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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
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
Publisher: American Society of Mechanical Engineers
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

The Research of Corrosion Resistance of CZ2 Zirconium Alloy Welding Specimens

Yang Xu, Liu-Tao Chen, Chang-Yuan Gao, Jun Tan, Lin Shi
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A092, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93838
https://doi.org/10.1115/ICONE29-93838
View Paper titled, The Research of Corrosion Resistance of CZ2 Zirconium Alloy Welding Specimens
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Topics: Corrosion, Corrosion resistance, Weight (Mass), Welding, Zirconium alloys
Proceedings Papers

High Temperature Oxidation Kinetics of Zr-Sn-Nb Alloy and the Effect of Its Oxide Film Growth On Corrosion Resistance

Wanqian Zhao
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A083, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93520
https://doi.org/10.1115/ICONE29-93520
View Paper titled, High Temperature Oxidation Kinetics of Zr-Sn-Nb Alloy and the Effect of Its Oxide Film Growth On Corrosion Resistance
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Topics: Alloys, Corrosion resistance, High temperature, Oxidation, Tin, Zirconium, Zirconium alloys
Proceedings Papers

Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod

Kaiyuan Wang, Xiaohan Liu, Xin Jin
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A021, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89917
https://doi.org/10.1115/ICONE29-89917
View Paper titled, Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod
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Topics: Absorption, Boron, Cladding systems (Building), Corrosion resistance, Design, Fuels, Irradiation (Radiation exposure), Manufacturing, Neutrons, Nuclear fission
Proceedings Papers

The Research on Welding Procedure and Performance of Zr-3 Thick Plate

Yu Gao, Xiaoru Liang, Yuxin Wang, Lifeng Guo
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A021, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92037
https://doi.org/10.1115/ICONE29-92037
View Paper titled, The Research on Welding Procedure and Performance of Zr-3 Thick Plate
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Topics: Corrosion resistance, Heat treating (Metalworking), Mechanical properties, Welding, Zirconium
Proceedings Papers

Corrosion Behavior of Iron-Chrome Alloys in Liquid Bismuth

Toshihide Takai, Tomohiro Furukawa, Shigeki Watanabe, Noriko S. Ishioka
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T03A002, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63277
https://doi.org/10.1115/ICONE28-63277
View Paper titled, Corrosion Behavior of Iron-Chrome Alloys in Liquid Bismuth
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Topics: Alloys, Corrosion, Corrosion resistance, Iron, Oxygen, Stainless steel, Cancer, Fast neutron reactors, Irradiation (Radiation exposure), Mass production
Proceedings Papers

Study on the Thermal-Mechanical Performance of SiC Composites Cladding Under Multiple Conditions

Chunyu Yin
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T05A013, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16793
https://doi.org/10.1115/ICONE2020-16793
View Paper titled, Study on the Thermal-Mechanical Performance of SiC Composites Cladding Under Multiple Conditions
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Topics: Cladding systems (Building), Composite materials, Failure, Hoop stress, Fracture toughness, Probability, Temperature, Accidents, Brittleness, Ceramics
Proceedings Papers

Corrosion Property of Container Using Hybrid Material for Thermal Decomposition Process of Sulfuric Acid

Ikuo Ioka, Yoshiro Kuriki, Jin Iwatsuki, Daisuke Kawai, Yoshiyuki Inagaki, Shinji Kubo, Yoshiyuki Inagaki
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T06A026, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16783
https://doi.org/10.1115/ICONE2020-16783
View Paper titled, Corrosion Property of Container Using Hybrid Material for Thermal Decomposition Process of Sulfuric Acid
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Topics: Boiling, Containers, Corrosion, Hydrogen production, Corrosion resistance, Lasers, Plasma spraying, Base metals, Ductility, Heat
Proceedings Papers

Operational Impacts and Consequences of Piping Component Failure: A Review of Operating Experience Data As Recorded in CODAP

