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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
DOI: https://doi.org/10.1115/ICONE28-66591
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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
DOI: https://doi.org/10.1115/ICONE28-63770
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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
DOI: https://doi.org/10.1115/ICONE26-81665
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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
DOI: https://doi.org/10.1115/ICONE26-82381
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Topics: Nuclear fuels, Temperature, Electrical conductance, Fuels, Materials properties, Cracking (Materials), Creep, Databases, Fracture (Process), Fuel rods
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

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
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

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
DOI: https://doi.org/10.1115/ICONE25-67301
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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
DOI: https://doi.org/10.1115/ICONE25-67314
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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
DOI: https://doi.org/10.1115/ICONE25-67779
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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
DOI: https://doi.org/10.1115/ICONE25-67410
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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
DOI: https://doi.org/10.1115/ICONE25-67478
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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
DOI: https://doi.org/10.1115/ICONE25-66022
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Topics: Fluid structure interaction, Fluids, Nuclear power stations, Pipes, Simulation, Stress, Boiling water reactors, Cracking (Materials), Deformation, Flow (Dynamics)
Proceedings Papers

AP1000 ® Submergence Testing of Service Level I Protective Coatings

Matthew R. Beenken, Christina L. Rocco, Timothy S. Andreychek
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, V001T03A012, June 26–30, 2016
Paper No: ICONE24-60228
DOI: https://doi.org/10.1115/ICONE24-60228
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Topics: Protective coatings, Testing, Coatings, Containment, Temperature, Accidents, Coolants, Design, Fluids, Pressure
Proceedings Papers

Numerical and Theoretical Study on Parameter Selection of Acoustic Load Test of Steam Dryer

Jia Zhong, Han Wang, Nan Wang, Jinyi Zhang, Yujia Liu, Wen Liu, Kai Zhang
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A079, June 26–30, 2016
Paper No: ICONE24-61023
DOI: https://doi.org/10.1115/ICONE24-61023
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Topics: Sound pressure, Steam, Acoustics, Pipes, Resonance, Flow (Dynamics), Cracking (Materials), Engineering prototypes, Failure, Fracture (Process)
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
DOI: https://doi.org/10.1115/ICONE24-61106
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Topics: Foundry coatings, Quality control, Hardening, Wear, Erosion, Stress, Cobalt, Contamination, Corrosion resistance, Crack propagation
Proceedings Papers

Long Term Operation Issues for Electrical Cable Systems in Nuclear Power Plants

Leonard S. Fifield, Robert Duckworth, Samuel W. Glass, III
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, V002T05A008, June 26–30, 2016
Paper No: ICONE24-60729
DOI: https://doi.org/10.1115/ICONE24-60729
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Topics: Cables, Nuclear power stations, Insulation, Damage, Design, Heat, Licensing, Polymers, Radiation (Physics), Temperature
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
DOI: https://doi.org/10.1115/ICONE24-60267
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Topics: Cooling, Fuel storage, Safety, Water, Temperature, Containment, Cooling systems, Spent nuclear fuels, Concretes, Cracking (Materials)
Proceedings Papers

Computational Analyses of the Thermal Stress Induced by Coolant Mixing in a T-Joint

K. G. F. Janssens, M. Niffenegger, M. Sharabi
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, V001T02A005, July 7–11, 2014
Paper No: ICONE22-30218
DOI: https://doi.org/10.1115/ICONE22-30218
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Topics: Coolants, Thermal stresses, Boundary-value problems, Engineering simulation, Finite element analysis, Flow (Dynamics), Low cycle fatigue, Simulation, Computational fluid dynamics, Cracking (Materials)
Proceedings Papers

Modelling of the Impact of Local Effects on Fuel-Cladding Interaction During Power Ramp

Jan Klouzal, Martin Dostál
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, V001T02A016, July 7–11, 2014
Paper No: ICONE22-30807
DOI: https://doi.org/10.1115/ICONE22-30807
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Topics: Cladding systems (Building), Fuels, Modeling, Cracking (Materials), Design, Failure, Fracture (Process), Heat, Heat transfer, Manufacturing
Proceedings Papers

Cost Saving When Using Enhanced Conductivity Nuclear Fuel Containing BeO in WWER-1000 Reactors

Tomáš Zahrádka, Radek Škoda
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, V001T01A019, July 7–11, 2014
Paper No: ICONE22-30901
DOI: https://doi.org/10.1115/ICONE22-30901
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Topics: Nuclear fuels, Thermal conductivity, Fuels, Temperature, Corporate average fuel economy, Cracking (Materials), Fracture (Process), Fuel efficiency, Gases, Geometry