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Proceedings Papers

Experimental Study of Motion-Resistance Force of Hydraulic Cylinder of CRHDM

Qianfeng Liu, Yuzheng Li, Huang Zhang, Bo Hanliang
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A006, July 22–26, 2018
Paper No: ICONE26-81214
https://doi.org/10.1115/ICONE26-81214
View Paper titled, Experimental Study of Motion-Resistance Force of Hydraulic Cylinder of CRHDM
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Topics: Hydraulic cylinders, Cylinders, Friction, Leakage, Carbon, Design, Diamonds, Hydraulic control, Hydraulic drive systems, Intellectual property
Proceedings Papers

Research About the Uniform Field Breakdown Strength of Helium Gas at High Temperature and Pressure in Millimeter-Scale Gaps

You Qi, Shi Zhengang, Liu Xingnan, Yan Xunshi, Yang Guojun
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A012, July 22–26, 2018
Paper No: ICONE26-81293
https://doi.org/10.1115/ICONE26-81293
View Paper titled, Research About the Uniform Field Breakdown Strength of Helium Gas at High Temperature and Pressure in Millimeter-Scale Gaps
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Topics: Helium, High temperature, Pressure, Insulation, Design, Very high temperature reactors, Coolants, Engineering standards, High pressure (Physics), Magnetic bearings
Proceedings Papers

Transient Analysis of Fire Protection System at a Nuclear Power Plant Using Computer Code USLAM

Asif H. Arastu, Eugene Tom
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A036, July 22–26, 2018
Paper No: ICONE26-82622
https://doi.org/10.1115/ICONE26-82622
View Paper titled, Transient Analysis of Fire Protection System at a Nuclear Power Plant Using Computer Code USLAM
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Topics: Computers, Fire, Nuclear power stations, Transient analysis, Water hammer, Vacuum, Elevations (Drawings), Valves, Water, Atmospheric pressure
Proceedings Papers

Eulerian Two-Fluid Model for Aerosol Removal in Filtered Containment Venting Scrubbers

Ji-Su Kim, Jong Woon Park, Minkyung Kim
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A018, July 22–26, 2018
Paper No: ICONE26-81506
https://doi.org/10.1115/ICONE26-81506
View Paper titled, Eulerian Two-Fluid Model for Aerosol Removal in Filtered Containment Venting Scrubbers
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Topics: Aerosols, Containment, Fluids, Particulate matter, Drops, Water, Computers, Drag (Fluid dynamics), Flow (Dynamics), Matlab
Proceedings Papers

Study on the Mechanism and Characteristics of Transient Noise of the Steam Discharge Pipes

Lu Dai, Zhiguo Wei, Jun Wu, Yong Liu, Can Ma, Qi Xiao
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A024, July 22–26, 2018
Paper No: ICONE26-81938
https://doi.org/10.1115/ICONE26-81938
View Paper titled, Study on the Mechanism and Characteristics of Transient Noise of the Steam Discharge Pipes
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Topics: Noise (Sound), Pipes, Steam, Transients (Dynamics), Valves, Flow (Dynamics), Collapse, Energy dissipation, Friction, High pressure (Physics)
Proceedings Papers

Experimental Research on the Fluid Induced Forces of Clearance Flow in Canned Motor Reactor Coolant Pump

Rui Xu, Yaoyu Hu, Yun Long, Junlian Yin, Dezhong Wang
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A030, July 22–26, 2018
Paper No: ICONE26-82296
https://doi.org/10.1115/ICONE26-82296
View Paper titled, Experimental Research on the Fluid Induced Forces of Clearance Flow in Canned Motor Reactor Coolant Pump
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Topics: Clearances (Engineering), Engines, Flow (Dynamics), Fluids, Motors, Nuclear reactor coolants, Pumps, Coolants, Stiffness, Boundary-value problems
Proceedings Papers

Research on Auxiliary Bearing Structure With Buffer Shim Based on LS-DYNA for Helium Circulator of HTR-10

