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Chin-Cheng Huang
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Proceedings Papers

Comparison of Pressure-Temperature Limits for a Pressurized Water Reactor Pressure Vessel Considering Beltline and Extended Beltline Regions

Hsoung-Wei Chou, Yu-Yu Shen, Chin-Cheng Huang
Proc. ASME. PVP2018, Volume 6A: Materials and Fabrication, V06AT06A031, July 15–20, 2018
Paper No: PVP2018-84145
https://doi.org/10.1115/PVP2018-84145
View Paper titled, Comparison of Pressure-Temperature Limits for a Pressurized Water Reactor Pressure Vessel Considering Beltline and Extended Beltline Regions
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Topics: Pressure, Pressure vessels, Pressurized water reactors, Temperature, Nozzles, Embrittlement, Neutrons, Vessels, ASME Standards, Finite element model
Proceedings Papers

Application of Probabilistic Fracture Mechanics Analysis on BWR Recirculation Piping Systems

Yu-Yu Shen, Hsoung-Wei Chou, Chin-Cheng Huang, Ru-Feng Liu
Proc. ASME. PVP2016, Volume 6A: Materials and Fabrication, V06AT06A043, July 17–21, 2016
Paper No: PVP2016-63175
https://doi.org/10.1115/PVP2016-63175
View Paper titled, Application of Probabilistic Fracture Mechanics Analysis on BWR Recirculation Piping Systems
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Topics: Boiling water reactors, Fracture mechanics, Piping systems, Fracture (Process), Probability, Welded joints, Leakage, Nuclear power stations, Pipes, Electromagnetic induction
Proceedings Papers

Fracture Probability Assessment for Embrittled Reactor Pressure Vessels Under Ultimate Response Guideline Operation

Hsoung-Wei Chou, Chin-Cheng Huang
Proc. ASME. PVP2016, Volume 6A: Materials and Fabrication, V06AT06A036, July 17–21, 2016
Paper No: PVP2016-63121
https://doi.org/10.1115/PVP2016-63121
View Paper titled, Fracture Probability Assessment for Embrittled Reactor Pressure Vessels Under Ultimate Response Guideline Operation
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Topics: Fracture (Materials), Fracture (Process), Probability, Reactor vessels, Boiling water reactors, Fukushima nuclear disaster, Japan, 2011, Damage, Disasters, Accident management, Accidents
Journal Articles

Deterministic and Probabilistic Fracture Mechanics Analysis for Structural Integrity Assessment of Pressurized Water Reactor Pressure Vessel

Kuan-Rong Huang, Chin-Cheng Huang, Hsiung-Wei Chou
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
J. Pressure Vessel Technol. June 2016, 138(3): 031202.
Paper No: PVT-15-1089
https://doi.org/10.1115/1.4032110
Published Online: February 8, 2016
View Article titled, Deterministic and Probabilistic Fracture Mechanics Analysis for Structural Integrity Assessment of Pressurized Water Reactor Pressure Vessel
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Topics: Embrittlement, Fracture (Materials), Fracture mechanics, Pressure, Pressure vessels, Pressurized water reactors, Probability, Radiation (Physics), Reliability, Stress
Proceedings Papers

Probabilistic Structural Integrity Evaluation on a Pressurized Water Reactor Pressure Vessel Under Pressure–Temperature Limit Operations

Hsoung-Wei Chou, Chin-Cheng Huang
Proc. ASME. PVP2015, Volume 7: Operations, Applications and Components, V007T07A030, July 19–23, 2015
Paper No: PVP2015-45166
https://doi.org/10.1115/PVP2015-45166
View Paper titled, Probabilistic Structural Integrity Evaluation on a Pressurized Water Reactor Pressure Vessel Under Pressure–Temperature Limit Operations
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Topics: Pressure, Pressure vessels, Pressurized water reactors, Temperature, Failure, Risk, Fracture toughness, ASME Standards, Embrittlement, Fracture (Materials)
Proceedings Papers

Structural Reliability Evaluation on the Pressurized Water Reactor Pressure Vessel Under Pressurized Thermal Shock Events

