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Proceedings Papers

Effect of Reactor Coolant Environment on Fatigue Property of Austenitic Stainless Steel in PWR

Fang Yonggang, Zhan Jiashuo, Chu Qibao, Wang Qing, Xu Yu
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A111, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67734
https://doi.org/10.1115/ICONE25-67734
View Paper titled, Effect of Reactor Coolant Environment on Fatigue Property of Austenitic Stainless Steel in PWR
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Topics: Fatigue properties, Nuclear reactor coolants, Pressurized water reactors, Stainless steel, Fatigue, Fatigue design, Coolants, Design, Fatigue analysis, Nuclear reactors
Proceedings Papers

Evaluation of Fatigue Life of Pressurized Water Reactor Internals Considering Light-Water Reactor Coolant Environmental Effect for Aging Management Program

Jianfeng Yang, Paul O’Brien
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, V001T07A018, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31169
https://doi.org/10.1115/ICONE22-31169
View Paper titled, Evaluation of Fatigue Life of Pressurized Water Reactor Internals Considering Light-Water Reactor Coolant Environmental Effect for Aging Management Program
Open the PDF for Evaluation of Fatigue Life of Pressurized Water Reactor Internals Considering Light-Water Reactor Coolant Environmental Effect for Aging Management Program in another window
Topics: Coolants, Fatigue life, Light water reactors, Pressurized water reactors, Fatigue, Design, Alloys, Cycles, ASME Boiler and Pressure Vessel Code, Carbon
Proceedings Papers

Fatigue Design Rules in Pressure Vessel Codes Uncertainties and Remaining Open Points

Claude Faidy
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, V001T07A011, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30715
https://doi.org/10.1115/ICONE22-30715
View Paper titled, Fatigue Design Rules in Pressure Vessel Codes Uncertainties and Remaining Open Points
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Topics: Fatigue design, Pressure vessels, Uncertainty, Fatigue, Fatigue analysis, Materials properties, Boilers, Damage, Electromagnetic scattering, Fatigue testing
Proceedings Papers

Development of the Optimized Fatigue Analysis Procedure to Evaluate Design Life for APR1400

Jaegon Lee, Taesoon Kim, Chankook Moon, Kwanghan Lee
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, 665-670, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48659
https://doi.org/10.1115/ICONE16-48659
View Paper titled, Development of the Optimized Fatigue Analysis Procedure to Evaluate Design Life for APR1400
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Topics: Design, Fatigue analysis, Fatigue, Fatigue design, Nozzles, Nuclear power stations, ASME Standards, Boilers, Coolants, Failure mechanisms