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Proceedings Papers

Effect Of The Mean Temperature of Storage Site on Chloride-Induced Stress Corrosion Cracking Rate in ASME Code Case N-860: Case Study

Jae-Yoon Jeong, Yun-Jae Kim, Poh-Sang Lam, Seunghyun Kim, Gi-Dong Kim

Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A051, July 17–22, 2022

Paper No: PVP2022-83766

DOI: https://doi.org/10.1115/PVP2022-83766

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Topics: ASME Standards, Fracture (Materials), Storage, Stress corrosion cracking, Temperature

Journal Articles

Nondestructive Evaluation of Stress Corrosion Cracking in a Welded Steel Plate Using Guided Ultrasonic Waves

Zhaoyun Ma, Lingyu Yu, Yuh J. Chao, Poh-Sang Lam, Robert L. Sindelar, Andrew J. Duncan, Thanh-Tam Truong, Christopher Verst, Pei-Kang Sun, Andrew Campbell

ASME J Nondestructive Evaluation. August 2022, 5(3): 031003.

Paper No: NDE-21-1032

DOI: https://doi.org/10.1115/1.4053653

Published Online: March 1, 2022

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Topics: Fracture (Materials), Imaging, Inspection, Nondestructive evaluation, Stress corrosion cracking, Ultrasonic waves, Waves, Steel, Finite element analysis

Proceedings Papers

Investigation of Chloride-Induced Stress Corrosion Cracking for AISI 304/304L Stainless Steel Using Notched Bar Specimens

Jae-Yoon Jeong, Yun-Jae Kim, Poh-Sang Lam, Andrew Duncan, Myeong-Woo Lee

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A106, August 3, 2020

Paper No: PVP2020-21399

DOI: https://doi.org/10.1115/PVP2020-21399

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Topics: Corrosion, Spent nuclear fuels, Stainless steel, Stress corrosion cracking

Proceedings Papers

CISCC Experiment of a Large Plate Sectioned From a Spent Nuclear Fuel Canister

Andrew J. Duncan, Poh-Sang Lam, Robert L. Sindelar

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A108, August 3, 2020

Paper No: PVP2020-21774

DOI: https://doi.org/10.1115/PVP2020-21774

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Topics: Deliquescence, Fracture (Materials), Spent nuclear fuels, Stress, Stress corrosion cracking, Welding, Electrical discharge machining, Corrosion, Stainless steel, Temperature

Proceedings Papers

Ultrasonic Nondestructive Evaluation of Stress Corrosion Crack in Welded Steel Plate

Zhaoyun Ma, Lingyu Yu, Poh-Sang Lam, Robert L. Sindelar, Andrew J. Duncan, Thanh-Tam Truong, Yuh J. Chao

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A021, August 3, 2020

Paper No: PVP2020-21794

DOI: https://doi.org/10.1115/PVP2020-21794

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Topics: Imaging, Nondestructive evaluation, Radioactive wastes, Steel, Stress corrosion cracking

Journal Articles

Does the Biaxial Loading Affect the Apparent Fracture Toughness ( K C )?

Chentong Chen, Hanbin Xiao, Yuh J. Chao, Poh-Sang Lam

J. Pressure Vessel Technol. June 2020, 142(3): 031503.

Paper No: PVT-19-1061

DOI: https://doi.org/10.1115/1.4045675

Published Online: March 18, 2020

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Topics: Fracture (Materials), Fracture toughness, Stress, Displacement

Proceedings Papers

Does the Biaxial Loading Affect the Apparent Fracture Toughness ( K c )?

Chentong Chen, Hanbin Xiao, Yuh J. Chao, Poh-Sang Lam

Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A021, July 14–19, 2019

Paper No: PVP2019-94002

DOI: https://doi.org/10.1115/PVP2019-94002

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Topics: Finite element methods, Fracture (Materials), Fracture mechanics, Fracture toughness, Stress, Geometry

Proceedings Papers

Engineering J Estimates for Spent Fuel Canisters Under Combined Mechanical and Welding Residual Stresses

Hyun-Jae Lee, Yun-Jae Kim, Poh-Sang Lam, Robert L. Sindelar

Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A052, July 14–19, 2019

Paper No: PVP2019-93936

DOI: https://doi.org/10.1115/PVP2019-93936

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Topics: Residual stresses, Spent nuclear fuels, Welding, Stress, Finite element analysis, Fracture (Materials), Fracture (Process)

Proceedings Papers

Crack Growth Rate Testing and Large Plate Demonstration Under Chloride-Induced Stress Corrosion Cracking Conditions in Stainless Steel Canisters for Storage of Spent Nuclear Fuel

Poh-Sang Lam, Andrew J. Duncan, Lisa N. Ward, Robert L. Sindelar, Yun-Jae Kim, Jae-Yoon Jeong, Hyun-Jae Lee, Myeong Woo Lee

Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A053, July 14–19, 2019

Paper No: PVP2019-94031

DOI: https://doi.org/10.1115/PVP2019-94031

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Topics: Fracture (Materials), Spent nuclear fuels, Stainless steel, Storage, Stress, Stress corrosion cracking, Testing, Welding

Proceedings Papers

Crack Growth Rate Model for CISCC of Stainless Steel Canisters

John E. Broussard, III, Charles Bryan, Robert Sindelar, Poh-Sang Lam

Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A054, July 14–19, 2019

Paper No: PVP2019-94055

DOI: https://doi.org/10.1115/PVP2019-94055

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Topics: Fracture (Materials), Stainless steel, Stress corrosion cracking, Tension, Aerosols, ASME Boiler and Pressure Vessel Code, Cracking (Materials), Deliquescence, Fracture (Process), Spent nuclear fuels

Proceedings Papers

Crack Growth Rate Testing of Bolt-Load Compact Tension Specimens Under Chloride-Induced Stress Corrosion Cracking Conditions in Spent Nuclear Fuel Canisters

Andrew J. Duncan, Poh-Sang Lam, Robert L. Sindelar, Kathryn E. Metzger

Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A068, July 15–20, 2018

Paper No: PVP2018-84753

DOI: https://doi.org/10.1115/PVP2018-84753

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Topics: Fracture (Materials), Spent nuclear fuels, Stress, Stress corrosion cracking, Tension, Testing, Temperature, ASTM International, Seas, Bearings

Proceedings Papers

FE Welding Residual Stress Analysis and Validation for Spent Nuclear Fuel Canisiters

Jae-Min Gim, Ji-Soo Kim, Yun-Jae Kim, Poh-Sang Lam

Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A069, July 15–20, 2018

Paper No: PVP2018-84857

DOI: https://doi.org/10.1115/PVP2018-84857

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Topics: Spent nuclear fuels, Stress analysis (Engineering), Welding, Finite element analysis, Fracture (Materials), Heat, Heat treating (Metalworking), Residual stresses, Stainless steel, Stress

Proceedings Papers

Progress Report on Stress Intensity Factor and J-Integral Estimation for Nuclear Fuel Canisters Under Mechanical Loading

Ji-Su Kim, Jae-Min Gim, Yun-Jae Kim, Poh-Sang Lam

Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A070, July 15–20, 2018

Paper No: PVP2018-84966

DOI: https://doi.org/10.1115/PVP2018-84966

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Topics: Nuclear fuels, Stress, Fracture (Materials), American Petroleum Institute, Finite element analysis, Fracture mechanics, Spent nuclear fuels, Surface cracks, Welding

Proceedings Papers

Engineering J Estimation Equations for Spent Fuel Canisters Under Combined Mechanical and Welding Residual Stresses

Hyun-Jae Lee, Jae-Yoon Jeong, Yun-Jae Kim, Poh-Sang Lam

Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A071, July 15–20, 2018

Paper No: PVP2018-85076

DOI: https://doi.org/10.1115/PVP2018-85076

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Topics: Residual stresses, Spent nuclear fuels, Welding, Stress, Finite element analysis

Proceedings Papers

Modeling of Crack Extensions in Arc-Shaped Specimens of Hydrogen-Charged Austenitic Stainless Steels Using Cohesive Zone Model

Shengjia Wu, Shin-Jang Sung, Jwo Pan, Poh-Sang Lam, Michael J. Morgan, Paul S. Korinko

Proc. ASME. PVP2018, Volume 6A: Materials and Fabrication, V06AT06A020, July 15–20, 2018

Paper No: PVP2018-84919

DOI: https://doi.org/10.1115/PVP2018-84919

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Topics: Fracture (Materials), Hydrogen, Modeling, Stainless steel, Steel, Stress, Displacement, Finite element analysis, Fittings, Separation (Technology)

Proceedings Papers

A Compendium of Mechanical Testing of Austenitic Stainless Steels in Hydrogen

Poh-Sang Lam, Andrew J. Duncan, Michael J. Morgan, Robert L. Sindelar, Thad M. Adams

Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A040, July 15–20, 2018

Paper No: PVP2018-84723

DOI: https://doi.org/10.1115/PVP2018-84723

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Topics: Hydrogen, Mechanical testing, Stainless steel, Ductility, Grain size, Nickel, Rivers, High pressure (Physics), Alloys, Elongation

Journal Articles

Effects of Gamma Radiation on Resonant and Antiresonant Characteristics of Piezoelectric Wafer Active Sensors

Mohammad Faisal Haider, Victor Giurgiutiu, Bin Lin, Lingyu Yu, Poh-Sang Lam, Christopher Verst

ASME J Nondestructive Evaluation. February 2019, 2(1): 011001–011001-12.

