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Proceedings Papers

A Study on the Steady-State Flow Behavior of the Boiling-Driven Open Natural Circulation System

Xiaofan Hou, Qianglong Wang, Jinrong Jiu, Hanying Chen, Shiwei Yao

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A046, August 8–12, 2022

Paper No: ICONE29-93372

DOI: https://doi.org/10.1115/ICONE29-93372

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Topics: Boiling, Flow (Dynamics), Steady state, Theoretical analysis

Proceedings Papers

Study on the Radiation Heat Transfer Effect of the Covered Gas Space of the Pool Reactor

Xinyue Luo, Daogang Lu, Jiaqi Feng, Yuhao Zhang

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A040, August 8–12, 2022

Paper No: ICONE29-92323

DOI: https://doi.org/10.1115/ICONE29-92323

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Topics: Heat transfer, Radiation (Physics), Sodium fast reactors, Cavities, Fast neutron reactors, Temperature, Vessels, Computational fluid dynamics, Construction, Containers

Proceedings Papers

The Investigation on Geysering in Scaling Analyses of Natural Circulation

Xiangfei Meng

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A020, August 8–12, 2022

Paper No: ICONE29-89568

DOI: https://doi.org/10.1115/ICONE29-89568

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Topics: Boiling, Boiling water reactors, Circuits, Cycles, Delays, Design, Economics , Engineering prototypes, Flow (Dynamics), Flow instability

Proceedings Papers

Study on Rotor’s Vibration Characteristics of Helium Circulator of HTR

Jiahao 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, V001T06A011, August 4–5, 2020

Paper No: ICONE2020-16347

DOI: https://doi.org/10.1115/ICONE2020-16347

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Topics: Helium, Vibration, Rotors, Shells, Finite element methods, Boilers, Degrees of freedom, Design, Heat, Theoretical analysis

Proceedings Papers

Proportional-Integral Disturbance Observer of Nuclear Reactors

Zhe Dong

Paper No: ICONE2020-16207

DOI: https://doi.org/10.1115/ICONE2020-16207

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Topics: Nuclear reactors, Coolants, Computer simulation, Errors, Heating, Neutron flux, Neutrons, Steady state, Temperature, Theoretical analysis

Proceedings Papers

Finite Element Analysis of AMB Eddy-Current Loss in HTR-PM Primary Helium Circulator

Jinpeng Yu, Yan Zhou, Mo Ni, Guojun Yang, Lei Zhao

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A015, July 22–26, 2018

Paper No: ICONE26-81375

DOI: https://doi.org/10.1115/ICONE26-81375

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Topics: Eddies (Fluid dynamics), Eddy currents (Electricity), Finite element analysis, Helium, Magnetic fields, Rotors, Electromagnetic force, Torque, Magnetic bearings, Rotation

Proceedings Papers

Analysis and Validation of Wilks Nonparametric Uncertainty Method for Best-Estimate Calculations in Nuclear Safety

Deng Cheng-Cheng, Liu Wei-Li, Yang Jun, Wu Qiao

Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A015, July 2–6, 2017

Paper No: ICONE25-66655

DOI: https://doi.org/10.1115/ICONE25-66655

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Topics: Safety, Uncertainty, Emergency core cooling systems, Stability, Accidents, Flow (Dynamics), Nuclear power stations, Response surface methodology, Uncertainty analysis, Uncertainty quantification

Proceedings Papers

Theoretical Analysis of Step-Down of Hydraulic Cylinder Motion for Control Rod Hydraulic Drive System Based on Model II

Qianfeng Liu, Yuzheng Li, Benke Qin, Bo Hanliang

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A041, July 2–6, 2017

Paper No: ICONE25-66364

DOI: https://doi.org/10.1115/ICONE25-66364

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Topics: Hydraulic cylinders, Hydraulic drive systems, Theoretical analysis, Cylinders, Transients (Dynamics), Hydraulic control, Intellectual property, Patents, Pressure

Proceedings Papers

Analysis on Moisture Transfer Behavior in Dehumidifying Process of Low Moisture Content Graphite

Li Jun, Yin Huaqiang, Yang Xingtuan, Jiang Shengyao

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A052, July 2–6, 2017

Paper No: ICONE25-66517

DOI: https://doi.org/10.1115/ICONE25-66517

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Topics: Dehumidification, Graphite, Diffusion (Physics), Seepage (Hydrology), Simulation, Very high temperature reactors, Corrosion, Porosity, Porous materials, Simulation results

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

Shape Characteristics and Condensation Heat Transfer of Supersonic Steam Jet in Subcooled Water

Wang Fangnian, Qin Huan, Chen Yaodong, Bai Ning, Xing Mian, Meng Zhaocan, Shen Feng

Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A102, July 2–6, 2017

Paper No: ICONE25-67604

DOI: https://doi.org/10.1115/ICONE25-67604

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Topics: Condensation, Heat transfer, Shapes, Steam, Subcooling, Water, Nozzles, Pressure, Theoretical analysis, Water temperature

Proceedings Papers

Investigation on Coupling Behaviors of Thermal-Hydraulics/Neutronics Under Asymmetrical Inlet Conditions

Yong Zheng, Min-jun Peng, Geng-lei Xia, Ren Li

Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A067, July 7–11, 2014

Paper No: ICONE22-30522

DOI: https://doi.org/10.1115/ICONE22-30522

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Topics: Thermal hydraulics, Transients (Dynamics), Nuclear power stations, Steady state, Accidents, Neutrons, Safety, Simulation, Temperature, Complex systems

