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Chang-yuan Gao
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Proceedings Papers

The Research of Corrosion Resistance of CZ2 Zirconium Alloy Welding Specimens

Yang Xu, Liu-Tao Chen, Chang-Yuan Gao, Jun Tan, Lin Shi
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A092, August 8–12, 2022
Paper No: ICONE29-93838
DOI: https://doi.org/10.1115/ICONE29-93838
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Topics: Corrosion, Corrosion resistance, Weight (Mass), Welding, Zirconium alloys
Proceedings Papers

Investigation on Breakaway Oxidation Behavior of CZ Alloys

Chang-yuan Gao, Liu-tao Chen, Lin Shi, Yang Xu, Jun Tan, Yong-jun Deng
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A026, July 22–26, 2018
Paper No: ICONE26-81541
DOI: https://doi.org/10.1115/ICONE26-81541
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Topics: Alloys, Oxidation, China, Hydrogen, Nuclear power, Steam, Accidents, Coolants, Failure mechanisms, Fuels
Proceedings Papers

Annealing Temperature Effect on Creep Property of CZ Alloy for PWR Modern Fuel Claddings

Yang Xu, Jun Tan, Liu-tao Chen, Dun-gu Wen, Hong Zou, Chang-yuan Gao, Xu Wang, Si-si Dong, Wei-jun Wang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A039, July 2–6, 2017
Paper No: ICONE25-67054
DOI: https://doi.org/10.1115/ICONE25-67054
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Topics: Alloys, Annealing, Creep, Fuels, Pressurized water reactors, Temperature, Zirconium alloys, Stress, China, Cladding systems (Building)