1-20 of 64
Cracking (Materials)
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

The Effect of Nozzle Safe End Hot/Cold Wire Tungsten Inert Gas Buttering on Microstructure and Property

Chengdong Yang, Maolong Zhang, Xiangkun Ru, Weibao Tang
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A002, August 8–12, 2022
Paper No: ICONE29-89075
https://doi.org/10.1115/ICONE29-89075
View Paper titled, The Effect of Nozzle Safe End Hot/Cold Wire Tungsten Inert Gas Buttering on Microstructure and Property
Open the PDF for The Effect of Nozzle Safe End Hot/Cold Wire Tungsten Inert Gas Buttering on Microstructure and Property in another window
Topics: Cracking (Materials), Ductility, Fracture (Process), Nozzles, Tungsten, Wire, Grain boundaries, Grain size
Proceedings Papers

Evaluation on Weldability of Nickel-Base Alloy Weld Materials With High Chromium Content

Yoshinori Katayama, Takahiro Hayashi, Daiki Tanaka, Hidenori Takahashi
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A003, August 8–12, 2022
Paper No: ICONE29-89096
https://doi.org/10.1115/ICONE29-89096
View Paper titled, Evaluation on Weldability of Nickel-Base Alloy Weld Materials With High Chromium Content
Open the PDF for Evaluation on Weldability of Nickel-Base Alloy Weld Materials With High Chromium Content in another window
Topics: Alloys, Cracking (Materials), Ductility, Fracture (Process), Nickel, Solidification
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
https://doi.org/10.1115/ICONE29-92321
View Paper titled, Optimizing Material/Component Fabrication Processing for Improving Service Performance in Nuclear Power Plant Coolants
Open the PDF for Optimizing Material/Component Fabrication Processing for Improving Service Performance in Nuclear Power Plant Coolants in another window
Topics: Coolants, Cracking (Materials), Fracture (Process), Manufacturing, Nuclear power stations, Pressurized water reactors, Stress corrosion cracking
Proceedings Papers

Comparative Study on Creep-Fatigue Damage Assessment Between R5 Procedures and a Full Inelastic Analysis

Antony M. Hurst, Louis C. W. Chang, Nak-Kyun Cho
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A008, August 8–12, 2022
Paper No: ICONE29-91707
https://doi.org/10.1115/ICONE29-91707
View Paper titled, Comparative Study on Creep-Fatigue Damage Assessment Between R5 Procedures and a Full Inelastic Analysis
Open the PDF for Comparative Study on Creep-Fatigue Damage Assessment Between R5 Procedures and a Full Inelastic Analysis in another window
Topics: Creep, Damage assessment, Fatigue, Inelastic analysis, Stress, Damage, Elastic analysis, Cracking (Materials), Fracture (Process), Geometry
Proceedings Papers

Research on Cracked Fuel Relocation of Dual-Cooled Annular Fuel Element Under Normal and LOCA Conditions

Yangbin Deng, Yuan Yin
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A022, August 8–12, 2022
Paper No: ICONE29-90755
https://doi.org/10.1115/ICONE29-90755
View Paper titled, Research on Cracked Fuel Relocation of Dual-Cooled Annular Fuel Element Under Normal and LOCA Conditions
Open the PDF for Research on Cracked Fuel Relocation of Dual-Cooled Annular Fuel Element Under Normal and LOCA Conditions in another window
Topics: Cracking (Materials), Discrete element methods, Fracture (Process), Fuels
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
https://doi.org/10.1115/ICONE29-92656
View Paper titled, Numerical Study of the Effect of δ-Ferrite on Crack-Tip Mechanical Field
Open the PDF for Numerical Study of the Effect of δ-Ferrite on Crack-Tip Mechanical Field in another window
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

Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development

Guoqiang Wang, William A. Byers, Zeses Karoutas
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A041, August 4–6, 2021
Paper No: ICONE28-66591
https://doi.org/10.1115/ICONE28-66591
View Paper titled, Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development
Open the PDF for Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development in another window
Topics: Accidents, Cladding systems (Building), Critical heat flux, Fuels, Chemistry, Pressurized water reactors, Coolants, Electrical resistivity, Film boiling, Heat flux
Proceedings Papers

