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Proceedings Papers

Effect of Contact Stress on Fretting Corrosion Behavior of Alloy 690 Tube Exposed to Simulated Secondary Water

Wenhua Zhuang, Zhongli Han, Xianglong Guo, Lefu Zhang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A054, August 8–12, 2022
Paper No: ICONE29-92395
DOI: https://doi.org/10.1115/ICONE29-92395
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Topics: Alloys, Corrosion, Stress, Water, Wear
Proceedings Papers

Analysis Method to Predict Grid-to-Rod Fretting Wear of Fuel Rod in Pressurized Water Reactors

Libing Zhu, Shufeng Zhao, Jingya Sun, Shiyin Xu, Fujun Gan, Sirui Li
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A074, August 8–12, 2022
Paper No: ICONE29-93076
DOI: https://doi.org/10.1115/ICONE29-93076
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Topics: Fuel rods, Pressurized water reactors, Wear
Proceedings Papers

The Wear and General Corrosion Properties of Low-Temperature Plasma Nitrided 17-4PH Stainless Steel With a Work-Hardened Sublayer

Zhongli Han, Ping Lai, Wenhua Zhuang, Xianglong Guo, Lefu Zhang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A026, August 8–12, 2022
Paper No: ICONE29-90835
DOI: https://doi.org/10.1115/ICONE29-90835
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Topics: Corrosion, Low temperature, Nitriding, Plasmas (Ionized gases), Stainless steel, Wear
Proceedings Papers

Study of Pre-Oxidization Law and Fretting Wear Resistance of CZ2 Alloy Cladding

Guocheng Sun, Shi Lin, Xu Wang, Liutao Chen
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A088, August 8–12, 2022
Paper No: ICONE29-93804
DOI: https://doi.org/10.1115/ICONE29-93804
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Topics: Alloys, Cladding systems (Building), Wear, Wear resistance
Proceedings Papers

Study on the Application of Electromagnetic Stepping CRDM at Tilted Environment

Zhaohui Lu, Zewen Li, Jianming Zhou, Qingsong Liu
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A005, August 8–12, 2022
Paper No: ICONE29-90150
DOI: https://doi.org/10.1115/ICONE29-90150
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Topics: Design, Engineering prototypes, Failure, Kinematics, Polishing equipment, Pressurized water reactors, Stress, Structural design, Surface finishing, Wear
Proceedings Papers

Research on Fretting Wear of Grid and Cladding Tube Under Simulated Primary Circuit Environment of Pressurized Water Reactor

Tingting Liu, Kun Li, Wenhui Ma, Yuxiang Zhang, Minli Chen, Xiaohang Wu
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A044, August 8–12, 2022
Paper No: ICONE29-91561
DOI: https://doi.org/10.1115/ICONE29-91561
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Topics: Circuits, Cladding systems (Building), Pressurized water reactors, Wear
Proceedings Papers

Flow Induced Vibration and Fretting Wear Characteristics of Fuel Rods

Zhipeng Feng, Huanhuan Qi, Xuan Huang, Guo Chen, Shuai Liu, Yixiong Zhang
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A003, August 4–6, 2021
Paper No: ICONE28-62135
DOI: https://doi.org/10.1115/ICONE28-62135
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Topics: Flow-induced vibrations, Fuel rods, Wear, Fuels, Manufacturing, Design, Fluid density, Pressurized water reactors, Evaluation methods, Excitation
Proceedings Papers

Numerical and Experimental Investigation on Core Assembly Thermal-Gradient-Induced Deformation of Sodium-Cooled Fast Reactor

Zehua Ma, Yingwei Wu, G. H. Su, Wenxi Tian, Suizheng Qiu
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A063, July 22–26, 2018
Paper No: ICONE26-81891
DOI: https://doi.org/10.1115/ICONE26-81891
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Topics: Deformation, Manufacturing, Sodium fast reactors, Temperature gradient, Computation, Displacement, Finite element model, Friction, Reliability, Rods
Proceedings Papers

Research and Engineering Application of Repaired Fuel Assembly Reusing Technique

Lihua Wang, Qingxiang Yang, Ping Yang, Jiazheng Liu, Libing Zhu, Bo Yang, Hong Cao, Zhe Wang, Yang Ding, Jie Ding
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A024, July 2–6, 2017
Paper No: ICONE25-66659
DOI: https://doi.org/10.1115/ICONE25-66659
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Topics: Fuels, Manufacturing, Design, Fuel rods, Nuclear power stations, Economics , Rods, Safety, Computer software, Coolants
Proceedings Papers

Simulation of Small Steam Generator Tube Break (SSGTB) in a Small Pressurized Water Reactor (SPWR)

Huasong Cao
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A014, July 2–6, 2017
Paper No: ICONE25-66637
DOI: https://doi.org/10.1115/ICONE25-66637
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Topics: Boilers, Pressurized water reactors, Simulation, Temperature, Coolants, Corrosion, Design, Flow (Dynamics), Pressure, Pumps
Proceedings Papers

