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Proceedings Papers

Design Development of a Nuclear Standard Bidirectional Solenoid Valve to Enable PWR Fluid System Simplification

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A001, July 29–August 2, 2013

Paper No: ICONE21-15112

DOI: https://doi.org/10.1115/ICONE21-15112

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Topics: Design, Fluids, Pressurized water reactors, Solenoids, Valves, Water, Maintenance, Petrochemicals, Pneumatic control valves, Pneumatic systems

Proceedings Papers

Experimental Study of a Gas Separator for MSR Gas Removal System

Nana Zhang, Changqi Yan, Licheng Sun

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A040, July 29–August 2, 2013

Paper No: ICONE21-16124

DOI: https://doi.org/10.1115/ICONE21-16124

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Topics: Molten salt reactors, Separation (Technology), Water, Pressure drop, Flow (Dynamics), Breeder reactors, Bubbles, Conceptual design, Design, Fluids

Proceedings Papers

Several Constraint Methods for Avoiding Thermal Stress Distortion on Structure Simulating Calculation

Shoutong Dai, Hao Yin

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A014, July 29–August 2, 2013

Paper No: ICONE21-15405

DOI: https://doi.org/10.1115/ICONE21-15405

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Topics: Thermal stresses

Proceedings Papers

Scientific Bases of Water Chemistry for Corrosion Control of NPPs by Integration of Radiation- and Electro-Chemistry

Genn Saji

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A053, July 29–August 2, 2013

Paper No: ICONE21-16525

DOI: https://doi.org/10.1115/ICONE21-16525

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Topics: Corrosion, Corrosion protection, Electrochemistry, Nuclear power stations, Radiation (Physics), Water, Water chemistry

Proceedings Papers

The Impact of the High Temperature on the Performance of Critical Components in the HTR-PM Control Rod Drive Mechanism

Cheng Chen, Xingzhong Diao

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A027, July 29–August 2, 2013

Paper No: ICONE21-15559

DOI: https://doi.org/10.1115/ICONE21-15559

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Topics: Dampers, High temperature, Permanent magnets, Stepper motors, Temperature, Emergencies, Engines, Mechanical properties, Motors, Reliability

Proceedings Papers

Researches on the Simulation of the Degasifying Column Used in Nuclear Power Plant

Jianhua Xie, Quanliu Ye, Jinchun Yang

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A002, July 29–August 2, 2013

Paper No: ICONE21-15113

DOI: https://doi.org/10.1115/ICONE21-15113

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Topics: Nuclear power stations, Simulation, Computer software, Nuclear reactor coolants, Oxygen, Process simulation, Risk, Simulation results

Proceedings Papers

The Position Design for M310 Reactor Vessel’s Instrumentation Penetration Based on None-Alignment Analysis

Xin Xia, Hua Du, Ning Li, Bin Xu, Yan Li, Wei Zhao

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A041, July 29–August 2, 2013

Paper No: ICONE21-16177

DOI: https://doi.org/10.1115/ICONE21-16177

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Topics: Design, Instrumentation

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

Proceedings Papers

The Reliability Prediction of HTR’s Graphite Component in Various Temperature and Neutron Dose Levels

Xiang Fang, Haitao Wang, Xingtuan Yang, Suyuan Yu

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A028, July 29–August 2, 2013

Paper No: ICONE21-15574

DOI: https://doi.org/10.1115/ICONE21-15574

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Topics: Graphite, Neutrons, Reliability, Temperature, Bricks, High temperature, Irradiation (Radiation exposure), Stress, Constitutive equations, Failure

Proceedings Papers

Analyzing and Comparing the Floor Response Spectra of the NPP Based on Different Soil Dynamic Numerical Models

Xiu-yun Zhu, Rong Pan

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A054, July 29–August 2, 2013

Paper No: ICONE21-16627

DOI: https://doi.org/10.1115/ICONE21-16627

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Topics: Computer simulation, Nuclear power stations, Soil, Spectra (Spectroscopy)

Proceedings Papers

Experimental Investigations of Control Rod Drive Mechanism

Guangyao Lu, Zhaohui Lu, Wenyuan Xiang, Yonghong Lv, Wenyou Huang, Jianming Zhou

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A003, July 29–August 2, 2013

Paper No: ICONE21-15196

DOI: https://doi.org/10.1115/ICONE21-15196

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Topics: Accidents, China, Design, Nuclear power, Nuclear power stations, Nuclear reactors, Pressurized water reactors, Reactor vessels, Rods, Signals

Proceedings Papers

Research of the Effects on a Nuclear Cable Material Irradiated by Beta/Gamma Irradiation

Weixia Zhong, Jiansheng Sun, Jinping Liu, Ping Sun

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A042, July 29–August 2, 2013

Paper No: ICONE21-16198

DOI: https://doi.org/10.1115/ICONE21-16198

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Topics: Cables, Gamma rays, Irradiation (Radiation exposure)

Proceedings Papers

Results and Discussion on Scaling Analysis for the NHR200-II Integral Test Facility Under Single Phase Natural Circulation

Yang Liu, Qianqian Jia, Haijun Jia, Lei Wu

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A029, July 29–August 2, 2013

