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Proceedings Papers

Die Design and Process Study of Zr-4 Alloy Profile Extrusion

Peng Qi, Bo Gao, Zhihao Zhang, Jianming Yin
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A041, August 8–12, 2022
Paper No: ICONE29-92961
DOI: https://doi.org/10.1115/ICONE29-92961
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Topics: Alloys, Computer simulation, Design, Extruding, Zirconium, Zirconium alloys
Proceedings Papers

Study on Load Capacity of Main Steam Superpipe Nozzle Used in Nuclear Power Plant

Zhou Gengyu, Liang Shuhua, Sun Lin, Lv Feng
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A075, July 2–6, 2017
Paper No: ICONE25-66965
DOI: https://doi.org/10.1115/ICONE25-66965
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Topics: Nozzles, Nuclear power stations, Steam, Stress, Pipes, Finite element analysis, Safety, Computational methods, Design, Extruding
Proceedings Papers

Crystal Plasticity Modeling of Hot Extrusion Texture and Plasticity in a Titanium Alloy for an ICME Toolset

Xianfeng Ma, Kan Ma, Yawen Wu
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A117, July 2–6, 2017
Paper No: ICONE25-67989
DOI: https://doi.org/10.1115/ICONE25-67989
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Topics: Crystals, Extruding, Modeling, Plasticity, Texture (Materials), Titanium alloys, Deformation, Alloys, Constitutive equations, Cooling
Proceedings Papers

Development of Shearing Device for Reducing the Storage Volume of the Spent Fuel Associated Assemblies in Nuclear Power Plants

Zhang Bin, Qiao Su-kai, Hao Qing-jun, Huang Hong-zhi, Ding Ming, Liu Pan
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A035, July 2–6, 2017
Paper No: ICONE25-67447
DOI: https://doi.org/10.1115/ICONE25-67447
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Topics: Die cutting, Nuclear power stations, Shearing (Deformation), Spent nuclear fuels, Storage, Spent fuel storage, Shear (Mechanics), Bearings, Blades, Extruding
Proceedings Papers

Research on Manufacturing Technology of China Experimental Fast Reactor Fuel Rod

Yu Hu, Jianhong Wang
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T06A005, June 26–30, 2016
Paper No: ICONE24-60076
DOI: https://doi.org/10.1115/ICONE24-60076
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Topics: China, Fast neutron reactors, Fuel rods, Manufacturing technology, Manufacturing, Welding, Wire, Cladding systems (Building), Extruding, Fuels
Proceedings Papers

Characterization of Hot Deformation Behavior of Zr-1.0Sn-0.3Nb-0.3Fe-0.1Cr Using Processing Map

B. F. Luan, R. S. Qiu, Z. Zhou, K. L. Murty, J. Zhou, Q. Liu
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A006, July 29–August 2, 2013
Paper No: ICONE21-15186
DOI: https://doi.org/10.1115/ICONE21-15186
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Topics: Deformation, Zirconium, Stress, Flow (Dynamics), Temperature, Recrystallization, Compression, Testing, Alloys, Constitutive equations
Proceedings Papers

Effect of Orientation on Mechanical Behavior of an Extruded Al Alloy

M. A. Malik, I. Salam, W. Muhammad
Proc. ASME. ICONE16, Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues, 641-647, May 11–15, 2008
Paper No: ICONE16-48548
DOI: https://doi.org/10.1115/ICONE16-48548
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Topics: Aluminum alloys, Extruding, Mechanical behavior, Mechanical properties, Reliability, Yield strength, Cylinders, Elongation, Fracture (Materials), Fracture (Process)
Proceedings Papers

Thoria-Based Cermet Nuclear Fuel: Cermet Fabrication and Behavior Estimates

Sean M. McDeavitt, T. J. Downar, A. A. Solomon, S. T. Revankar, M. C. Hash, A. S. Hebden
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 59-67, April 14–18, 2002
Paper No: ICONE10-22317
DOI: https://doi.org/10.1115/ICONE10-22317
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Topics: Cermets, Manufacturing, Nuclear fuels, Fuels, Nuclear fuel cycle, Temperature, Zirconium, Ceramics, Compacting, Cycles