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Proceedings Papers

Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development

Guoqiang Wang, William A. Byers, Zeses Karoutas
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A041, August 4–6, 2021
Paper No: ICONE28-66591
DOI: https://doi.org/10.1115/ICONE28-66591
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Topics: Accidents, Cladding systems (Building), Critical heat flux, Fuels, Chemistry, Pressurized water reactors, Coolants, Electrical resistivity, Film boiling, Heat flux
Proceedings Papers

Investigation on Solidification Behavior of Deposited Metal by GTAW With ERNiCrFe-13 Wire

Xiao Guo, Kai Xu, Xiaochun Lv, Peiyin Chen, Bo Chen, Shubin Huo
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T10A001, August 4–6, 2021
Paper No: ICONE28-63770
DOI: https://doi.org/10.1115/ICONE28-63770
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Topics: Gas tungsten arc welding, Metals, Solidification, Wire, Temperature, Cracking (Materials), Fracture (Process), Differential scanning calorimetry, Ductility, Lasers
Proceedings Papers

First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM

Alessandro Scolaro, Ivor Clifford, Carlo Fiorina, Andreas Pautz
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A051, July 22–26, 2018
Paper No: ICONE26-82381
DOI: https://doi.org/10.1115/ICONE26-82381
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Topics: Nuclear fuels, Temperature, Electrical conductance, Fuels, Materials properties, Cracking (Materials), Creep, Databases, Fracture (Process), Fuel rods
Proceedings Papers

Numerical Impact Simulation of Aircraft Into Reinforced Concrete Walls With Different Thickness

Kazuma Hirosaka, Hidekazu Takazawa, Katsumasa Miyazaki, Norihide Tohyama, Hiroyuki Nouji, Naomi Matsumoto
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A047, July 22–26, 2018
Paper No: ICONE26-82616
DOI: https://doi.org/10.1115/ICONE26-82616
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Topics: Aircraft, Reinforced concrete, Simulation, Phantoms, Concrete walls, Simulation models, Computer simulation, Damage, Impact testing, Kinematics
Proceedings Papers

New Needs of Fracture Mechanic Analysis at Design and Operation Level: Status of French Nuclear Mechanical Codes

Claude Faidy
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A002, July 22–26, 2018
Paper No: ICONE26-81096
DOI: https://doi.org/10.1115/ICONE26-81096
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Topics: Design, Fracture (Materials), Fracture (Process), Boilers, Brittle fracture, Brittleness, Failure, In-service inspection, Leak-before-break, Manufacturing
Proceedings Papers

A Theoretical Model of the Stress Intensity Factor Threshold of DHC for Fuel Cladding Tube

Liang Chen, Lili Liu, Xiaoming Song, Hua Pang
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A031, July 22–26, 2018
Paper No: ICONE26-81665
DOI: https://doi.org/10.1115/ICONE26-81665
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Topics: Cladding systems (Building), Fuels, Stress, Temperature, Fracture (Materials), Temperature gradient, Cracking (Materials), Diffusion (Physics), Fracture (Process), Hydrogen
Proceedings Papers

Thermal Hydraulic Analysis of Pressurized Thermal Shock for Loviisa NPP Using Apros Simulation Code

Gintaras Žemulis, Pasi Junninen, Petri Kytömäki
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A051, July 22–26, 2018
Paper No: ICONE26-81558
DOI: https://doi.org/10.1115/ICONE26-81558
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Topics: Nuclear power stations, Simulation, Thermal shock, Safety, Emergencies, Reactor vessels, Embrittlement, Heat, Boundary-value problems, Cooling
Proceedings Papers

The Compatibility of Nuclear Graphite With Molten Salt in the Molten Salt Reactor

Zhoutong He, Hui Tang, Can Zhang, Yantao Gao, Huihao Xia, Xingtai Zhou
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A026, July 22–26, 2018
Paper No: ICONE26-82065
DOI: https://doi.org/10.1115/ICONE26-82065
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Topics: Graphite, Molten salt reactors, Temperature, Strength (Materials), Thermal expansion, Coolants, Fracture (Materials), Fracture (Process), Irradiation (Radiation exposure), Pressure
Proceedings Papers

An Image-Based Micro-Scale Fracture Model for Weld Zone in Nuclear Pipe and Component

Xiaoming Bai, Liangang Zheng, Xinjun Wang, Xi Lv
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A047, July 2–6, 2017
Paper No: ICONE25-66441
DOI: https://doi.org/10.1115/ICONE25-66441
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Topics: Fracture (Materials), Fracture (Process), Microscale devices, Pipes, Finite element analysis, Boundary-value problems, Damping, Engineering standards, Materials properties, Mechanical properties
Proceedings Papers