Paper No: ICONE21-15659

DOI: https://doi.org/10.1115/ICONE21-15659

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Topics: Test facilities, Fluids, Density, Engineering prototypes, Flow (Dynamics), Heat flux, Heating, Pressure, Seawater, Steam

Proceedings Papers

Shaking Table Tests and Numerical Simulation Analysis of a 1:15 Scale Model Reinforced Concrete Containment Vessel

Xiaolei Wang, Dagang Lu, Gangling Hou

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A055, July 29–August 2, 2013

Paper No: ICONE21-16668

DOI: https://doi.org/10.1115/ICONE21-16668

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Topics: Computer simulation, Containment vessels, Reinforced concrete, Earthquakes, Excitation, Cracking (Materials), Cylinders, Design, Displacement, Engineering prototypes

Proceedings Papers

Prospective Applications of Flow Drag and Noise Reduction Technology for Nuclear Reactors

Beibei Feng, Darong Chen, Xingtuan Yang, Shengyao Jiang

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A016, July 29–August 2, 2013

Paper No: ICONE21-15427

DOI: https://doi.org/10.1115/ICONE21-15427

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Topics: Drag (Fluid dynamics), Flow (Dynamics), Noise control, Nuclear reactors, Cooling, Helium, Noise (Sound), Water, Engineering systems and industry applications, Heat transfer

Proceedings Papers

Identification of Flexible Rotor Suspended by Magnetic Bearings

Zhe Sun, Jingjing Zhao, Zhengang Shi, Suyuan Yu

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A043, July 29–August 2, 2013

Paper No: ICONE21-16220

DOI: https://doi.org/10.1115/ICONE21-16220

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Topics: Magnetic bearings, Rotors, Bearings, Stiffness, Very high temperature reactors, Degrees of freedom, Design, Force sensors, Helium

Proceedings Papers

Study on the Prestressing Effect in Reinforced Concrete Containment by Using ANSYS

Feng Sun, Rong Pan

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A004, July 29–August 2, 2013

Paper No: ICONE21-15241

DOI: https://doi.org/10.1115/ICONE21-15241

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Topics: Containment, Design, Pressure, Reinforced concrete, Tendons

Proceedings Papers

Comparative Study on Self-Compacting Concrete Pouring Methods of AP1000 Structure Module

Shuai Dai, Zhonghao Ye, Erfei Li, Chuyao Zheng

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A056, July 29–August 2, 2013

Paper No: ICONE21-16823

DOI: https://doi.org/10.1115/ICONE21-16823

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Topics: Compacting, Concrete placement, Concretes, Construction, Modular construction

Proceedings Papers

Evaluation of Interaction Effects on Part-Through Cracks in Steam Generator Tubes

Yong-Seok Kang, Hong-Deok Kim, Kuk-Hee Lee, Jai-Hak Park

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A017, July 29–August 2, 2013

Paper No: ICONE21-15429

DOI: https://doi.org/10.1115/ICONE21-15429

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Topics: Boilers, Fracture (Materials), Pressure

Proceedings Papers

Numerical Study of the Gas-Steam Transient Behavior in the Integrated Pressurizer

Lei Wu, Haijun Jia, Yang Liu

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A030, July 29–August 2, 2013

Paper No: ICONE21-15660

DOI: https://doi.org/10.1115/ICONE21-15660

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Topics: Steam, Transients (Dynamics), Pressure, Heating, Temperature, Boiling, High temperature, Nitrogen, Plasma spraying, Safety

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NARROW

Design Development of a Nuclear Standard Bidirectional Solenoid Valve to Enable PWR Fluid System Simplification

Experimental Study of a Gas Separator for MSR Gas Removal System

Several Constraint Methods for Avoiding Thermal Stress Distortion on Structure Simulating Calculation

Scientific Bases of Water Chemistry for Corrosion Control of NPPs by Integration of Radiation- and Electro-Chemistry

The Impact of the High Temperature on the Performance of Critical Components in the HTR-PM Control Rod Drive Mechanism

Researches on the Simulation of the Degasifying Column Used in Nuclear Power Plant

The Position Design for M310 Reactor Vessel’s Instrumentation Penetration Based on None-Alignment Analysis

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

The Reliability Prediction of HTR’s Graphite Component in Various Temperature and Neutron Dose Levels

Analyzing and Comparing the Floor Response Spectra of the NPP Based on Different Soil Dynamic Numerical Models

Experimental Investigations of Control Rod Drive Mechanism

Research of the Effects on a Nuclear Cable Material Irradiated by Beta/Gamma Irradiation

Results and Discussion on Scaling Analysis for the NHR200-II Integral Test Facility Under Single Phase Natural Circulation

Shaking Table Tests and Numerical Simulation Analysis of a 1:15 Scale Model Reinforced Concrete Containment Vessel

Prospective Applications of Flow Drag and Noise Reduction Technology for Nuclear Reactors

Identification of Flexible Rotor Suspended by Magnetic Bearings

Study on the Prestressing Effect in Reinforced Concrete Containment by Using ANSYS

Comparative Study on Self-Compacting Concrete Pouring Methods of AP1000 Structure Module

Evaluation of Interaction Effects on Part-Through Cracks in Steam Generator Tubes

Numerical Study of the Gas-Steam Transient Behavior in the Integrated Pressurizer

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