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Proceedings Papers

Effect of Temperature and Lithium Concentration on the Out of Reactor Corrosion Property of SZA Alloys and Model Study

Qifeng Zeng, Chen Wang, Ben Wang, Junqiang Lu, Cong Li, Lefu Zhang, Shengyi Si
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A046, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135893
https://doi.org/10.1115/ICONE31-135893
View Paper titled, Effect of Temperature and Lithium Concentration on the Out of Reactor Corrosion Property of SZA Alloys and Model Study
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Topics: Alloys, Corrosion, Corrosion resistance, Lithium, Temperature, Zirconium alloys
Journal Articles

Effect of Niobium on Sintering Process of Gamma Phase Uranium Alloys Fuel Pellets

Keke Hou, Chao Yan, Peng Wang, Changqing Cao, Jun Lin, Yanguang Cui, Junqiang Lu, Libing Zhu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041101.
Paper No: NERS-22-1130
https://doi.org/10.1115/1.4062795
Published Online: July 17, 2023
View Article titled, Effect of Niobium on Sintering Process of Gamma Phase Uranium Alloys Fuel Pellets
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Topics: Alloys, Fuels, Sintering, Uranium, Thermal conductivity, Density
Proceedings Papers

CAP1400 Fuel Assembly Development and PWR Fuel Assembly Technology Progress in China

Libing Zhu, Jie Ding, Qin Zhou, Yunqing Zhou, Fujun Gan, Junqiang Lu, Yixiong Zheng, Jiwei Li, Yang Ding, Qifeng Zeng, Song Liu
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A025, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66700
https://doi.org/10.1115/ICONE25-66700
View Paper titled, CAP1400 Fuel Assembly Development and PWR Fuel Assembly Technology Progress in China
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Topics: China, Fuels, Manufacturing, Pressurized water reactors, Irradiation (Radiation exposure), Alloys, Cladding systems (Building), Design, Fuel rods, Reliability
Proceedings Papers

Preparation and Properties Investigation of Neutron Absorber Material Mo-Tb-Dy and Y-Tb-Dy Alloys

Junqiang Lu, Lei Chen, Congzhang Qiu, Weiyan Yang, Feifei Zhang, Ruifang Yang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A026, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66747
https://doi.org/10.1115/ICONE25-66747
View Paper titled, Preparation and Properties Investigation of Neutron Absorber Material Mo-Tb-Dy and Y-Tb-Dy Alloys
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Topics: Alloys, Neutrons, Irradiation (Radiation exposure), Temperature, Corrosion, Atoms, Corrosion resistance, Density, Diluents, Displacement
Proceedings Papers

Microstructure and Properties of New Zirconium Alloys for CAP1400 Fuel Assembly

Qifeng Zeng, Libing Zhu, Gaihuan Yuan, Lian Wang, Guocheng Sun, Junqiang Lu
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A037, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66951
https://doi.org/10.1115/ICONE25-66951
View Paper titled, Microstructure and Properties of New Zirconium Alloys for CAP1400 Fuel Assembly
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Topics: Fuels, Manufacturing, Zirconium alloys, Alloys, Corrosion resistance, Creep, Mechanical properties, Design, Temperature, Water chemistry