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Proceedings Papers

Finite Element Model to Simulate the Spacer Grid Buckling Characteristics

Youngik Yoo, Joongjin Kim, Kyongbo Eom, Hyeongkoo Kim
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, V001T05A002, August 4–5, 2020
Paper No: ICONE2020-16082
DOI: https://doi.org/10.1115/ICONE2020-16082
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Topics: Buckling, Finite element model, Fuel rods, Manufacturing, Mechanical behavior, Nuclear fuels, Compression, Drag (Fluid dynamics), Impact testing, Mechanical properties
Proceedings Papers

The Experimental Research on the Mechanical Characteristics of the Newly Designed Fuel Rod Supporting Structure of Spacer Grid

Quan-yao Ren, Zeng-ping Pu, Mei-yin Zheng, Jie Chen, Mian Qin, Yuan-Ji Han, Yuan Peng, Ping Chen, Rui-rui Zhao, Jian-wei Li
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, V001T05A004, August 4–5, 2020
Paper No: ICONE2020-16121
DOI: https://doi.org/10.1115/ICONE2020-16121
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Topics: Deformation, Fuel rods, Mechanical properties, Springs, Stress, Deflection, Manufacturing, Neutron flux, Strips
Proceedings Papers

Research of the Rod Drop Time Based on the Control Rod System of TMSR-SF1

Zuokang Lin, Lin Zhu, Chunfeng Zhao, Yun Cao, Xiao Wang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A073, July 2–6, 2017
Paper No: ICONE25-66921
DOI: https://doi.org/10.1115/ICONE25-66921
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Topics: Accidents, Control systems, Density, Disks, Earthquakes, Errors, Experimental methods, Molten salt reactors, Polishing equipment, Rods
Proceedings Papers

Investigation Into the Influence of Fuel Rods on the Anti-Seismic Mechanical Characteristics of Fuel Assembly Spacer Grid by FEM Method

Jingya Sun, Yu Dang, Song Liu, Jiazheng Liu, Libing Zhu
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A052, July 2–6, 2017
Paper No: ICONE25-67362
DOI: https://doi.org/10.1115/ICONE25-67362
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Topics: Finite element methods, Finite element model, Fuel rods, Fuels, Manufacturing, Mechanical properties, Springs, Deflection, Friction, Simulation
Proceedings Papers

Numerical Simulations for Super Large-Scale Natural Draft Cooling Tower With an Optimized Non-Uniform Water Distribution

J. Y. Li, H. Wang, W. Sheng
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A037, July 2–6, 2017
Paper No: ICONE25-67057
DOI: https://doi.org/10.1115/ICONE25-67057
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Topics: Computer simulation, Cooling towers, Water distribution, Sprays, Water, Density, Engineering simulation, Simulation, Cooling, Flow (Dynamics)
Proceedings Papers

Numerical Simulation of Crud Effects on the Flow and Heat Transfer Performance in PWR 17×17 Rod Bundles

Bing Ren, Fujun Gan, Yu Dang, Libing Zhu
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A017, July 2–6, 2017
Paper No: ICONE25-66537
DOI: https://doi.org/10.1115/ICONE25-66537
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Topics: Computer simulation, Flow (Dynamics), Fuel rods, Heat transfer, Pressurized water reactors, Cladding systems (Building), Corrosion, Fuels, Risk, Simulation
Proceedings Papers

Seismic Performance of PCS Water Storage Tank Considering Fluid-Structure Interaction

Hongliang Gou, ZiDuan Shang, Yugang Sun, Meng Chu, Honghui Ge
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A036, July 2–6, 2017
Paper No: ICONE25-66338
DOI: https://doi.org/10.1115/ICONE25-66338
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Topics: Fluid structure interaction, Water storage, Water, Sloshing, Design, Dynamic response, Finite element model, Modal analysis, Shear (Mechanics), Springs
Proceedings Papers

Seism Analysis of Large-Type Radioactive Liquid Tank

Dai Shoutong
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A104, July 2–6, 2017
Paper No: ICONE25-67636
DOI: https://doi.org/10.1115/ICONE25-67636
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Topics: Accidents, Computer software, Finite element model, Leakage, Nuclear engineering, Radioactive wastes, Sloshing, Springs, Three-dimensional models, Weight (Mass)
Proceedings Papers

Numerical and Experimental Analysis of the Control Rod Hydraulic Deceleration Device for the Control Rod Hydraulic Drive System

Qin Benke, Li Leishi, Bo Hanliang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A049, July 2–6, 2017
Paper No: ICONE25-66463
DOI: https://doi.org/10.1115/ICONE25-66463
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Topics: Experimental analysis, Hydraulic drive systems, Cylinders, Temperature, Flow (Dynamics), Scram, Blades, Design, Dynamics (Mechanics), Fuels
Proceedings Papers