Numerical Simulation of Flow Field Inside Reactor Upper Plenum for PWR With Code_Saturne

Jiawei Liu, Puzhen Gao, Tingting Xu, Jiesheng Min, Guofei Chen
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A119, July 2–6, 2017
Paper No: ICONE25-68008
DOI: https://doi.org/10.1115/ICONE25-68008
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Topics: Computer simulation, Flow (Dynamics), Pressurized water reactors, Design, Computational fluid dynamics, Pressure, Wear, Computer software, Flow-induced vibrations, Manufacturing
Proceedings Papers

Testing the Impact on Emergency Diesel Performance of Water in Diesel Fuel

Robert Cryer, Mark O’Connell
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, V001T01A004, June 26–30, 2016
Paper No: ICONE24-60214
DOI: https://doi.org/10.1115/ICONE24-60214
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Topics: Diesel, Emergencies, Testing, Water, Diesel engines, Engines, Computer software, Contamination, Nuclear power stations, Simulation
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
Paper No: ICONE24-61106
DOI: https://doi.org/10.1115/ICONE24-61106
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Topics: Foundry coatings, Quality control, Hardening, Wear, Erosion, Stress, Cobalt, Contamination, Corrosion resistance, Crack propagation
Proceedings Papers

Numerical Simulation of Fretting Wear of Heat-Transfer Tubes in Steam Generator Under Random Excitation Forces

Lichen Tang, Hao Qian, Yongcheng Xie, Yi Jing, Yongzhong Huo
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, V001T03A017, June 26–30, 2016
Paper No: ICONE24-60630
DOI: https://doi.org/10.1115/ICONE24-60630
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Topics: Boilers, Computer simulation, Heat transfer, Random excitation, Wear, Displacement, Finite element methods, Finite element model, Fluids, Friction
Proceedings Papers

Improvement of FAC Maintenance Program Issued From BRT-CICERO™ via CFD Calculations

Elodie Gipon
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T10A003, June 26–30, 2016
Paper No: ICONE24-60136
DOI: https://doi.org/10.1115/ICONE24-60136
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Topics: Computational fluid dynamics, Maintenance, Pipes, Computer software, Flow (Dynamics), Nuclear power stations, Algorithms, Corrosion, Feedback, Mass transfer
Proceedings Papers

Development of the Pump-Integrated Intermediate Heat Exchanger in Advanced Loop-Type Sodium-Cooled Fast Reactor for Demonstration

Katsunori Amano, Yasuhiro Enuma, Satoshi Futagami, Tomoyuki Inoue, Sota Watanabe
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, V002T06A004, June 26–30, 2016
Paper No: ICONE24-60064
DOI: https://doi.org/10.1115/ICONE24-60064
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Topics: Heat exchangers, Pumps, Sodium fast reactors, Design, Safety, Coolants, Earthquakes, Leakage, Maintainability, Nuclear power
Proceedings Papers

Fretting Wear of the Zr Fuel Rod Cladding

Ladislav Pecinka, Jaroslav Svoboda, Vladimír Zeman
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, V001T03A027, July 7–11, 2014
Paper No: ICONE22-31103
DOI: https://doi.org/10.1115/ICONE22-31103
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Topics: Cladding systems (Building), Fuel rods, Wear, Zirconium, Fuels, Nuclear power stations, Pressurized water reactors, Damage, Failure, Flow (Dynamics)
Proceedings Papers

Application of Leakage-Flux Analysis for Three-Phase Induction Motors

Kohichi Nakayama, Yukio Watanabe, Kenji Osaki, Kotaro Hegi
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, V001T01A010, July 7–11, 2014
Paper No: ICONE22-30593
DOI: https://doi.org/10.1115/ICONE22-30593
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Topics: Electromagnetic induction, Leakage, Motors, Bearings, Electric current, Vibration, Wear
Proceedings Papers

Development of Co-Reduced Valve Seat for Nuclear Power Plants

Toshiyuki Tazawa, Masahiro Saito, Nobuo Kojima
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, V001T02A045, July 29–August 2, 2013
Paper No: ICONE21-16714
DOI: https://doi.org/10.1115/ICONE21-16714
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Topics: Nuclear power stations, Valves, Alloys, Overlays (Materials engineering), Abrasion, Radiation (Physics), Boiling water reactors, Hardness (Materials), Leakage, Mechanical testing
Proceedings Papers

Fretting of Fuel Cladding Materials for Pb Cooled Fast Reactors: Long Term Prediction Using Fretting Maps

Mattia Del Giacco, Alfons Weisenburger, Georg Müller
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, V001T02A050, July 29–August 2, 2013
Paper No: ICONE21-16905
DOI: https://doi.org/10.1115/ICONE21-16905
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Topics: Cladding systems (Building), Fast neutron reactors, Fuels, Steel, Corrosion, Wear, Lead alloys, Nuclear reactors, Stress, Temperature