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Proceedings Papers

Effects of Stoichiometry and High-Temperature Annealing on Zirconium Carbide Coating Layer in TRISO Particles

Xinyu Cheng, Rongzheng Liu, Bing Liu, Xu Yang, Malin Liu, Jiaxing Chang, Youlin Shao
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A066, August 8–12, 2022
Paper No: ICONE29-92858
DOI: https://doi.org/10.1115/ICONE29-92858
View Paper titled, Effects of Stoichiometry and High-Temperature Annealing on Zirconium Carbide Coating Layer in TRISO Particles
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Topics: Annealing, Coatings, Fuels, High temperature, Particulate matter, Stoichiometry, Very high temperature reactors, Zirconium
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
DOI: 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

Study on the Manufacturing Process of Large Super Alloy X-750 Forgings for Nuclear Equipment

Mei-fang Chen, Sheng-qiang Cao, Kai Dong
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A019, August 8–12, 2022
Paper No: ICONE29-91791
DOI: https://doi.org/10.1115/ICONE29-91791
View Paper titled, Study on the Manufacturing Process of Large Super Alloy X-750 Forgings for Nuclear Equipment
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Topics: Alloys, Forging, Forgings (Products), Manufacturing, Springs, Temperature, Grain size, Annealing, Creep, Fracture (Materials)
Proceedings Papers

Effect of Annealing Temperature on Dislocation Loop Absorption And Evolution in Fe by Molecular Dynamics Study

Pandong Lin, Junfeng Nie, Meidan Liu
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A007, August 4–6, 2021
Paper No: ICONE28-62550
DOI: https://doi.org/10.1115/ICONE28-62550
View Paper titled, Effect of Annealing Temperature on Dislocation Loop Absorption And Evolution in Fe by Molecular Dynamics Study
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Topics: Absorption, Annealing, Atoms, Dislocations, Molecular dynamics, Temperature
Proceedings Papers

Uncertainty Quantification for the Development of Mechanistic Hydride Behavior Model for Spent Fuel Cladding Storage and Transportation

Edward M. Duchnowski, Seokbin Seo, Nicholas R. Brown
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A046, August 4–5, 2020
Paper No: ICONE2020-16812
DOI: https://doi.org/10.1115/ICONE2020-16812
View Paper titled, Uncertainty Quantification for the Development of Mechanistic Hydride Behavior Model for Spent Fuel Cladding Storage and Transportation
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Topics: Cladding systems (Building), Spent nuclear fuels, Storage, Transportation systems, Uncertainty quantification, Hydrogen, Diffusion (Physics), Fuels, Temperature profiles, Uncertainty
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
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

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
DOI: 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
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
View Paper titled, Annealing Temperature Effect on Creep Property of CZ Alloy for PWR Modern Fuel Claddings
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Topics: Alloys, Annealing, Creep, Fuels, Pressurized water reactors, Temperature, Zirconium alloys, Stress, China, Cladding systems (Building)
Proceedings Papers

Ceramic High-Temperature Heat-Pipes

Peter Meisel, Wolfgang Lippmann, Antonio Hurtado
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T16A008, July 7–11, 2014
Paper No: ICONE22-30802
DOI: https://doi.org/10.1115/ICONE22-30802
View Paper titled, Ceramic High-Temperature Heat-Pipes
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Topics: Ceramics, Heat pipes, High temperature, Heat, Heat transfer, Fluids, Sodium, Temperature, Annealing, Brazing
Proceedings Papers

Effects of Carbide Precipitate Formation on the Change in Ultrasonic Velocity in Austenitic Stainless Steels

Taira Okita, Junji Etoh, Mitsuyuki Sagisaka, Takashi Matsunaga, Yoshihiro Isobe
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T02A019, July 7–11, 2014
Paper No: ICONE22-30859
DOI: https://doi.org/10.1115/ICONE22-30859
View Paper titled, Effects of Carbide Precipitate Formation on the Change in Ultrasonic Velocity in Austenitic Stainless Steels
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Topics: Stainless steel, Annealing, Carbon, Grain boundaries, Precipitation, Temperature, Ultrasonic testing
Proceedings Papers