Guojun Yang, Zhe Sun, Xingnan Liu, Zhengang Shi
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A013, July 22–26, 2018
Paper No: ICONE26-81304
https://doi.org/10.1115/ICONE26-81304
View Paper titled, Research on Auxiliary Bearing Structure With Buffer Shim Based on LS-DYNA for Helium Circulator of HTR-10
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Topics: Bearings, Helium, Polishing equipment, Rotors, Stress, Damage, Stress concentration, Computer software, Deformation, Finite element methods
Proceedings Papers

Design of the Important Area Airborne Radioactivity Monitoring System and Calculation of the Alarm Threshold of HTR-PM

Wenqian Li, Chuan Li, Jianzhu Cao, Feng Xie
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A007, July 22–26, 2018
Paper No: ICONE26-81232
https://doi.org/10.1115/ICONE26-81232
View Paper titled, Design of the Important Area Airborne Radioactivity Monitoring System and Calculation of the Alarm Threshold of HTR-PM
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Topics: Design, Monitoring systems, Radioactivity, Pressurized water reactors, Coolants, Radiation measurement, Emergencies, Feedback, Gases, Helium
Proceedings Papers

WATCH Loop Development and Commissioning Tests

W. A. Byers, G. Wang
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A037, July 22–26, 2018
Paper No: ICONE26-82626
https://doi.org/10.1115/ICONE26-82626
View Paper titled, WATCH Loop Development and Commissioning Tests
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Topics: Boiling water reactors, Cladding systems (Building), Corrosion, Design, Electricity (Physics), Failure, Flow (Dynamics), Fuel rods, Fuels, Heat flux
Proceedings Papers

Super Critical Carbon Dioxide Brayton Cycle Based Heat Removal System in Nuclear Power Plants

Wei Shuhong, Zheng Hua
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A025, July 22–26, 2018
Paper No: ICONE26-81986
https://doi.org/10.1115/ICONE26-81986
View Paper titled, Super Critical Carbon Dioxide Brayton Cycle Based Heat Removal System in Nuclear Power Plants
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Topics: Brayton cycle, Carbon dioxide, Heat, Nuclear power stations, Safety, Spent nuclear fuels, Compression, Containment, Fukushima nuclear disaster, Japan, 2011, Heat engines
Proceedings Papers

Research on Simplified Method of Transients Combining and Loading in Fatigue Crack Growth Analysis of Carbon Steel Nuclear Piping

Zhenshun Liu, Hongdong Zhen
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A019, July 22–26, 2018
Paper No: ICONE26-81640
https://doi.org/10.1115/ICONE26-81640
View Paper titled, Research on Simplified Method of Transients Combining and Loading in Fatigue Crack Growth Analysis of Carbon Steel Nuclear Piping
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Topics: Carbon steel, Fatigue cracks, Pipes, Transients (Dynamics), Fracture (Materials), Stress, ASME Standards, Fatigue
Proceedings Papers

Filtration Technology Research of Graphite Dust Produced in Spent Fuel Transportation Process in HTR-PM

Jinhua Wang, Bing Wang, Bin Wu, Yue Li, Haitao Wang
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A001, July 22–26, 2018
Paper No: ICONE26-81022
https://doi.org/10.1115/ICONE26-81022
View Paper titled, Filtration Technology Research of Graphite Dust Produced in Spent Fuel Transportation Process in HTR-PM
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Topics: Dust, Filtration, Graphite, Spent nuclear fuels, Transportation systems, Fuels, Gas cooled reactors, High temperature, Nuclear power, Pipelines
Proceedings Papers

Proposal of a Simple Evaluation Method for Sloshing Impact Pressure on Flat Roofs

Shigeru Takaya, Tatsuya Fujisaki
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A031, July 22–26, 2018
Paper No: ICONE26-82562
https://doi.org/10.1115/ICONE26-82562
View Paper titled, Proposal of a Simple Evaluation Method for Sloshing Impact Pressure on Flat Roofs
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Topics: Evaluation methods, Pressure, Roofs, Sloshing, Computational fluid dynamics, Damage, Earthquakes, Fast neutron reactors, Reactor vessels, Slabs
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
https://doi.org/10.1115/ICONE26-82065
View Paper titled, The Compatibility of Nuclear Graphite With Molten Salt in the Molten Salt Reactor
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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