Braedon Carr, Bengt Lydell, Jovica R. Riznic
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A001, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81001
https://doi.org/10.1115/ICONE26-81001
View Paper titled, Operational Impacts and Consequences of Piping Component Failure: A Review of Operating Experience Data As Recorded in CODAP
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Topics: Failure, Pipes, Water, Chemistry, Transients (Dynamics), Accidents, Boiling water reactors, Control systems, Corrosion, Corrosion resistance
Proceedings Papers

Stress Corrosion Behaviors of Three Typical Materials (304L, 2205, Alloy 825) in Boiling Magnesium Chloride Solution

Liang Zhao, Kunjie Luo
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A060, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66711
https://doi.org/10.1115/ICONE25-66711
View Paper titled, Stress Corrosion Behaviors of Three Typical Materials (304L, 2205, Alloy 825) in Boiling Magnesium Chloride Solution
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Topics: Alloys, Boiling, Magnesium (Metal), Stress corrosion cracking, Stainless steel, Corrosion, Corrosion resistance, Steel, Temperature
Proceedings Papers

Corrosion Susceptibility in High Temperature Liquid/Vapor Environments of Materials for Tubing of Heavy-Water Collection System in CANDU Nuclear Power Plant

Guangfu Li, Liang Zhao, Xinghong Yang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A086, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67218
https://doi.org/10.1115/ICONE25-67218
View Paper titled, Corrosion Susceptibility in High Temperature Liquid/Vapor Environments of Materials for Tubing of Heavy-Water Collection System in CANDU Nuclear Power Plant
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Topics: Corrosion, High temperature, Nuclear power stations, Tubing, Vapors, Water, Stainless steel, Temperature, Alloys, Carbon steel
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
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
Publisher: American Society of Mechanical Engineers
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
Proceedings Papers

HIPed Hard Facings for Nuclear Applications: Materials, Key Potential Defects and Mitigating Quality Control Measures

John Sulley, David Stewart
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T03A034, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-61106
https://doi.org/10.1115/ICONE24-61106
View Paper titled, HIPed Hard Facings for Nuclear Applications: Materials, Key Potential Defects and Mitigating Quality Control Measures
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Topics: Foundry coatings, Quality control, Hardening, Wear, Erosion, Stress, Cobalt, Contamination, Corrosion resistance, Crack propagation
Proceedings Papers

Investigation on Thermal Treatments of High-Resistance Austenitic Stainless Steels Employed as Structural Materials in Generation IV Reactors

Giulia B. Mazzei, Rosa Lo Frano, James F. Stubbins
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A052, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60710
https://doi.org/10.1115/ICONE24-60710
View Paper titled, Investigation on Thermal Treatments of High-Resistance Austenitic Stainless Steels Employed as Structural Materials in Generation IV Reactors
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Topics: Alloys, Corrosion resistance, Damage, Generation IV reactors, Irradiation (Radiation exposure), Mechanical properties, Neutrons, Nuclear reactors, Nucleation (Physics), Sodium fast reactors
Proceedings Papers

Investigation of Liquid Metal Embrittlement of AISI 316L Steels

L. Stefanini, Rosa Lo Frano, Erich Stergar
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A072, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60969
https://doi.org/10.1115/ICONE24-60969
View Paper titled, Investigation of Liquid Metal Embrittlement of AISI 316L Steels
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Topics: Embrittlement, Liquid metals, Steel, Coolants, Corrosion resistance, Electrical conductivity, Electromagnetic scattering, Fracture (Materials), Fracture (Process), Irradiation (Radiation exposure)
Proceedings Papers

Fracture Resistance of Cast Austenitic Stainless Steels

Y. Chen, W-Y. Chen, A. S. Rao, Z. Li, Y. Yang, B. Alexandreanu, K. Natesan
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T03A022, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60736
https://doi.org/10.1115/ICONE24-60736
View Paper titled, Fracture Resistance of Cast Austenitic Stainless Steels
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Topics: Fracture (Materials), Stainless steel, Neutrons, Irradiation (Radiation exposure), Ferrites (Magnetic materials), Fracture toughness, Alloys, Embrittlement, Light water reactors, Corrosion resistance