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Journal Articles

Fracture Assessment for Pressurized Water Reactor Vessel Nozzles Subjected to Pressure and Thermal Loading

Chu Qibao, Wang Qing, Fang Yonggang, Tan Wei
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
J. Pressure Vessel Technol. October 2022, 144(5): 051302.
Paper No: PVT-21-1018
DOI: https://doi.org/10.1115/1.4053225
Published Online: February 10, 2022
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Topics: Fracture (Materials), Nozzles, Pressure, Stress, Transients (Dynamics), Fatigue cracks
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
Paper No: ICONE25-67734
DOI: https://doi.org/10.1115/ICONE25-67734
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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

Steam Generator Modal Analysis of Nuclear Power Plant

Lu Yan, Chu Qibao, Wang Qing, Fang Yonggang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A110, July 2–6, 2017
Paper No: ICONE25-67710
DOI: https://doi.org/10.1115/ICONE25-67710
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Topics: Boilers, Modal analysis, Nuclear power stations, Design, Nuclear reactor coolants