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Proceedings Papers

Development and Experiment on High Temperature and Radiation Resistance Concrete Material for Spent Fuel Dry Storage

Zhang Xueling, Cheng Cheng, Pan Yongjie, Wei Yuanyuan, Tang Qionghui, Li Zengfen, Yang Shouhai
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A047, August 8–12, 2022
Paper No: ICONE29-92125
DOI: https://doi.org/10.1115/ICONE29-92125
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Topics: Concretes, Fibers, High temperature, Radiation (Physics), Spent nuclear fuels, Steel, Storage, Tension
Proceedings Papers

Effects of Pre-Crack Depth and Hydrogen Absorption on the Failure Strain of Zircaloy-4 Cladding Tubes Under Biaxial Strain Conditions

Feng Li, Takeshi Mihara, Yutaka Udagawa, Masaki Amaya
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A052, August 4–5, 2020
Paper No: ICONE2020-16738
DOI: https://doi.org/10.1115/ICONE2020-16738
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Topics: Absorption, Cladding systems (Building), Failure, Fracture (Materials), Hydrogen, Heat treating (Metalworking), Accidents, Fuels, Manufacturing, Metals
Proceedings Papers

Assessment of Failure Modes of Monolithic Fuel Plates

Hakan Ozaltun, Pavel G. Medvedev, Barry H. Rabin
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A055, July 22–26, 2018
Paper No: ICONE26-82437
DOI: https://doi.org/10.1115/ICONE26-82437
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Topics: Failure mechanisms, Fuels, Plates (structures), Failure, Irradiation (Radiation exposure), Tension, Fuel systems, Porosity, Simulation results, Thermomechanics
Proceedings Papers

RPV Structure Integrity Assessment With Surface Cracks Under PTS

Wei Lu, Zheng He
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A048, July 2–6, 2017
Paper No: ICONE25-66447
DOI: https://doi.org/10.1115/ICONE25-66447
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Topics: Surface cracks, Stress, Transients (Dynamics), Fracture toughness, Cladding systems (Building), Fracture (Materials), Stress concentration, Temperature, Cooling, Finite element methods
Proceedings Papers

Three Dimensional Modeling of the Thermo-Mechanical Performance of the Fuel Rods of a PWR

Wang Zhu, Zhang Chunyu, Li Aolin, Yuan Cenxi
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A001, July 2–6, 2017
Paper No: ICONE25-66010
DOI: https://doi.org/10.1115/ICONE25-66010
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Topics: Fuel rods, Pressurized water reactors, Thermomechanics, Three-dimensional modeling, Stress, Temperature, Accidents, Cladding systems (Building), Displacement, Finite element analysis
Proceedings Papers

Simulation of Behaviors of a One-Third Scale Containment Model Test

Guopeng Ren, Rong Pan, Feng Sun
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A113, July 2–6, 2017
Paper No: ICONE25-67779
DOI: https://doi.org/10.1115/ICONE25-67779
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Topics: Containment, Simulation, Tendons, Concretes, Finite element model, Pressure, Deformation, Nuclear power stations, Design, Safety
Proceedings Papers

Microstructures and Properties of 304L Steel CAP1400 Fuel Bottom Nozzles Prepared by Additive Manufacturing Technology

Li Zongshu, Liu Wentao, Yang Songtao, Hao Ruotong
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A046, July 2–6, 2017
Paper No: ICONE25-67213
DOI: https://doi.org/10.1115/ICONE25-67213
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Topics: Additive manufacturing, Fuels, Nozzles, Steel, Manufacturing, Lasers, Fracture (Materials), Fracture (Process), Ferrites (Magnetic materials), Mechanical properties
Proceedings Papers

Biaxial-EDC Test Attempts With Pre-Cracked Zircaloy-4 Cladding Tubes

Feng Li, Takeshi Mihara, Yutaka Udagawa, Masaki Amaya
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A034, July 2–6, 2017
Paper No: ICONE25-67602
DOI: https://doi.org/10.1115/ICONE25-67602
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Topics: Cladding systems (Building), Failure, Fracture (Materials), Fuels, Stress, Accidents, Bonding, Compression, Crack propagation, Deformation
Proceedings Papers

Research on Tensile Properties of Ni-Base Super Alloy GH3128

Xi Zhao, Yu Zhou, Kun Yuan
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, V001T03A010, June 26–30, 2016
Paper No: ICONE24-60174
DOI: https://doi.org/10.1115/ICONE24-60174
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Topics: Alloys, Tensile strength, Fracture (Materials), Fracture (Process), Plasticity, Temperature, Tension, Very high temperature reactors, Ductile fracture, Heat exchangers
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

Tensioned Metastable Fluid Detectors for High Efficiency Thermal and Fast Neutron Sensitivity