Paper No: NDE-18-1010

DOI: https://doi.org/10.1115/1.4041068

Published Online: September 17, 2018

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Topics: Gamma rays, Irradiation (Radiation exposure), Mechanical admittance, Radiation (Physics), Resonance, Semiconductor wafers, Sensors, Transducers, Capacitance, Structural health monitoring

Proceedings Papers

Crack Extensions in Compact Tension Specimens of Hydrided Irradiated Zr-2.5Nb Materials Using Cohesive Zone Model

Shengjia Wu, Shin-Jang Sung, Jwo Pan, Poh-Sang Lam, Douglas A. Scarth

Proc. ASME. PVP2017, Volume 6A: Materials and Fabrication, V06AT06A025, July 16–20, 2017

Paper No: PVP2017-65022

DOI: https://doi.org/10.1115/PVP2017-65022

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Topics: Fracture (Materials), Tension, Zirconium, Finite element analysis, Stress, Displacement, Fittings, Calibration, Separation (Technology), Stress-strain curves

Proceedings Papers

Elastic-Plastic Fracture Analysis of a Reactor Pressure Vessel Subjected to Pressurized Thermal Shock

Huajing Guo, Zhongxian Wang, Poh-Sang Lam

Proc. ASME. PVP2017, Volume 6A: Materials and Fabrication, V06AT06A042, July 16–20, 2017

Paper No: PVP2017-66221

DOI: https://doi.org/10.1115/PVP2017-66221

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Topics: Fracture (Materials), Reactor vessels, Thermal shock, Failure, Finite element model, Surface cracks, Temperature

Proceedings Papers

Fracture Initiation in Compact Tension Specimens of Hydrided Irradiated Zr-2.5Nb Materials With Split Circumferential Hydrides

Shin-Jang Sung, Jwo Pan, Poh-Sang Lam, Douglas A. Scarth

Proc. ASME. PVP2017, Volume 6A: Materials and Fabrication, V06AT06A036, July 16–20, 2017

Paper No: PVP2017-66051

DOI: https://doi.org/10.1115/PVP2017-66051

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Topics: Fracture (Materials), Tension, Zirconium, Fracture (Process), Stress, Failure, Finite element analysis, Fracture toughness, Stress-strain relations, Temperature

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Journal citation

NARROW

Effect Of The Mean Temperature of Storage Site on Chloride-Induced Stress Corrosion Cracking Rate in ASME Code Case N-860: Case Study

Nondestructive Evaluation of Stress Corrosion Cracking in a Welded Steel Plate Using Guided Ultrasonic Waves

Investigation of Chloride-Induced Stress Corrosion Cracking for AISI 304/304L Stainless Steel Using Notched Bar Specimens

CISCC Experiment of a Large Plate Sectioned From a Spent Nuclear Fuel Canister

Ultrasonic Nondestructive Evaluation of Stress Corrosion Crack in Welded Steel Plate

Does the Biaxial Loading Affect the Apparent Fracture Toughness ( K C )?

Does the Biaxial Loading Affect the Apparent Fracture Toughness ( K c )?

Engineering J Estimates for Spent Fuel Canisters Under Combined Mechanical and Welding Residual Stresses

Crack Growth Rate Testing and Large Plate Demonstration Under Chloride-Induced Stress Corrosion Cracking Conditions in Stainless Steel Canisters for Storage of Spent Nuclear Fuel

Crack Growth Rate Model for CISCC of Stainless Steel Canisters

Crack Growth Rate Testing of Bolt-Load Compact Tension Specimens Under Chloride-Induced Stress Corrosion Cracking Conditions in Spent Nuclear Fuel Canisters

FE Welding Residual Stress Analysis and Validation for Spent Nuclear Fuel Canisiters

Progress Report on Stress Intensity Factor and J-Integral Estimation for Nuclear Fuel Canisters Under Mechanical Loading

Engineering J Estimation Equations for Spent Fuel Canisters Under Combined Mechanical and Welding Residual Stresses

Modeling of Crack Extensions in Arc-Shaped Specimens of Hydrogen-Charged Austenitic Stainless Steels Using Cohesive Zone Model

A Compendium of Mechanical Testing of Austenitic Stainless Steels in Hydrogen

Effects of Gamma Radiation on Resonant and Antiresonant Characteristics of Piezoelectric Wafer Active Sensors

Crack Extensions in Compact Tension Specimens of Hydrided Irradiated Zr-2.5Nb Materials Using Cohesive Zone Model

Elastic-Plastic Fracture Analysis of a Reactor Pressure Vessel Subjected to Pressurized Thermal Shock

Fracture Initiation in Compact Tension Specimens of Hydrided Irradiated Zr-2.5Nb Materials With Split Circumferential Hydrides

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