A Study on the Sealing Behaviors of the Laterally One Side Restrained C-Ring Under Internal Pressure by Numerical Simulation

Dong Yuanyuan, Luo Ying
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A029, July 2–6, 2017
Paper No: ICONE25-66288
DOI: https://doi.org/10.1115/ICONE25-66288
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Topics: Computer simulation, Pressure, Sealing (Process), Linings (Textiles), Springs, Compression, Deformation, Leakage, Metals, Reactor vessels
Proceedings Papers

Modelling and Analysis of Loviisa NPP Pilot Operated Main Steam Safety Valves

Mika Juntti
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A051, July 2–6, 2017
Paper No: ICONE25-66705
DOI: https://doi.org/10.1115/ICONE25-66705
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Topics: Modeling, Nuclear power stations, Safety, Steam, Valves, Delays, Computer software, Flow (Dynamics), Pressure, Process simulation
Proceedings Papers

Natural Convection: A Case of Simple Harmonics

Shoaib Usman
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A094, July 2–6, 2017
Paper No: ICONE25-67500
DOI: https://doi.org/10.1115/ICONE25-67500
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Topics: Natural convection, Surface roughness, Springs, Convection, Dimensionless numbers, Fluids, Gravity (Force), Kinematics, Rayleigh number, Thermal systems
Proceedings Papers

Mathematical Models of Spacer Grids

Alan B. Maskal, Fatih Aydogan
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A005, June 26–30, 2016
Paper No: ICONE24-60098
DOI: https://doi.org/10.1115/ICONE24-60098
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Topics: Boiling water reactors, Boundary-value problems, Cycles, Databases, Densitometers, Elevations (Drawings), Flow (Dynamics), Fuel rods, Heat transfer, Light water reactors
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

Advanced Cooling Tube Mobile Heat Exchanger in the Outer Shape of a Fuel Assembly for Spent Fuel Pool Cooling

Matthias Reuter, Leo Ornot, Torsten Maier, Thomas Fuchs, Kerstin Gauter, Markus Reck, Joseph Redmond
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, V002T07A010, June 26–30, 2016
Paper No: ICONE24-60676
DOI: https://doi.org/10.1115/ICONE24-60676
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Topics: Cooling, Fuels, Heat exchangers, Manufacturing, Shapes, Spent nuclear fuels, Nuclear power stations, Fukushima nuclear disaster, Japan, 2011, Geometry, Inventions
Proceedings Papers

3-D Base Control Systems for the Seismic Protection of Power Plant Equipment and Buildings

Peter Nawrotzki, Weiqiang Wang
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T06A024, July 29–August 2, 2013
Paper No: ICONE21-15814
DOI: https://doi.org/10.1115/ICONE21-15814
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Topics: Control systems, Power stations, Structures, Nuclear power stations, Safety, Damage, Earthquakes, Machinery, Aircraft, Dampers
Proceedings Papers

Electromagnetic Self-Locking Device for Air Cylinders in Spent Fuel Storage System of Pebble-Bed High Temperature Gas-Cooled Reactor

Bin Wu, Jinhua Wang, Yue Li, Jiguo Liu
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A047, July 29–August 2, 2013
Paper No: ICONE21-16342
DOI: https://doi.org/10.1115/ICONE21-16342
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Topics: Pneumatic cylinders, Spent fuel storage, Very high temperature reactors, Locks (Waterways), Compressed air, Cylinders, Machinery, Spent nuclear fuels, Temperature, Accidents
Proceedings Papers

Seismic Analysis of Lead-Bismuth-Cooled Fast Reactor Vessel

Juan Ma, Mei Huang
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A028, July 29–August 2, 2013
Paper No: ICONE21-15899
DOI: https://doi.org/10.1115/ICONE21-15899
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Topics: Fast neutron reactors, Fluid structure interaction, Seismic analysis, Vessels, Reactor vessels, Earthquakes, Bellows (Equipment), Density, Earthquake resistant design, Finite element analysis
Proceedings Papers

A Three-Dimensional Rigid-Body Model for Seismic Analysis of the Pebble-Bed HTR Graphite Core Structure

Chuan Zeng, Haitao Wang
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A035, July 29–August 2, 2013
Paper No: ICONE21-15896
DOI: https://doi.org/10.1115/ICONE21-15896
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Topics: Graphite, Seismic analysis, Bricks, Shapes, Stress, Center of mass, Collisions (Physics), Computers, Degrees of freedom, Dynamic analysis
Proceedings Papers

Assessing the Integrity of Generator Stator End Windings

Matthew Ellis, Joop Kraijesteijn
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 387-392, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54570
DOI: https://doi.org/10.1115/ICONE20-POWER2012-54570
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Topics: Generators, Stators, Stiffness, Testing, Corrective actions, Dampers, Damping, Excitation, Impulse (Physics), Insulation