Anthony Sansone, Jeff A. Webster, Rusi P. Taleyarkhan, Brian Archambault
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A057, June 26–30, 2016
Paper No: ICONE24-60757
DOI: https://doi.org/10.1115/ICONE24-60757
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Topics: Fluids, Neutrons, Sensors, Thermal energy, Boron, Heat flux, Ice, Irradiation (Radiation exposure), Methanol, Neutron sources
Proceedings Papers

Outline of Specification for Composite SC Walls in Nuclear Facilities

Saahastaranshu R. Bhardwaj, Amit H. Varma, Taha Al-Shawaf
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, V002T08A009, June 26–30, 2016
Paper No: ICONE24-60960
DOI: https://doi.org/10.1115/ICONE24-60960
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Topics: Composite materials, Nuclear power stations, Design, Shear (Mechanics), Steel, Failure, Safety, Accidents, Anchorage, Bending (Stress)
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
Paper No: ICONE24-60736
DOI: https://doi.org/10.1115/ICONE24-60736
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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
Proceedings Papers

Structural Integrity Research for Reactor Pressure Vessel Under In-Vessel Retention of a Core Melt

Yongjian Gao, Yinbiao He, Ming Cao, Yuebing Li, Shiyi Bao, Zengliang Gao
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, V001T03A005, June 26–30, 2016
Paper No: ICONE24-60092
DOI: https://doi.org/10.1115/ICONE24-60092
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Topics: Reactor vessels, Vessels, Finite element analysis, Creep, Materials properties, Nuclear power stations, Pressure, Accidents, Leakage, Load bearing capacity
Proceedings Papers

Integrity Assessment of Mechanical Components Subjected to Mixed Mode Cracking

Lingfu Zeng, Chouping Luo, Lennart G. Jansson
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, V001T03A032, June 26–30, 2016
Paper No: ICONE24-61097
DOI: https://doi.org/10.1115/ICONE24-61097
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Topics: Fracture (Process), Fracture (Materials), Pipes, Failure, Finite element analysis, Metals, Nuclear power, Stress, Tension
Proceedings Papers

Effect of Bolt Clamping Force and Constraint Arrangement on Structural Strength of Bolted Joint

Jianfeng Mao, Shiyi Bao, Luo Lijia, Zengliang Gao
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, V001T03A014, June 26–30, 2016
Paper No: ICONE24-60409
DOI: https://doi.org/10.1115/ICONE24-60409
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Topics: Bolted joints, Computer simulation, Deformation, Finite element methods, Plates (structures), Failure mechanisms, Friction, Hardware, Shear stress, Simulation
Proceedings Papers

Numerical Simulation of Different Sizes Missing Pellet Surface Effects on Thermal-Mechanical Behaviors in Nuclear Fuel Rods

Changbing Tang, Yongjun Jiao, Wenjie Li, Tao Qing, Yifei Miao, Ping Chen
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, V001T02A008, June 26–30, 2016
Paper No: ICONE24-60116
DOI: https://doi.org/10.1115/ICONE24-60116
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Topics: Computer simulation, Fuel rods, Cladding systems (Building), Irradiation (Radiation exposure), Nuclear fission, Stress, Creep, Temperature, Compressive stress, Failure
Proceedings Papers

Characterization and Optimization of a Tensioned Metastable Fluid Nuclear Particle Sensor Using Laser Based Profilimetry

Alexander R. Hagen, Thomas F. Grimes, Brian C. Archambault, Trevor N. Harris, Rusi P. Taleyarkhan
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A036, July 7–11, 2014
Paper No: ICONE22-30325
DOI: https://doi.org/10.1115/ICONE22-30325
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Topics: Fluids, Lasers, Optimization, Particulate matter, Sensors, Simulation, Cavitation, Ions, Neutrons, Acoustics
Proceedings Papers

High Efficiency Gamma-Beta Blind Alpha Spectrometry for Nuclear Energy Applications

Jeffrey A. Webster, Alexander Hagen, Brian C. Archambault, Nicholas Hume, Rusi Taleyarkhan
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A054, July 7–11, 2014
Paper No: ICONE22-30821
DOI: https://doi.org/10.1115/ICONE22-30821
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Topics: Alpha decay, Bubble chambers, Cascades (Fluid dynamics), Centrifugal force, Drops, Fluids, Isotopes, Neutrons, Nuclear fission, Nuclear industry
Proceedings Papers

A Computational Modeling Tool for Welding Repair of Irradiated Materials

Zhili Feng, Ken Wolfe, Eric Willis
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, V001T01A038, July 29–August 2, 2013
Paper No: ICONE21-16472
DOI: https://doi.org/10.1115/ICONE21-16472
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Topics: Computer simulation, Cracking (Materials), Fracture (Process), Helium, Maintenance, Welding, Bubbles, Fracture (Materials), Heat, Stress