction Failure Probability for Pressurized Water Reactor Materials

Deyan Kong, Xu Liu, Jie Cheng, Jianjun Wang, Jinqiang Zhang, Dingyong Chen, Qingzhao Li, Yanting Liu

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A029, August 8–12, 2022

Paper No: ICONE29-91951

DOI: https://doi.org/10.1115/ICONE29-91951

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Topics: Chaos, Failure, Polynomials, Pressurized water reactors, Probability, Stress corrosion cracking, Uncertainty analysis

Proceedings Papers

Study on Ultrasonic Inspection Technology of Fastening Bolts of Reactor Internals

Jianbang Tang, Yukun Wu, Weiqiang Wang, Guanbing Ma, Chenming Zeng, Junlong Xu

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A048, August 8–12, 2022

Paper No: ICONE29-92644

DOI: https://doi.org/10.1115/ICONE29-92644

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Topics: Inspection, Nuclear power stations, Nondestructive evaluation, Design, High pressure (Physics), High temperature, In-service inspection, Irradiation (Radiation exposure), Nuclear fuels, Probes

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

Paper No: ICONE29-93835

DOI: https://doi.org/10.1115/ICONE29-93835

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Topics: Alloys, Fracture (Materials), Fracture (Process), Stress corrosion cracking

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

Paper No: ICONE29-92656

DOI: https://doi.org/10.1115/ICONE29-92656

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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 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

Paper No: ICONE29-89321

DOI: https://doi.org/10.1115/ICONE29-89321

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Topics: Alloys, Crystals, Ductility, Fracture (Materials), Fracture (Process), Nickel, Stress corrosion cracking, Welding

Proceedings Papers

Optimizing Material/Component Fabrication Processing for Improving Service Performance in Nuclear Power Plant Coolants

Zhanpeng Lu

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A030, August 8–12, 2022

Paper No: ICONE29-92321

DOI: https://doi.org/10.1115/ICONE29-92321

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Topics: Coolants, Cracking (Materials), Fracture (Process), Manufacturing, Nuclear power stations, Pressurized water reactors, Stress corrosion cracking

Proceedings Papers

Evaluations of TiO 2 Deposition on Structure Surfaces and Water Radiolysis for the Corrosive Environment in a Reactor Pressure Vessel

Takashi Mawatari, Yasushi Yamamoto, Osamu Shibasaki, Takahiro Hara, Yusuke Horayama, Junichi Takagi

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, V001T02A032, August 4–6, 2021

Paper No: ICONE28-64931

DOI: https://doi.org/10.1115/ICONE28-64931

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Topics: Electrolytic corrosion, Reactor vessels, Stress corrosion cracking, Titanium dioxide, Water

Proceedings Papers

Evaluations of TiO 2 Deposition on Structure Surfaces and Water Radiolysis for the Corrosive Environment in a Reactor Pressure Vessel

Takashi Mawatari, Yasushi Yamamoto, Osamu Shibasaki, Takahiro Hara, Yusuke Horayama, Junichi Takagi

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, V001T06A013, August 4–5, 2020

Paper No: ICONE2020-16405

DOI: https://doi.org/10.1115/ICONE2020-16405

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Topics: Reactor vessels, Stress corrosion cracking, Titanium dioxide, Water, Flow (Dynamics), Computational fluid dynamics, Resolution (Optics), Risk, Boiling water reactors, Catalysts

Proceedings Papers

Development of a Device for Detecting Helium Leaks From Canisters: Part 2 — Numerical Analysis of Temperature Behavior During Gas Leaks From a Canister of a 1/4.5 Scale Cask Model

Kosuke Shimizu, Hirofumi Takeda, Masanori Goto

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A037, July 22–26, 2018

Paper No: ICONE26-81417

DOI: https://doi.org/10.1115/ICONE26-81417

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Topics: Helium, Leakage, Numerical analysis, Temperature, Computational fluid dynamics, Heat transfer, Pressure, Sensors, Concretes, Computer software

Proceedings Papers

Development of Device for Detecting Helium Leak From Canister: Part 1 — Experiment on Temperature Behavior During Gas Leak From Canister of 1/4.5 Scale Cask Model

Hirofumi Takeda, Masanori Goto

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A047, July 22–26, 2018

Paper No: ICONE26-81477

DOI: https://doi.org/10.1115/ICONE26-81477

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Topics: Helium, Leakage, Temperature, Concretes, Pressure, Sensors, Metals, Sealing (Process), Storage, Heat flux

Proceedings Papers

Machine GTAW Ambient Temperature Temper Bead Technique for Ni-Based Weld Overlay Repairs of Nuclear Components: Assessment of Hydrogen Cracking by Implant Test

Marcello Consonni, Claire Verdon

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, V001T01A031, July 2–6, 2017

Paper No: ICONE25-67160

DOI: https://doi.org/10.1115/ICONE25-67160

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Topics: Gas tungsten arc welding, Hydrogen embrittlement, Machinery, Maintenance, Overlays (Materials engineering), Temperature, Heating, Welding, Cracking (Materials), Fracture (Process)