Investigation on Solidification Behavior of Deposited Metal by GTAW With ERNiCrFe-13 Wire

Xiao Guo, Kai Xu, Xiaochun Lv, Peiyin Chen, Bo Chen, Shubin Huo
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T10A001, August 4–6, 2021
Paper No: ICONE28-63770
https://doi.org/10.1115/ICONE28-63770
View Paper titled, Investigation on Solidification Behavior of Deposited Metal by GTAW With ERNiCrFe-13 Wire
Open the PDF for Investigation on Solidification Behavior of Deposited Metal by GTAW With ERNiCrFe-13 Wire in another window
Topics: Gas tungsten arc welding, Metals, Solidification, Wire, Temperature, Cracking (Materials), Fracture (Process), Differential scanning calorimetry, Ductility, Lasers
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
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
Open the PDF for A Theoretical Model of the Stress Intensity Factor Threshold of DHC for Fuel Cladding Tube in another window
Topics: Cladding systems (Building), Fuels, Stress, Temperature, Fracture (Materials), Temperature gradient, Cracking (Materials), Diffusion (Physics), Fracture (Process), Hydrogen
Proceedings Papers

First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM

Alessandro Scolaro, Ivor Clifford, Carlo Fiorina, Andreas Pautz
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A051, July 22–26, 2018
Paper No: ICONE26-82381
https://doi.org/10.1115/ICONE26-82381
View Paper titled, First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM
Open the PDF for First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM in another window
Topics: Nuclear fuels, Temperature, Electrical conductance, Fuels, Materials properties, Cracking (Materials), Creep, Databases, Fracture (Process), Fuel rods
Proceedings Papers

Case Study Analyses of Flaw Growth and Tolerance of Stainless Steel Canisters in Marine Environment

Chang Heui-Yung
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A094, July 2–6, 2017
Paper No: ICONE25-67301
https://doi.org/10.1115/ICONE25-67301
View Paper titled, Case Study Analyses of Flaw Growth and Tolerance of Stainless Steel Canisters in Marine Environment
Open the PDF for Case Study Analyses of Flaw Growth and Tolerance of Stainless Steel Canisters in Marine Environment in another window
Topics: Stainless steel, Storage, Temperature, Climate, Cracking (Materials), Fracture (Process), Nuclear fuels, Nuclear power stations, Shells, Spent fuel storage
Proceedings Papers

Stress Corrosion Cracking Behavior in Liquid/Vapors of Boiling Magnesium Chloride Solution of 304L/316L/690 for Heavy-Water Collection Tubing in CANDU Nuclear Power Plant

Guangfu Li, Liang Zhao, Xinghong Yang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A095, July 2–6, 2017
Paper No: ICONE25-67314
https://doi.org/10.1115/ICONE25-67314
View Paper titled, Stress Corrosion Cracking Behavior in Liquid/Vapors of Boiling Magnesium Chloride Solution of 304L/316L/690 for Heavy-Water Collection Tubing in CANDU Nuclear Power Plant
Open the PDF for Stress Corrosion Cracking Behavior in Liquid/Vapors of Boiling Magnesium Chloride Solution of 304L/316L/690 for Heavy-Water Collection Tubing in CANDU Nuclear Power Plant in another window
Topics: Boiling, Magnesium (Metal), Nuclear power stations, Stress corrosion cracking, Tubing, Vapors, Water, Cracking (Materials), Fracture (Process), Alloys
Proceedings Papers

Simulation of Behaviors of a One-Third Scale Containment Model Test

Guopeng Ren, Rong Pan, Feng Sun
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A113, July 2–6, 2017
Paper No: ICONE25-67779
https://doi.org/10.1115/ICONE25-67779
View Paper titled, Simulation of Behaviors of a One-Third Scale Containment Model Test
Open the PDF for Simulation of Behaviors of a One-Third Scale Containment Model Test in another window
Topics: Containment, Simulation, Tendons, Concretes, Finite element model, Pressure, Deformation, Nuclear power stations, Design, Safety
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
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
Open the PDF for Simulation of the Delayed Hydride Cracking Velocity for Zirconium Alloy Materials Considering Irradiation Effects in another window
Topics: Cracking (Materials), Irradiation (Radiation exposure), Simulation, Zirconium alloys, Embrittlement, Hardening, Traction, Anisotropy, Boundary-value problems, Computer simulation
Proceedings Papers