Effect of Mo and Bi on Mechanical Properties of Zr-Fe-Cr Alloy at Room Temperature

B. F. Luan, L. Q. Yang, T. G. Wei, K. L. Murty, C. S. Long, 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, V001T02A010, July 29–August 2, 2013
Paper No: ICONE21-15325
DOI: https://doi.org/10.1115/ICONE21-15325
View Paper titled, Effect of Mo and Bi on Mechanical Properties of Zr-Fe-Cr Alloy at Room Temperature
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Topics: Alloys, Mechanical properties, Temperature, Zirconium, Annealing, Tensile strength, Electrons, Elongation, Equipment performance, Heat
Proceedings Papers

The Effect of Fabrication Process on Microstructure Evolution of N18 Alloy Sheets

Xun Dai, Hong Liu, Hongman Jiang, Ying Wang
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 135-140, May 17–21, 2010
Paper No: ICONE18-29339
DOI: https://doi.org/10.1115/ICONE18-29339
View Paper titled, The Effect of Fabrication Process on Microstructure Evolution of N18 Alloy Sheets
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Topics: Alloys, Manufacturing, Hot rolling, Recrystallization, Texture (Materials), Cold rolling, Deformation, Density, Annealing, Electron backscatter diffraction
Proceedings Papers

Investigation of the Beltline Welding Seam and Base Metal of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel

Jan Schuhknecht, Hans-Werner Viehrig, Udo Rindelhardt
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 289-295, July 12–16, 2009
Paper No: ICONE17-75063
DOI: https://doi.org/10.1115/ICONE17-75063
View Paper titled, Investigation of the Beltline Welding Seam and Base Metal of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel
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Topics: Base metals, Reactor vessels, Welding, Metals, Temperature, ASTM International, Irradiation (Radiation exposure), Nuclear power stations, Steel, Testing
Proceedings Papers

Evolution of Microstructure, Microtexture and Texture in Dilute Zirconium Based Structural Components of Pressurised Heavy Water Reactors

D. Srivastava, K. V. Mani Krishna, S. Neogy, G. K. Dey, I. Samajdar, S. Banerjee
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 401-409, July 12–16, 2009
Paper No: ICONE17-75274
DOI: https://doi.org/10.1115/ICONE17-75274
View Paper titled, Evolution of Microstructure, Microtexture and Texture in Dilute Zirconium Based Structural Components of Pressurised Heavy Water Reactors
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Topics: Heavy water reactors, Structural elements (Construction), Texture (Materials), Zirconium, Alloys, Zirconium alloys, Phase transitions, Annealing, Cladding systems (Building), Corrosion
Proceedings Papers

Weld Material Investigations of a WWER-440 Reactor Pressure Vessel: Results From the First Trepan Taken From the Former Greifswald NPP

Udo Rindelhardt, Hans-Werner Viehrig, Joerg Konheiser, Jan Schuhknecht
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, 423-431, May 11–15, 2008
Paper No: ICONE16-48070
DOI: https://doi.org/10.1115/ICONE16-48070
View Paper titled, Weld Material Investigations of a WWER-440 Reactor Pressure Vessel: Results From the First Trepan Taken From the Former Greifswald NPP
Open the PDF for Weld Material Investigations of a WWER-440 Reactor Pressure Vessel: Results From the First Trepan Taken From the Former Greifswald NPP in another window
Topics: Nuclear power stations, Reactor vessels, Fluence (Radiation measurement), Neutrons, Brittleness, Temperature, Cycles, Fracture toughness, Metals, Welded joints
Proceedings Papers

Analysis of Justification for Extension of Operation of Russian NPP With VVER in Aspect of Pressure Vessel Radiation Embrittlement

Gennady I. Borodkin, Inna V. Kaliberda, Nikolay N. Khrennikov
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 163-168, April 25–29, 2004
Paper No: ICONE12-49539
DOI: https://doi.org/10.1115/ICONE12-49539
View Paper titled, Analysis of Justification for Extension of Operation of Russian NPP With VVER in Aspect of Pressure Vessel Radiation Embrittlement
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Topics: Embrittlement, Nuclear power stations, Pressure vessels, Radiation (Physics), Licensing, Safety, Annealing, Databases, Design, Metals