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Proceedings Papers

LBB Analysis on Nuclear-Class Pipes of Floating Nuclear Power Stations

Fan Bai, Yong Liu, Xingsheng Lao, Qi Xiao, Zhenxing Zhao, Jun Wu, Can Ma, Wang Wei
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A029, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82180
https://doi.org/10.1115/ICONE26-82180
View Paper titled, LBB Analysis on Nuclear-Class Pipes of Floating Nuclear Power Stations
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Topics: Nuclear power stations, Pipes, Fracture (Materials), Leakage, Design, Drilling, Fatigue, Finite element methods, Fracture mechanics, Leak-before-break
Proceedings Papers

Crack Growth Safety Assessment of Overlay Weld on the Ω Seal for Control Rod Drive Mechanism

Jiacheng Luo, Yong Zhang, Pengzhou Li, Juan Luo, Lei Sun
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A036, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67615
https://doi.org/10.1115/ICONE25-67615
View Paper titled, Crack Growth Safety Assessment of Overlay Weld on the Ω Seal for Control Rod Drive Mechanism
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Topics: Fracture (Materials), Overlays (Materials engineering), Safety, Pressure, Stress corrosion cracking, Computational methods, Coolants, Cycles, Design, Fatigue
Proceedings Papers

Neutron Embrittlement Analysis of Qinshan 320MWe RPV on OLE

Tao Hongxin, He Yinbiao, Cao Ming, Shen Rui
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, V001T01A013, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66361
https://doi.org/10.1115/ICONE25-66361
View Paper titled, Neutron Embrittlement Analysis of Qinshan 320MWe RPV on OLE
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Topics: Embrittlement, Neutrons, Fracture (Materials), Fracture (Process), Irradiation (Radiation exposure), Pressurized water reactors, Safety, Service life (Equipment), Fracture mechanics, High pressure (Physics)
Proceedings Papers

Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regard to Primary Water Stress Corrosion Cracking

Akihiro Mano, Yoshihito Yamaguchi, Jinya Katsuyama, Yinsheng Li
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A014, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66145
https://doi.org/10.1115/ICONE25-66145
View Paper titled, Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regard to Primary Water Stress Corrosion Cracking
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Topics: Fracture mechanics, Stress corrosion cracking, Water, Failure, Pipes, Probability, Fracture (Materials), Pressurized water reactors, Alloys, Boiling water reactors
Proceedings Papers

Research on the Fracture Mechanics Analysis Method for Reactor Pressure Vessel Nozzle Corner Flaw

Shen Rui, Cao Ming, He Yinbiao, Tao Hongxin
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A028, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66284
https://doi.org/10.1115/ICONE25-66284
View Paper titled, Research on the Fracture Mechanics Analysis Method for Reactor Pressure Vessel Nozzle Corner Flaw
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Topics: Corners (Structural elements), Fracture mechanics, Nozzles, Reactor vessels, Computer software, Finite element analysis, Stress, Design, Fracture (Materials), Pressurized water reactors
Proceedings Papers

Verification of Probabilistic Fracture Mechanics Analysis Code PASCAL

Yinsheng Li, Genshichiro Katsumata, Koichi Masaki, Shotaro Hayashi, Yu Itabashi, Masaki Nagai, Masahide Suzuki, Yasuhiro Kanto
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A050, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66468
https://doi.org/10.1115/ICONE25-66468
View Paper titled, Verification of Probabilistic Fracture Mechanics Analysis Code PASCAL
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Topics: Fracture mechanics, Fracture (Process), Embrittlement, Irradiation (Radiation exposure), Light water reactors, Neutrons, Nuclear power, Nuclear power stations, Pressure, Reactor vessels
Proceedings Papers

Improvement of Probabilistic Fracture Mechanics Analysis Code for Reactor Piping Considering Large Earthquakes