Proceedings Papers

The Treatment of Low-Level Radioactive Wastewater by the Nuclear Weapons Using Ultrasonic Standing Wave Methods

Suxia Hou, Jijun Luo, Bin He, Jun Xu, Rusong Li

Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A008, July 7–11, 2014

Paper No: ICONE22-30532

DOI: https://doi.org/10.1115/ICONE22-30532

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Topics: Nuclear weapons, Sewage, Standing waves, Particulate matter, Decontamination, Radioactive wastes, Ultrasound, Contamination, Hazards, Radiation (Physics)

Proceedings Papers

Relationship Between Flow Pattern and Pressure Distribution in Venturi Scrubber

Naoki Horiguchi, Hiroyuki Yoshida, Akiko Kaneko, Yutaka Abe

Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T15A007, July 7–11, 2014

Paper No: ICONE22-30117

DOI: https://doi.org/10.1115/ICONE22-30117

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Topics: Flow (Dynamics), Pressure, Venturi tubes, Radioactive substances, Accidents, Containment, Countermeasures, Diffusion (Physics), Disasters, Fukushima nuclear disaster, Japan, 2011

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

Theoretical Analysis of Ultrasonic Testing Technique for Dissimilar Metal Weld

Xiyu Liu, Yueming Tang

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, V001T02A016, July 29–August 2, 2013

Paper No: ICONE21-15504

DOI: https://doi.org/10.1115/ICONE21-15504

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Topics: Metals, Theoretical analysis, Ultrasonic testing

Proceedings Papers

Research on the Measurement of Deep Subcriticality Based on Pulsed Neutron Source Method

Shibiao Pan

Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T11A011, July 29–August 2, 2013

Paper No: ICONE21-15883

DOI: https://doi.org/10.1115/ICONE21-15883

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Topics: Neutron sources, Neutrons, Rods, China, Critical points (Physics), Design, Diffusion (Physics), Measurement systems, Neutron flux, Nuclear power

Proceedings Papers

A New Method to Weaken Thermal Stratification Phenomena in Pipes of Nuclear Power Plant

Shengfei Wang, Yuxin Pang, Xiaojing Li, Dandan Fu, Yang Li, Jiaju Yin

Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A019, July 29–August 2, 2013

Paper No: ICONE21-15199

DOI: https://doi.org/10.1115/ICONE21-15199

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Topics: Nuclear power stations, Pipes, Thermal stratification, Heat pipes, Surges, Design, Piping systems, Fatigue, Flow (Dynamics), Heat

Proceedings Papers

Thermal Hydraulic Analysis Code Development for DHRS of SFR

Xiaokun Wang, Donghui Zhang

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A060, July 29–August 2, 2013

Paper No: ICONE21-16543

DOI: https://doi.org/10.1115/ICONE21-16543

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Topics: Sodium fast reactors, Boundary-value problems, Heat, Heat exchangers, Temperature, Transients (Dynamics), China, Drag (Fluid dynamics), Fast neutron reactors, Flow (Dynamics)

Proceedings Papers

Theoretic Analysis on Separation Efficiency of Wire Mesh Mist Eliminator of High-Temperature Gas-Cooled Reactor Helium Purification and Auxiliary System

Huaqiang Yin, Lei Hao, Xingtuan Yang, Xuedong He

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A015, July 29–August 2, 2013

Paper No: ICONE21-15417

DOI: https://doi.org/10.1115/ICONE21-15417

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Topics: Helium, Separation (Technology), Theoretical analysis, Very high temperature reactors, Wire mesh, Accidents, Fluids, Packing (Shipments), Packings (Cushioning), Systems engineering

NARROW

A Study on the Steady-State Flow Behavior of the Boiling-Driven Open Natural Circulation System

Study on the Radiation Heat Transfer Effect of the Covered Gas Space of the Pool Reactor

The Investigation on Geysering in Scaling Analyses of Natural Circulation

Study on Rotor’s Vibration Characteristics of Helium Circulator of HTR

Proportional-Integral Disturbance Observer of Nuclear Reactors

Finite Element Analysis of AMB Eddy-Current Loss in HTR-PM Primary Helium Circulator

Analysis and Validation of Wilks Nonparametric Uncertainty Method for Best-Estimate Calculations in Nuclear Safety

Theoretical Analysis of Step-Down of Hydraulic Cylinder Motion for Control Rod Hydraulic Drive System Based on Model II

Analysis on Moisture Transfer Behavior in Dehumidifying Process of Low Moisture Content Graphite

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

Shape Characteristics and Condensation Heat Transfer of Supersonic Steam Jet in Subcooled Water

Investigation on Coupling Behaviors of Thermal-Hydraulics/Neutronics Under Asymmetrical Inlet Conditions

The Treatment of Low-Level Radioactive Wastewater by the Nuclear Weapons Using Ultrasonic Standing Wave Methods

Relationship Between Flow Pattern and Pressure Distribution in Venturi Scrubber

Fretting Wear of the Zr Fuel Rod Cladding

Theoretical Analysis of Ultrasonic Testing Technique for Dissimilar Metal Weld

Research on the Measurement of Deep Subcriticality Based on Pulsed Neutron Source Method

A New Method to Weaken Thermal Stratification Phenomena in Pipes of Nuclear Power Plant

Thermal Hydraulic Analysis Code Development for DHRS of SFR

Theoretic Analysis on Separation Efficiency of Wire Mesh Mist Eliminator of High-Temperature Gas-Cooled Reactor Helium Purification and Auxiliary System

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