Investigation on DDC Susceptibility of 690 Nickel-Alloy Welding Wire

Yu Gu, Bo Zuo, Junbao Zhang, Yifeng Huang, Yan Yu
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A027, July 2–6, 2017
Paper No: ICONE25-66271
DOI: https://doi.org/10.1115/ICONE25-66271
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Topics: Nickel alloys, Welding, Wire, Metals, Fracture (Process), Nickel, Alloys, Cladding systems (Building), Ductility, Electron backscatter diffraction
Proceedings Papers

Case Study Analyses of Flaw Growth and Tolerance of Stainless Steel Canisters in Marine Environment

Chang Heui-Yung
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A094, July 2–6, 2017
Paper No: ICONE25-67301
DOI: https://doi.org/10.1115/ICONE25-67301
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Topics: Stainless steel, Storage, Temperature, Climate, Cracking (Materials), Fracture (Process), Nuclear fuels, Nuclear power stations, Shells, Spent fuel storage
Proceedings Papers

Stress Corrosion Cracking Behavior in Liquid/Vapors of Boiling Magnesium Chloride Solution of 304L/316L/690 for Heavy-Water Collection Tubing in CANDU Nuclear Power Plant

Guangfu Li, Liang Zhao, Xinghong Yang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A095, July 2–6, 2017
Paper No: ICONE25-67314
DOI: https://doi.org/10.1115/ICONE25-67314
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Topics: Boiling, Magnesium (Metal), Nuclear power stations, Stress corrosion cracking, Tubing, Vapors, Water, Cracking (Materials), Fracture (Process), Alloys
Proceedings Papers

Verification of Probabilistic Fracture Mechanics Analysis Code PASCAL

Yinsheng Li, Genshichiro Katsumata, Koichi Masaki, Shotaro Hayashi, Yu Itabashi, Masaki Nagai, Masahide Suzuki, Yasuhiro Kanto
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A050, July 2–6, 2017
Paper No: ICONE25-66468
DOI: https://doi.org/10.1115/ICONE25-66468
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Topics: Fracture mechanics, Fracture (Process), Embrittlement, Irradiation (Radiation exposure), Light water reactors, Neutrons, Nuclear power, Nuclear power stations, Pressure, Reactor vessels
Proceedings Papers

The Fracture Behavior of Hydrogen-Charged A508III Low Alloy Steel in the Process of Natural Hydrogen-Escaping

Qian Xiao, Zhanpeng Lu, Junjie Chen, Hao Peng
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A088, July 2–6, 2017
Paper No: ICONE25-67246
DOI: https://doi.org/10.1115/ICONE25-67246
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Topics: Alloy steel, Fracture (Materials), Fracture (Process), Hydrogen, Brittle fracture, Steel, Tensile strength, Brittleness, Current density, Dislocation density
Proceedings Papers

Small Punch Test on Mechanical Properties of Molybdenum Single Crystal Weld

Yan Ma, Jianju Wang, Jinyun Lei
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A033, July 2–6, 2017
Paper No: ICONE25-66824
DOI: https://doi.org/10.1115/ICONE25-66824
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Topics: Crystals, Mechanical properties, Molybdenum, Displacement, Stress, Yield strength, Brittleness, Creep, Electron beam welding, Embrittlement
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

Composite Versus Dispersed Accident Tolerant Nuclear Fuels

Jayangani Ranasinghe, Barbara Szpunar, Ericmoore Jossou, Linu Malakkal, Jerzy A. Szpunar
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A056, July 2–6, 2017
Paper No: ICONE25-67478
DOI: https://doi.org/10.1115/ICONE25-67478
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Topics: Accidents, Composite materials, Nuclear fuels, Fuels, Temperature, Temperature gradient, Thermal conductivity, Aluminum, Approximation, Cracking (Materials)
Proceedings Papers

Microstructure and Properties Analysis of Inner Cladding Tube and End Plug Girth Weld of Annular Fuel Element

Ji Pengbo, Lu Hanghang, Wang Zhaosong, Zhang Zhoufeng, Liu Bin
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A048, July 2–6, 2017
Paper No: ICONE25-67243
DOI: https://doi.org/10.1115/ICONE25-67243
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Topics: Cladding systems (Building), Fuels, Welding, Fracture (Materials), Fracture (Process), Microhardness, Heat, Pressurized water reactors, Tensile strength, Welded joints
Proceedings Papers

The Root Cause Analysis of the Bolt Fracture in the Nuclear Power Plant Essential Service Water System

Li Nan, Lao Yi, Che Yinhui
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, V001T01A047, July 2–6, 2017
Paper No: ICONE25-67885
DOI: https://doi.org/10.1115/ICONE25-67885
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Topics: Fracture (Materials), Fracture (Process), Nuclear power stations, Root cause analysis, Water, Corrosion, Pumps, Heat treating (Metalworking), Spectroscopy, Stainless steel