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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

Corrosion Susceptibility in High Temperature Liquid/Vapor Environments of Materials for Tubing of Heavy-Water Collection System in CANDU Nuclear Power Plant

Guangfu Li, Liang Zhao, Xinghong Yang

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A086, July 2–6, 2017

Paper No: ICONE25-67218

DOI: https://doi.org/10.1115/ICONE25-67218

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Topics: Corrosion, High temperature, Nuclear power stations, Tubing, Vapors, Water, Stainless steel, Temperature, Alloys, Carbon steel

Proceedings Papers

The Current Status of CANDU Steam Generators

Matthew Naraine, Jovica Riznic

Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A001, July 2–6, 2017

Paper No: ICONE25-66001

DOI: https://doi.org/10.1115/ICONE25-66001

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Topics: Boilers, Chemistry, Design, Pressurized water reactors, Tubing, Carbon steel, Collaboration, Databases, Failure mechanisms, Industrial research

Proceedings Papers

Performance Experienced From Switching Copper Condenser Tubing to a High Performance Stainless

Summer Goebel, Colin R. Criminger

Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 783-791, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54828

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54828

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Topics: Condensers (steam plant), Copper, Tubing, Cooling towers, Rivers, Alloys, Coal, Leakage, Nickel, Pollution

Proceedings Papers

Experiments on Choking Flow of Subcooled Liquid Through a Simulated Steam Generator Tube Crack

Brian Wolf, Shripad T. Revankar, Jovica R. Riznic

Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 41-50, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54080

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54080

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Topics: Boilers, Flow (Dynamics), Fracture (Materials), Subcooling, Flashing, Lasers, Leakage, Leak-before-break, Pressure, Tubing

Proceedings Papers

An Addendum: Probabilistic Failure Analysis of a Residual Heat Removal Heat Exchanger During Postulated Loss of Coolant Accident

Matt Solom, Christopher Pannier, Christopher Chance, Robert Seager, Alan Lee, Jordan Green, Tam Duong, Paola Alicea

Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 343-347, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54636

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54636

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Topics: Accidents, Coolants, Failure analysis, Heat, Heat exchangers, Failure, Probability, Simulation, Flow (Dynamics), FORTRAN

Proceedings Papers

Effect of Hazardous Impurities on Steam Generator Tube Degradation

Yucheng Lu

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 283-291, May 17–21, 2010

Paper No: ICONE18-30120

DOI: https://doi.org/10.1115/ICONE18-30120

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Topics: Boilers, Alloys, Corrosion, Chemistry, Tubing, Copper, Electrolytic corrosion, Materials degradation, Boundary-value problems, Contamination

Proceedings Papers

Actual Problems of VVER SG Tubing Service Life Management

N. B. Trunov, V. S. Popadchuk, S. E. Davidenko, R. Ju. Zhukov

Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 29-36, July 12–16, 2009

Paper No: ICONE17-75096

DOI: https://doi.org/10.1115/ICONE17-75096

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Topics: Service life (Equipment), Tubing, Corrosion, Boilers, Engineering prototypes, Heat, Inspection, Nuclear power stations, Optimization, Pressure

Proceedings Papers

Residual Life Assessment of Steam Generators With Alloy 600TT Tubing: Methods and Application

Ian de Curieres, Marie-Christine Meunier, Pierre Joly

Paper No: ICONE17-75272

DOI: https://doi.org/10.1115/ICONE17-75272

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Topics: Alloys, Boilers, Tubing, Damage, Inspection, Cracking (Materials), Fracture (Materials), Fracture (Process)

Proceedings Papers

Degradation of Alloy 800 Under Steam Generator Secondary Side Crevice Conditions

Y. C. Lu, G. Goszczynski, S. Ramamurthy

Paper No: ICONE17-75695

DOI: https://doi.org/10.1115/ICONE17-75695

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Topics: Alloys, Boilers, Tubing, Chemistry, Pressurized water reactors, Corrosion, Cracking (Materials), Electrochemical analysis, Electrodes, Fracture (Process)

Proceedings Papers

Analyses of the Failed Impulsion Lines of NPP Dukovany Steam Generator

M. Postler, J. Burda, P. Tkadlcˇi´k

Paper No: ICONE17-75928

DOI: https://doi.org/10.1115/ICONE17-75928

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Topics: Boilers, Nuclear power stations, Leakage, Tubing, Containment, Deformation, Failure, Fracture (Materials), Manufacturing, Stainless steel

Proceedings Papers

FFS Issues for Steam Generator Tube (Top of Tubesheet) Intergranular Attack/Stress Corrosion Cracking

David Durance, Ken Sedman, John Roberts, Jeff Gorman

Paper No: ICONE17-75599

DOI: https://doi.org/10.1115/ICONE17-75599

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Topics: Boilers, Fitness-for-service, Stress corrosion cracking, Springs, Sulfur, Damage, Low temperature, Maintenance, Oxygen, Tubing

Proceedings Papers

Computational Fluid Dynamics Modeling of PWR Steam Generator Sludge Collector/Loose Parts Weir

Chunyun Wang, Jason Burr, Naeem Karim

Proc. ASME. ICONE17, Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 671-677, July 12–16, 2009

Paper No: ICONE17-75816

DOI: https://doi.org/10.1115/ICONE17-75816

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Topics: Boilers, Computational fluid dynamics, Modeling, Pressurized water reactors, Flow (Dynamics), Particulate matter, Computers, Design, Feedwater, Fluids