Hsoung-Wei Chou, Chin-Cheng Huang
Proc. ASME. PVP2014, Volume 7: Operations, Applications and Components, V007T07A019, July 20–24, 2014
Paper No: PVP2014-28350
https://doi.org/10.1115/PVP2014-28350
View Paper titled, Structural Reliability Evaluation on the Pressurized Water Reactor Pressure Vessel Under Pressurized Thermal Shock Events
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Topics: Pressure vessels, Pressurized water reactors, Reliability, Thermal shock, Reactor vessels, Cracking (Materials), Failure, Fracture (Process), Nuclear power stations, Fracture mechanics
Proceedings Papers

Probabilistic Fracture Mechanics Analysis for Degraded Reactor Pressure Vessel in Pressurized Water Reactor Nuclear Power Plant

Kuan-Rong Huang, Chin-Cheng Huang, Hsoung-Wei Chou
Proc. ASME. PVP2014, Volume 7: Operations, Applications and Components, V007T07A021, July 20–24, 2014
Paper No: PVP2014-28595
https://doi.org/10.1115/PVP2014-28595
View Paper titled, Probabilistic Fracture Mechanics Analysis for Degraded Reactor Pressure Vessel in Pressurized Water Reactor Nuclear Power Plant
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Topics: Fracture mechanics, Nuclear power stations, Pressurized water reactors, Reactor vessels, Embrittlement, Reliability, Transients (Dynamics), Boilers, Design, Failure
Proceedings Papers

Structural Integrity Analyses for a Preemptive Weld Overlay in a Pressurizer Surge Nozzle

Ru-Feng Liu, Chin-Cheng Huang
Proc. ASME. PVP2013, Volume 6A: Materials and Fabrication, V06AT06A084, July 14–18, 2013
Paper No: PVP2013-97258
https://doi.org/10.1115/PVP2013-97258
View Paper titled, Structural Integrity Analyses for a Preemptive Weld Overlay in a Pressurizer Surge Nozzle
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Topics: Nozzles, Overlays (Materials engineering), Surges, Stress, ASME Standards, Fatigue, Fatigue cracks, Shrinkage (Materials), Compressive stress, Cracking (Materials)
Proceedings Papers

Effects of Fracture Toughness Curves of ASME Section XI: Appendix G on a Reactor Pressure Vessel Under Pressure–Temperature Limit Operation

Hsoung-Wei Chou, Chin-Cheng Huang, Kuan-Rong Huang, Ru-Feng Liu
Proc. ASME. PVP2013, Volume 7: Operations, Applications and Components, V007T07A030, July 14–18, 2013
Paper No: PVP2013-97262
https://doi.org/10.1115/PVP2013-97262
View Paper titled, Effects of Fracture Toughness Curves of ASME Section XI: Appendix G on a Reactor Pressure Vessel Under Pressure–Temperature Limit Operation
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Topics: Fracture toughness, Pressure, Reactor vessels, Temperature, Failure, Probability, Transients (Dynamics), Embrittlement, Fracture mechanics, Heat
Proceedings Papers

Failure Probability Assessment for a Boiling Water Reactor Pressure Vessel Under Low Temperature Over-Pressure Event

Hsoung-Wei Chou, Chin-Cheng Huang, Bo-Yi Chen, Hsien-Chou Lin, Ru-Feng Liu
Proc. ASME. PVP2012, Volume 7: Operations, Applications and Components, 13-20, July 15–19, 2012
Paper No: PVP2012-78244
https://doi.org/10.1115/PVP2012-78244
View Paper titled, Failure Probability Assessment for a Boiling Water Reactor Pressure Vessel Under Low Temperature Over-Pressure Event
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Topics: Boiling water reactors, Failure, Low temperature, Pressure, Pressure vessels, Probability, Fracture (Process), Licensing, Reactor vessels, Vessels
Journal Articles

Boiling Water Reactor Pressure Vessel Integrity Evaluation by Probabilistic Fracture Mechanics (PVP2010-25195)

