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Proceedings Papers

The Optimization Design of Storage Efficiency and Structural Analysis for the 3 Cubic Meter Radioactive Waste Container

Yu-Yu Shen, Hsien-Chou Lin, Hsoung-Wei Chou
Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A026, July 14–19, 2019
Paper No: PVP2019-93201
DOI: https://doi.org/10.1115/PVP2019-93201
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Topics: Containers, Design, Optimization, Radioactive wastes, Storage, Structural analysis
Proceedings Papers

Flaw Acceptance Evaluation for the Final Disposal Canister Under Earthquake Induced Rock Shear

Hsoung-Wei Chou, Szu-Ying Wu
Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A008, July 14–19, 2019
Paper No: PVP2019-93165
DOI: https://doi.org/10.1115/PVP2019-93165
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Topics: Earthquakes, Fracture mechanics, Rocks, Shear (Mechanics), Polishing equipment, Stress, Acceptance criteria, Cast iron, Crack detection, Density
Proceedings Papers

Application of Flaw Updating Process on Probabilistic Structural Evaluation for a Reactor Pressure Vessel Under Pressurized Thermal Shocks

Pin-Chiun Huang, Hsoung-Wei Chou, Yuh-Ming Ferng
Proc. ASME. PVP2018, Volume 6A: Materials and Fabrication, V06AT06A035, July 15–20, 2018
Paper No: PVP2018-84477
DOI: https://doi.org/10.1115/PVP2018-84477
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Topics: Reactor vessels, Thermal shock, Nondestructive evaluation, Vessels, Fracture (Materials), Fracture (Process), Databases, Fracture mechanics, Inspection, Nuclear power stations
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
DOI: https://doi.org/10.1115/PVP2018-84145
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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
DOI: https://doi.org/10.1115/PVP2016-63175
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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
DOI: https://doi.org/10.1115/PVP2016-63121
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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
Proceedings Papers

Effects of Chemical Content Variation on the Fracture Probability of PWR Pressure Vessel Subjected to PTS Events

Pin-Chiun Huang, Hsoung-Wei Chou, Yuh-Ming Ferng
Proc. ASME. PVP2015, Volume 7: Operations, Applications and Components, V007T07A031, July 19–23, 2015
Paper No: PVP2015-45230
DOI: https://doi.org/10.1115/PVP2015-45230
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Topics: Fracture (Materials), Fracture (Process), Pressure vessels, Pressurized water reactors, Probability, Copper, Nickel, Transients (Dynamics), Embrittlement, Fracture mechanics
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
DOI: https://doi.org/10.1115/PVP2015-45166
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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
DOI: https://doi.org/10.1115/PVP2014-28350
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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
DOI: https://doi.org/10.1115/PVP2014-28595
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Topics: Fracture mechanics, Nuclear power stations, Pressurized water reactors, Reactor vessels, Embrittlement, Reliability, Transients (Dynamics), Boilers, Design, Failure
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
DOI: https://doi.org/10.1115/PVP2013-97262
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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
DOI: https://doi.org/10.1115/PVP2012-78244
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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
DOI: https://doi.org/10.1115/1.4007292
Published Online: December 17, 2012
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Topics: Boiling water reactors, Design, Failure, Fluence (Radiation measurement), Fracture mechanics, Neutrons, Nuclear power stations, Pressure vessels, Probability, Transients (Dynamics)
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
DOI: https://doi.org/10.1115/PVP2010-25195
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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
DOI: https://doi.org/10.1115/PVP2010-25196
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Topics: Boiling water reactors, Fracture (Materials), Fracture (Process), Low temperature, Pressure, Pressure vessels, In-service inspection, Welded joints, Safety, Failure