Yoshihito Yamaguchi, Jinya Katsuyama, Makoto Udagawa, Kunio Onizawa, Yutaka Nishiyama, Yinsheng Li
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, V001T03A022, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30643
https://doi.org/10.1115/ICONE22-30643
View Paper titled, Improvement of Probabilistic Fracture Mechanics Analysis Code for Reactor Piping Considering Large Earthquakes
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Topics: Earthquakes, Fracture mechanics, Pipes, Failure, Fracture (Materials), Probability, Sensitivity analysis, Evaluation methods
Proceedings Papers

Comparison of PTS Guides for Reactor Pressure Vessel Integrity Assessment

Milan Brumovsky
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T07A007, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15419
https://doi.org/10.1115/ICONE21-15419
View Paper titled, Comparison of PTS Guides for Reactor Pressure Vessel Integrity Assessment
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Topics: Reactor vessels, Fracture mechanics, ASME Standards, Cooling, Emergencies, Materials degradation, Materials properties, Nuclear power stations, Safety, Testing
Proceedings Papers

Role of Irradiation Embrittlement in RPV Lifetime Assessment

Milan Brumovský, Miloš Kytka
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A013, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15420
https://doi.org/10.1115/ICONE21-15420
View Paper titled, Role of Irradiation Embrittlement in RPV Lifetime Assessment
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Topics: Embrittlement, Irradiation (Radiation exposure), Design, Radiation damage, Engineering standards, Failure, Fluence (Radiation measurement), Fracture mechanics, Hardening, Neutron flux
Proceedings Papers

Probabilistic Distribution of Parameters Applied to PFM Analysis for Piping in China Experimental Fast Reactor

Min Qi, Yueying Wang, Jia Liu
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A059, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16520
https://doi.org/10.1115/ICONE21-16520
View Paper titled, Probabilistic Distribution of Parameters Applied to PFM Analysis for Piping in China Experimental Fast Reactor
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Topics: China, Fast neutron reactors, Pipes, Fracture mechanics, Design for Manufacturing, Dimensions, Fittings, Pressure vessels, Probabilistic safety assessment, Probability
Proceedings Papers

A Risk-Informed Approach to Fatigue Break Criterion for ASME Class 1 High Energy Piping

S. R. Gosselin, F. A. Simonen
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 373-379, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54534
https://doi.org/10.1115/ICONE20-POWER2012-54534
View Paper titled, A Risk-Informed Approach to Fatigue Break Criterion for ASME Class 1 High Energy Piping
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Topics: Fatigue, Pipes, Risk, Damage, Probability, Design, Fracture (Materials), Accidents, ASME Standards, Coolants
Proceedings Papers

Structural Integrity of HDPE Piping and Joints in Nuclear Safety-Related Applications

S. Kalyanam, P. Krishnaswamy, D.-J. Shim, Y. Hioe, E. Focht
Proc. ASME. ICONE20-POWER2012, Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes, 51-62, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54192
https://doi.org/10.1115/ICONE20-POWER2012-54192
View Paper titled, Structural Integrity of HDPE Piping and Joints in Nuclear Safety-Related Applications
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Topics: Pipes, Safety, Stress, Nuclear power stations, Service life (Equipment), ASME Boiler and Pressure Vessel Code, ASTM International, Fracture mechanics, Pressure, Rupture
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54636
https://doi.org/10.1115/ICONE20-POWER2012-54636
View Paper titled, An Addendum: Probabilistic Failure Analysis of a Residual Heat Removal Heat Exchanger During Postulated Loss of Coolant Accident
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Topics: Accidents, Coolants, Failure analysis, Heat, Heat exchangers, Failure, Probability, Simulation, Flow (Dynamics), FORTRAN
Proceedings Papers

Dr. Mainte: An Integrated Simulator for Optimization of Maintenance Strategies of Light Water Reactors

Yoshihiro Isobe, Mitsuyuki Sagisaka
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 301-304, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29894
https://doi.org/10.1115/ICONE18-29894
View Paper titled, Dr. Mainte: An Integrated Simulator for Optimization of Maintenance Strategies of Light Water Reactors
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Topics: Light water reactors, Maintenance, Optimization, Decision making, Fracture mechanics, Nuclear power stations, Piping systems, Safety
Proceedings Papers