Proceedings Papers

Root Cause Analysis of a Leak Off Tube of the Primary Loop in a CANDU 6 Unit

Liang Zhao, Kunjie Luo

Paper No: ICONE25-66710

DOI: https://doi.org/10.1115/ICONE25-66710

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Topics: Leakage, Root cause analysis, Fracture (Materials), Fluids, Corrosion, Design, Fatigue cracks, Heat, Maintenance, Stress corrosion cracking

Proceedings Papers

Stress Improvement by Laser Peening in the Air

Souichi Ueno, Akihiro Tsuji, Hiroyuki Adachi, Tatsuya Naito

Paper No: ICONE25-66754

DOI: https://doi.org/10.1115/ICONE25-66754

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Topics: Laser hardening, Stress, Lasers, Water, Irradiation (Radiation exposure), Nozzles, Alloys, Density, Laser beams, Abrasion

Proceedings Papers

The Research on Ultrasonic Testing Technology for Bottom Part of Reactor Pressure Vessel

Ge Liang, Xu Xuguang, Cai Jiafan, Cheng Zhaoyu

Paper No: ICONE25-66984

DOI: https://doi.org/10.1115/ICONE25-66984

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Topics: Reactor vessels, Ultrasonic testing, Probes, Inspection, Alloys, Nuclear power stations, Accuracy and precision, Circuits, Corrosion, Design

Proceedings Papers

The Root Cause Analysis of the Bolt Fracture in the Nuclear Power Plant Essential Service Water System

Li Nan, Lao Yi, Che Yinhui

Paper No: ICONE25-67885

DOI: https://doi.org/10.1115/ICONE25-67885

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Topics: Fracture (Materials), Fracture (Process), Nuclear power stations, Root cause analysis, Water, Corrosion, Pumps, Heat treating (Metalworking), Spectroscopy, Stainless steel

Proceedings Papers

In-Service Inspection Technology Research on CANOPY Seal Weld of Control Rod Drive Mechanism in PWR

Zhou Lifeng, Cheng Zhaoyu, Cai Jiafan, Tang Yi

Paper No: ICONE25-66999

DOI: https://doi.org/10.1115/ICONE25-66999

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Topics: In-service inspection, Pressurized water reactors, Fracture (Materials), Inspection, ASME Standards, Failure, Probes, Signals, Testing, Water

Proceedings Papers

Data Compiling and Analysis of Oxide Film Growth on Nickel-Base Alloys in High Temperature Water

Xiangkun Ru, Zhanpeng Lu, Junjie Chen, Hao Peng, Qi Xiong, Jiarong Ma

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A090, July 2–6, 2017

Paper No: ICONE25-67254

DOI: https://doi.org/10.1115/ICONE25-67254

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Topics: Alloys, High temperature, Nickel, Water, Indium alloys, Iron, Film thickness, Fittings, Hydrogen, Oxidation

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

Stress Corrosion Behaviors of Three Typical Materials (304L, 2205, Alloy 825) in Boiling Magnesium Chloride Solution

Liang Zhao, Kunjie Luo

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A060, July 2–6, 2017

Paper No: ICONE25-66711

DOI: https://doi.org/10.1115/ICONE25-66711

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Topics: Alloys, Boiling, Magnesium (Metal), Stress corrosion cracking, Stainless steel, Corrosion, Corrosion resistance, Steel, Temperature

NARROW

Effect of Surface Machining on Stress Corrosion Cracking Sensitivity of 304L and 316L Austenite Stainless Steel

Prediction and Uncertainty Analysis of Stress Corrosion Fraction Failure Probability for Pressurized Water Reactor Materials

Study on Ultrasonic Inspection Technology of Fastening Bolts of Reactor Internals

Study of Iodine-Induced Stress Corrosion Cracking of CZ2 Alloy

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

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

Optimizing Material/Component Fabrication Processing for Improving Service Performance in Nuclear Power Plant Coolants

Evaluations of TiO 2 Deposition on Structure Surfaces and Water Radiolysis for the Corrosive Environment in a Reactor Pressure Vessel

Evaluations of TiO 2 Deposition on Structure Surfaces and Water Radiolysis for the Corrosive Environment in a Reactor Pressure Vessel

Development of a Device for Detecting Helium Leaks From Canisters: Part 2 — Numerical Analysis of Temperature Behavior During Gas Leaks From a Canister of a 1/4.5 Scale Cask Model

Development of Device for Detecting Helium Leak From Canister: Part 1 — Experiment on Temperature Behavior During Gas Leak From Canister of 1/4.5 Scale Cask Model

Machine GTAW Ambient Temperature Temper Bead Technique for Ni-Based Weld Overlay Repairs of Nuclear Components: Assessment of Hydrogen Cracking by Implant Test

Root Cause Analysis of a Leak Off Tube of the Primary Loop in a CANDU 6 Unit

Stress Improvement by Laser Peening in the Air

The Research on Ultrasonic Testing Technology for Bottom Part of Reactor Pressure Vessel

The Root Cause Analysis of the Bolt Fracture in the Nuclear Power Plant Essential Service Water System

In-Service Inspection Technology Research on CANOPY Seal Weld of Control Rod Drive Mechanism in PWR

Data Compiling and Analysis of Oxide Film Growth on Nickel-Base Alloys in High Temperature Water

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

Stress Corrosion Behaviors of Three Typical Materials (304L, 2205, Alloy 825) in Boiling Magnesium Chloride Solution

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