Bo-Yi Chen, Chin-Cheng Huang, Hsoung-Wei Chou, Ru-Feng Liu, Hsien-Chou Lin
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
J. Pressure Vessel Technol. February 2013, 135(1): 011206.
Paper No: PVT-12-1003
https://doi.org/10.1115/1.4007292
Published Online: December 17, 2012
View Article titled, Boiling Water Reactor Pressure Vessel Integrity Evaluation by Probabilistic Fracture Mechanics (PVP2010-25195)
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Topics: Boiling water reactors, Design, Failure, Fluence (Radiation measurement), Fracture mechanics, Neutrons, Nuclear power stations, Pressure vessels, Probability, Transients (Dynamics)
Journal Articles

Weld Residual Stress Analysis and the Effects of Structural Overlay on Various Nuclear Power Plant Nozzles

Tao Zhang, Frederick W. Brust, Gery Wilkowski, Chin-Cheng Huang, Ru-Feng Liu, Sam Ranganath, Lihua Wang, Yao Long Tsai
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
J. Pressure Vessel Technol. December 2012, 134(6): 061205.
https://doi.org/10.1115/1.4006558
Published Online: October 18, 2012
View Article titled, Weld Residual Stress Analysis and the Effects of Structural Overlay on Various Nuclear Power Plant Nozzles
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Topics: Nozzles, Stress, Overlays (Materials engineering), Surges, Sprays, Safety
Proceedings Papers

The Influence of Chemistry Concentration Uncertainty on the Probabilistic Fracture Mechanics Analysis

Bo-Yi Chen, Chin-Cheng Huang, Hsuing-Wei Chou, Ru-Feng Liu, Hsien-Chou Lin
Proc. ASME. PVP2011, Volume 7: Operations, Applications, and Components, 41-47, July 17–21, 2011
Paper No: PVP2011-57470
https://doi.org/10.1115/PVP2011-57470
View Paper titled, The Influence of Chemistry Concentration Uncertainty on the Probabilistic Fracture Mechanics Analysis
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Topics: Chemistry, Fracture mechanics, Uncertainty, Fracture (Materials), Fracture (Process), Probability, Reactor vessels, Welded joints, Boiling water reactors, Ductility
Proceedings Papers

Boiling Water Reactor Pressure Vessel Integrity Evaluation by Probabilistic Fracture Mechanics

Bo-Yi Chen, Chin-Cheng Huang, Hsoung-Wei Chou, Ru-Feng Liu, Hsien-Chou Lin
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 7, 149-155, July 18–22, 2010
Paper No: PVP2010-25195
https://doi.org/10.1115/PVP2010-25195
View Paper titled, Boiling Water Reactor Pressure Vessel Integrity Evaluation by Probabilistic Fracture Mechanics
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Topics: Boiling water reactors, Fracture mechanics, Pressure vessels, Welded joints, Probability, Failure, Fluence (Radiation measurement), Licensing, Life extension, Neutrons
Proceedings Papers

Probabilistic Fracture Analysis for Boiling Water Reactor Pressure Vessels Subjected to Low Temperature Over-Pressure Event

Hsoung-Wei Chou, Chin-Cheng Huang, Bo-Yi Chen, Ru-Feng Liu, Hsien-Chou Lin
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 7, 157-164, July 18–22, 2010
Paper No: PVP2010-25196
https://doi.org/10.1115/PVP2010-25196
View Paper titled, Probabilistic Fracture Analysis for Boiling Water Reactor Pressure Vessels Subjected to Low Temperature Over-Pressure Event
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Topics: Boiling water reactors, Fracture (Materials), Fracture (Process), Low temperature, Pressure, Pressure vessels, In-service inspection, Welded joints, Safety, Failure
Proceedings Papers

Weld Residual Stress Analysis and the Effects of Structural Overlay on Various Nuclear Power Plant Nozzles

Tao Zhang, Bud Brust, Gery Wilkowski, Sam Ranganath, Lihua Wang, Yao Long Tsai, Chin-Cheng Huang, Ru-Feng Liu
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B, 1333-1342, July 18–22, 2010
Paper No: PVP2010-25331
https://doi.org/10.1115/PVP2010-25331
View Paper titled, Weld Residual Stress Analysis and the Effects of Structural Overlay on Various Nuclear Power Plant Nozzles
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Topics: Nozzles, Nuclear power stations, Overlays (Materials engineering), Stress analysis (Engineering), Stress, Welded joints, Welding, Maintenance, Pipes, Metals