Composite Versus Dispersed Accident Tolerant Nuclear Fuels

Jayangani Ranasinghe, Barbara Szpunar, Ericmoore Jossou, Linu Malakkal, Jerzy A. Szpunar
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A056, July 2–6, 2017
Paper No: ICONE25-67478
https://doi.org/10.1115/ICONE25-67478
View Paper titled, Composite Versus Dispersed Accident Tolerant Nuclear Fuels
Open the PDF for Composite Versus Dispersed Accident Tolerant Nuclear Fuels in another window
Topics: Accidents, Composite materials, Nuclear fuels, Fuels, Temperature, Temperature gradient, Thermal conductivity, Aluminum, Approximation, Cracking (Materials)
Proceedings Papers

Fluid Solid Interaction (FSI) Simulation of a Tee Piping in Operating Nuclear Power Plant

Pei-Hsun Huang, Chao-Jen Li
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A002, July 2–6, 2017
Paper No: ICONE25-66022
https://doi.org/10.1115/ICONE25-66022
View Paper titled, Fluid Solid Interaction (FSI) Simulation of a Tee Piping in Operating Nuclear Power Plant
Open the PDF for Fluid Solid Interaction (FSI) Simulation of a Tee Piping in Operating Nuclear Power Plant in another window
Topics: Fluid structure interaction, Fluids, Nuclear power stations, Pipes, Simulation, Stress, Boiling water reactors, Cracking (Materials), Deformation, Flow (Dynamics)
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
https://doi.org/10.1115/ICONE25-67160
View Paper titled, Machine GTAW Ambient Temperature Temper Bead Technique for Ni-Based Weld Overlay Repairs of Nuclear Components: Assessment of Hydrogen Cracking by Implant Test
Open the PDF for Machine GTAW Ambient Temperature Temper Bead Technique for Ni-Based Weld Overlay Repairs of Nuclear Components: Assessment of Hydrogen Cracking by Implant Test in another window
Topics: Gas tungsten arc welding, Hydrogen embrittlement, Machinery, Maintenance, Overlays (Materials engineering), Temperature, Heating, Welding, Cracking (Materials), Fracture (Process)
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
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, V001T01A028, July 2–6, 2017
Paper No: ICONE25-66999
https://doi.org/10.1115/ICONE25-66999
View Paper titled, In-Service Inspection Technology Research on CANOPY Seal Weld of Control Rod Drive Mechanism in PWR
Open the PDF for In-Service Inspection Technology Research on CANOPY Seal Weld of Control Rod Drive Mechanism in PWR in another window
Topics: In-service inspection, Pressurized water reactors, Fracture (Materials), Inspection, ASME Standards, Failure, Probes, Signals, Testing, Water
Proceedings Papers

Safety Assessment of Fuel Storage Ponds Following Cooling Faults

Jonathan Webb, Charles Bridgford
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T07A006, June 26–30, 2016
Paper No: ICONE24-60267
https://doi.org/10.1115/ICONE24-60267
View Paper titled, Safety Assessment of Fuel Storage Ponds Following Cooling Faults
Open the PDF for Safety Assessment of Fuel Storage Ponds Following Cooling Faults in another window
Topics: Cooling, Fuel storage, Safety, Water, Temperature, Containment, Cooling systems, Spent nuclear fuels, Concretes, Cracking (Materials)
Proceedings Papers

HIPed Hard Facings for Nuclear Applications: Materials, Key Potential Defects and Mitigating Quality Control Measures

John Sulley, David Stewart
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, V001T03A034, June 26–30, 2016
Paper No: ICONE24-61106
https://doi.org/10.1115/ICONE24-61106
View Paper titled, HIPed Hard Facings for Nuclear Applications: Materials, Key Potential Defects and Mitigating Quality Control Measures
Open the PDF for HIPed Hard Facings for Nuclear Applications: Materials, Key Potential Defects and Mitigating Quality Control Measures in another window
Topics: Foundry coatings, Quality control, Hardening, Wear, Erosion, Stress, Cobalt, Contamination, Corrosion resistance, Crack propagation