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Proceedings Papers

Study on Fatigue Properties of Hydrided CZ2 Alloy

Jieming Huang, Changyuan Gao, Liutao Chen, Xu Wang, Jun Tan
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A085, August 8–12, 2022
Paper No: ICONE29-93763
https://doi.org/10.1115/ICONE29-93763
View Paper titled, Study on Fatigue Properties of Hydrided CZ2 Alloy
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Topics: Alloys, Fatigue, Fatigue properties
Proceedings Papers

Study of Iodine-Induced Stress Corrosion Cracking of CZ2 Alloy

Lin Shi, Changyuan Gao, Guoliang Zhang, Guocheng Sun, Xu Wang, Liutao Chen, Jun Tan
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A091, August 8–12, 2022
Paper No: ICONE29-93835
https://doi.org/10.1115/ICONE29-93835
View Paper titled, Study of Iodine-Induced Stress Corrosion Cracking of CZ2 Alloy
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Topics: Alloys, Fracture (Materials), Fracture (Process), Stress corrosion cracking
Proceedings Papers

Study on Water Chemistry and Temperature Adaptability of CZ Zirconium Alloy

Hansen Chen, Changyuan Gao, Liutao Chen, Xu Wang, Jun Tan
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A090, August 8–12, 2022
Paper No: ICONE29-93820
https://doi.org/10.1115/ICONE29-93820
View Paper titled, Study on Water Chemistry and Temperature Adaptability of CZ Zirconium Alloy
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Topics: Temperature, Water chemistry, Zirconium alloys
Proceedings Papers

Study on Out-Pile Performance of CZ Zirconium Alloy Guide Tube

Changyuan Gao, Lin Shi, Guoliang Zhang, Yang Xu, Minli Chen, Liutao Chen, Jun Tan
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A089, August 8–12, 2022
Paper No: ICONE29-93816
https://doi.org/10.1115/ICONE29-93816
View Paper titled, Study on Out-Pile Performance of CZ Zirconium Alloy Guide Tube
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Topics: Corrosion, Creep, Zirconium alloys, Alloys, Zirconium, Corrosion resistance, Stress, Temperature, Mechanical testing, Particulate matter
Proceedings Papers

Study of Pre-Oxidization Law and Fretting Wear Resistance of CZ2 Alloy Cladding

Guocheng Sun, Shi Lin, Xu Wang, Liutao Chen
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A088, August 8–12, 2022
Paper No: ICONE29-93804
https://doi.org/10.1115/ICONE29-93804
View Paper titled, Study of Pre-Oxidization Law and Fretting Wear Resistance of CZ2 Alloy Cladding
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Topics: Alloys, Cladding systems (Building), Wear, Wear resistance
Proceedings Papers

Oxidation Behaviour of CZ Alloys Under High Temperature Steam

Minli Chen, Changyuan Gao, Guoliang Zhang, Lin Shi, Liutao Chen, Jun Tan
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A087, August 8–12, 2022
Paper No: ICONE29-93795
https://doi.org/10.1115/ICONE29-93795
View Paper titled, Oxidation Behaviour of CZ Alloys Under High Temperature Steam
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Topics: Alloys, High temperature steam, Oxidation, Steam, Zirconium alloys
Proceedings Papers

Microstructual and Micro-Chemical Analysis of Zr Cladding Alloys on Corrosion and Creep Properties

Qing Yang Lv, Libin Zhang, Minli Chen, Changyuan Gao, Yang Xu, Liutao Chen, Jun Tan
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A086, August 8–12, 2022
Paper No: ICONE29-93770
https://doi.org/10.1115/ICONE29-93770
View Paper titled, Microstructual and Micro-Chemical Analysis of Zr Cladding Alloys on Corrosion and Creep Properties
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Topics: Alloys, Annealing, Cladding systems (Building), Corrosion, Creep, Tin, Zirconium
Proceedings Papers

Effect of Final Annealing Temperature on Axial Creep Property of CZ Alloys

Lin Shi, Liutao Chen, Yang Xu, Changyuan Gao, Jun Tan, Yongjun Deng
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A025, July 22–26, 2018
Paper No: ICONE26-81540
https://doi.org/10.1115/ICONE26-81540
View Paper titled, Effect of Final Annealing Temperature on Axial Creep Property of CZ Alloys
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Topics: Alloys, Annealing, Creep, Temperature, Stress, Cladding systems (Building), China, Nuclear power, Pressurized water reactors
Proceedings Papers

Stability of SPPs in Zirconium Alloy CZ2 Under Self-Ion Irradiation

Xu Wang, Jun Tan, Liutao Chen, Hong Zou, Dungu Wen, Yang Xu, Changyuan Gao, Yongjun Deng, Yuemin Zhou, Lumin Wang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A042, July 2–6, 2017
Paper No: ICONE25-67128
https://doi.org/10.1115/ICONE25-67128
View Paper titled, Stability of SPPs in Zirconium Alloy CZ2 Under Self-Ion Irradiation
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Topics: Irradiation (Radiation exposure), Stability, Zirconium alloys, Zirconium, Crystal structure, Temperature, Damage, Heat treating (Metalworking), Particulate matter, Radiation effects
Proceedings Papers

Effects of Annealing on the Corrosion Property of CZ1 Alloy

Liutao Chen, Jun Tan, Changyuan Gao, Dungu Wen, Hong Zou, Yang Xu, Xu Wang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A038, July 2–6, 2017
Paper No: ICONE25-67035
https://doi.org/10.1115/ICONE25-67035
View Paper titled, Effects of Annealing on the Corrosion Property of CZ1 Alloy
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Topics: Alloys, Annealing, Corrosion, Cladding systems (Building), Corrosion resistance, Particulate matter, Zirconium, China, Design, Fuels