VERLIFE - Unified Procedure for Lifetime Assessment of Components and Piping in WWER NPPs During Operation: Updating and Further Development

Milan Brumovsky
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 463-467, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30256
https://doi.org/10.1115/ICONE18-30256
View Paper titled, VERLIFE - Unified Procedure for Lifetime Assessment of Components and Piping in WWER NPPs During Operation: Updating and Further Development
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Topics: Nuclear power stations, Pipes, Corrosion, Damage, Design, Erosion, Fracture mechanics, In-service inspection, Leak-before-break, Manufacturing
Proceedings Papers

Rupture Frequency of CANDU ® Large-Diameter Primary Heat Transport Piping Estimated Using Probabilistic Fracture Mechanics Codes

Rob McLean, Xinjian Duan, Michael J. Kozluk
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 237-246, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29973
https://doi.org/10.1115/ICONE18-29973
View Paper titled, Rupture Frequency of CANDU ® Large-Diameter Primary Heat Transport Piping Estimated Using Probabilistic Fracture Mechanics Codes
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Topics: Fracture mechanics, Heat, Pipes, Rupture, Leakage, Probability, Welded joints, Manufacturing
Proceedings Papers

Stress Intensity Factors for Unusual Semi-Elliptical Surface Cracks With Ratio a/l Greater Than 0.5

Christian Malekian, Eric Wyart, Michael Savelsberg, David Lacroix, Anne Teughels, Nicolas Minjauw, Audrey Wendling
Proc. ASME. ICONE17, Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 131-141, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75441
https://doi.org/10.1115/ICONE17-75441
View Paper titled, Stress Intensity Factors for Unusual Semi-Elliptical Surface Cracks With Ratio a/l Greater Than 0.5
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Topics: Stress, Surface cracks, Fracture (Materials), Finite element analysis, Shapes, Corrosion, Fatigue, Finite element methods, Fracture mechanics, Plates (structures)
Proceedings Papers

Effects of Laser Peening Treatment on High Cycle Fatigue and Crack Propagation Behaviors in Austenitic Stainless Steel

Yasuo Ochi, Kiyotaka Masaki, Takashi Matsumura, Takaaki Ikarashi, Yuji Sano
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 701-707, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75821
https://doi.org/10.1115/ICONE17-75821
View Paper titled, Effects of Laser Peening Treatment on High Cycle Fatigue and Crack Propagation Behaviors in Austenitic Stainless Steel
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Topics: Crack propagation, High cycle fatigue, Laser hardening, Stainless steel, Stress, Fatigue cracks, Fatigue strength, Fracture (Materials), Irradiation (Radiation exposure), Lasers
Proceedings Papers

Natural Crack Growth in BWR Shroud Support Dissimilar Metal Weld Joints

S. F. Hankinson, T. Hayashi, C. K. Ng, S. A. Swamy
Proc. ASME. ICONE17, Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 89-95, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75330
https://doi.org/10.1115/ICONE17-75330
View Paper titled, Natural Crack Growth in BWR Shroud Support Dissimilar Metal Weld Joints
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Topics: Boiling water reactors, Fracture (Materials), Metals, Shapes, Stress, Simulation, Alloys, Finite element analysis, Fracture mechanics, Geometry
Proceedings Papers

Development of a J-Estimation Scheme for Surface Cracks in Piping Welds

Patrick Le Delliou, Ste´phane Marie, Yann Kayser, Bruno Barthelet
Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 121-130, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48393
https://doi.org/10.1115/ICONE16-48393
View Paper titled, Development of a J-Estimation Scheme for Surface Cracks in Piping Welds
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Topics: Pipes, Surface cracks, Welded joints, Analytical methods, Fracture (Materials), Carbon, Clearances (Engineering), Fracture mechanics, Geometry, In-service inspection