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Yongjun Deng
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Proceedings Papers

Construction of the Failed Fuel Information Database Platform

Xin Liu, Changzheng Li, Yang Wang, Hongyang Zhang, Yongjun Deng
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A008, August 8–12, 2022
Paper No: ICONE29-93281
DOI: https://doi.org/10.1115/ICONE29-93281
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Topics: Construction, Databases, Fuels, Manufacturing
Proceedings Papers

Study on the Influence of Roughness on Fuel Rod Gap Heat Transfer

Weichao Liu, Guoliang Zhang, Changzheng Li, Jin Cao, Shaofang Lin, Xiangang Fu, Lihong Nie, Yongjun Deng
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A060, August 8–12, 2022
Paper No: ICONE29-93004
DOI: https://doi.org/10.1115/ICONE29-93004
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Topics: Cladding systems (Building), Fuel rods, Heat transfer, Heat transfer coefficients, Surface roughness
Proceedings Papers

Key Impact Factors Analysis of Fuel Rod End Plug Welding Based on QFD

Yinghong Li, Zhipeng Lv, Changzheng Li, Yuyu Lin, Shaofang Lin, Zhiyi Cai, Yongjun Deng, Lihong Nie
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A064, August 8–12, 2022
Paper No: ICONE29-92803
DOI: https://doi.org/10.1115/ICONE29-92803
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Topics: Fuel rods, Fuels, Reliability, Welding
Proceedings Papers

Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition

Jie Wang, Yang Wang, Jun Wei, Yongjun Deng
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A015, August 8–12, 2022
Paper No: ICONE29-90521
DOI: https://doi.org/10.1115/ICONE29-90521
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Topics: Cladding systems (Building), Ductility, Equipment performance, Hydrogen, Zirconium alloys, Zirconium, Accidents, Failure, Fracture (Process), Light water reactors
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
DOI: https://doi.org/10.1115/ICONE26-81540
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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
DOI: https://doi.org/10.1115/ICONE25-67128
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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

Modeling of Fuel Rod Behavior and Recent Advances of the JASMINE Code

Xiaoyan Wei, Xin Jin, Yongjun Deng, Guoliang Zhang, Xiangang Fu
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A043, July 2–6, 2017
Paper No: ICONE25-67144
DOI: https://doi.org/10.1115/ICONE25-67144
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Topics: Fuel rods, Modeling, China, Computer software, Nuclear power, Nuclear reactors