Proceedings Papers

Corrosion Behaviour of Steels in Lead-Bismuth Eutectic (LBE) in the LINCE Loop Up to 5000 h

F. J. Marti´n-Mun˜oz, L. Soler-Crespo, D. Go´mez-Bricen˜o

Paper No: ICONE17-76011

DOI: https://doi.org/10.1115/ICONE17-76011

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Topics: Corrosion, Steel, Coolants, Oxygen, Temperature, Weight (Mass), Centrifugal pumps, Control systems, Design, Electricity (Physics)

Proceedings Papers

The Effect of Inspection Uncertainties in Predicting the Probability of Leak of Steam Generator Tubing Due to Pitting

M. D. Pandey, S. V. Datta, D. Komljenovic

Proc. ASME. ICONE16, Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues, 685-693, May 11–15, 2008

Paper No: ICONE16-48729

DOI: https://doi.org/10.1115/ICONE16-48729

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Topics: Boilers, Inspection, Leakage, Probability, Tubing, Uncertainty, Accounting, Corrosion, Eddies (Fluid dynamics), Eddy currents (Electricity)

Proceedings Papers

Stress Rupture Characteristics of Zirconium Alloy Cladding Under Closed-End Internal Pressurization

B. Marple, Y. J. Song, S. Gollapudi, K. L. Murty, I. Charit

Paper No: ICONE16-48006

DOI: https://doi.org/10.1115/ICONE16-48006

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Topics: Cladding systems (Building), Rupture, Stress, Zirconium alloys, Creep, Alloys, Deformation, Elongation, Nuclear reactors, Temperature

Proceedings Papers

Rupture and Internal Pressurization Creep of Nb-Modified Zircalloy-4 Tubing: Application to Dry Storage Feasibility

K. K. Murty, Y. Zhou, B. Devarajan

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 291-296, April 14–18, 2002

Paper No: ICONE10-22153

DOI: https://doi.org/10.1115/ICONE10-22153

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Topics: Creep, Rupture, Storage, Tubing, Stress, Alloys, Cladding systems (Building), Corrosion, Failure mechanisms, Heat

Proceedings Papers

In-Situ Pressure Testing of Steam Generator Tubes

Cordelia K. Chandler

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 261-266, April 14–18, 2002

Paper No: ICONE10-22191

DOI: https://doi.org/10.1115/ICONE10-22191

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Topics: Boilers, Pressure testing, Leakage, Condition monitoring, Testing, Tubing, Cycles, Damage, Eddy current testing, Flow measurement

Proceedings Papers

Evaluation of NDE Round-Robin Exercises Using the NRC Steam Generator Mockup at Argonne National Laboratory

Joseph Muscara, David S. Kupperman, Sasan Bakhtiari, Jang-Yul Park, William J. Shack

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 321-329, April 14–18, 2002

Paper No: ICONE10-22464

DOI: https://doi.org/10.1115/ICONE10-22464

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Topics: Boilers, Nondestructive evaluation, Fracture (Materials), Probes, Eddies (Fluid dynamics), Eddy currents (Electricity), Engineering simulation, Errors, Reliability, Simulation

Proceedings Papers

A Review of Alloy 600 Cracking in Operating Nuclear Plants Including Alloy 82 and 182 Weld Behavior

Warren Bamford, John Hall

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 131-139, April 25–29, 2004

Paper No: ICONE12-49520

DOI: https://doi.org/10.1115/ICONE12-49520

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Topics: Alloys, Cracking (Materials), Fracture (Process), Nuclear power stations, Base metals, Fracture (Materials), Pipes, Boilers, Metals, Reactor vessels

NARROW

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

Corrosion Susceptibility in High Temperature Liquid/Vapor Environments of Materials for Tubing of Heavy-Water Collection System in CANDU Nuclear Power Plant

The Current Status of CANDU Steam Generators

Performance Experienced From Switching Copper Condenser Tubing to a High Performance Stainless

Experiments on Choking Flow of Subcooled Liquid Through a Simulated Steam Generator Tube Crack

An Addendum: Probabilistic Failure Analysis of a Residual Heat Removal Heat Exchanger During Postulated Loss of Coolant Accident

Effect of Hazardous Impurities on Steam Generator Tube Degradation

Actual Problems of VVER SG Tubing Service Life Management

Residual Life Assessment of Steam Generators With Alloy 600TT Tubing: Methods and Application

Degradation of Alloy 800 Under Steam Generator Secondary Side Crevice Conditions

Analyses of the Failed Impulsion Lines of NPP Dukovany Steam Generator

FFS Issues for Steam Generator Tube (Top of Tubesheet) Intergranular Attack/Stress Corrosion Cracking

Computational Fluid Dynamics Modeling of PWR Steam Generator Sludge Collector/Loose Parts Weir

Corrosion Behaviour of Steels in Lead-Bismuth Eutectic (LBE) in the LINCE Loop Up to 5000 h

The Effect of Inspection Uncertainties in Predicting the Probability of Leak of Steam Generator Tubing Due to Pitting

Stress Rupture Characteristics of Zirconium Alloy Cladding Under Closed-End Internal Pressurization

Rupture and Internal Pressurization Creep of Nb-Modified Zircalloy-4 Tubing: Application to Dry Storage Feasibility

In-Situ Pressure Testing of Steam Generator Tubes

Evaluation of NDE Round-Robin Exercises Using the NRC Steam Generator Mockup at Argonne National Laboratory

A Review of Alloy 600 Cracking in Operating Nuclear Plants Including Alloy 82 and 182 Weld Behavior

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