Structural Dynamic Transient Analysis of Fire Protection System at a Nuclear Power Plant

Milton Dong, Eugene Tom
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A038, July 22–26, 2018
Paper No: ICONE26-82627
https://doi.org/10.1115/ICONE26-82627
View Paper titled, Structural Dynamic Transient Analysis of Fire Protection System at a Nuclear Power Plant
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Topics: Fire, Nuclear power stations, Structural dynamics, Transient analysis, Stress, Pipeline risers, Piping systems, Risers (Casting), Pipes, Water hammer
Proceedings Papers

Grounded Control Rod Position Measurement With Two-Electrode Capacitance Sensor

Guang Hu, Benke Qin, Hanliang Bo
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A014, July 22–26, 2018
Paper No: ICONE26-81362
https://doi.org/10.1115/ICONE26-81362
View Paper titled, Grounded Control Rod Position Measurement With Two-Electrode Capacitance Sensor
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Topics: Capacitance, Electrodes, Sensors, Accuracy and precision, Electrical properties, Electronics, Engineering simulation, Finite element methods, Heating, Nuclear reactors
Proceedings Papers

Design of the Sampling Measurement and Radiochemistry Lab in the Nuclear Island of HTR-PM

Mengqi Lou, Wenqian Li, Feng Xie, Jianzhu Cao, Liqiang Wei, Jiejuan Tong, Jiaji Kong
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A020, July 22–26, 2018
Paper No: ICONE26-81701
https://doi.org/10.1115/ICONE26-81701
View Paper titled, Design of the Sampling Measurement and Radiochemistry Lab in the Nuclear Island of HTR-PM
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Topics: Design, Instrumentation, Regulations, Coolants, Dust, Germanium, Helium, Nuclear power stations, Radiation measurement, Radiation measuring instruments
Proceedings Papers

Analytical Study on Fragility Evaluation With Uncertainty Against Fault Displacement for Nuclear Power Plant Buildings

Kenshiro Ishiki, Hirokazu Tsuji, Minoru Kanechika, Yoshinori Mihara
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A002, July 22–26, 2018
Paper No: ICONE26-81072
https://doi.org/10.1115/ICONE26-81072
View Paper titled, Analytical Study on Fragility Evaluation With Uncertainty Against Fault Displacement for Nuclear Power Plant Buildings
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Topics: Displacement, Nuclear power stations, Structures, Uncertainty, Soil, Hazards, Accidents, Building materials, Chaos, Design
Proceedings Papers

Research on Structural Design and Analysis of S-CO 2 Turbine Impeller

Jun Wu, Can Ma, Chunhui Dai, Zhenxing Zhao, Lu Dai, Zhouyang Liu
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A008, July 22–26, 2018
Paper No: ICONE26-81267
https://doi.org/10.1115/ICONE26-81267
View Paper titled, Research on Structural Design and Analysis of S-CO 2 Turbine Impeller
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Topics: Impellers, Structural design, Supercritical carbon dioxide, Turbines, Deformation, Stress, Safety, Blades, Brayton cycle, Carbon
Proceedings Papers

Creep Deformation Analysis of a Pipe Specimen Based on Creep Damage Evaluation Method

Jinya Katsuyama, Yoshihito Yamaguchi, Yinsheng Li
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A032, July 22–26, 2018
Paper No: ICONE26-82568
https://doi.org/10.1115/ICONE26-82568
View Paper titled, Creep Deformation Analysis of a Pipe Specimen Based on Creep Damage Evaluation Method
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Topics: Creep, Damage, Evaluation methods, Pipes, Accidents, Constitutive equations, Failure, Failure analysis, Finite element analysis, Fukushima nuclear disaster, Japan, 2011