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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, V001T03A009, August 4–5, 2020

Paper No: ICONE2020-16351

DOI: https://doi.org/10.1115/ICONE2020-16351

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Topics: Building materials, Computer simulation, Buoyancy, Air flow, China, Energy dissipation, Flow (Dynamics), Modeling, Natural convection, Permeability

Proceedings Papers

Research on Hydraulic Model Test of Pumping Station Forebay

Jiale Jian, Fang Wang, Rongyong Zhang, Benjing Tang

Paper No: ICONE2020-16782

DOI: https://doi.org/10.1115/ICONE2020-16782

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Topics: Nuclear power stations, Pumping stations, Pumps, Water distribution, Flow (Dynamics), Turning angles, Tunnels, Energy dissipation, Seawater

Proceedings Papers

Development of Evaluation Method for Thermal Stratification by Cavity Flow in a Vertical Branch Pipe With Elbow and Horizontal Section: Experimental Results

Atsushi Kodama, Yoshiteru Komuro, Keiichi Hori, Hironori Noguchi, Yoshiyuki Kondo, Koichi Tanimoto

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A014, July 22–26, 2018

Paper No: ICONE26-81143

DOI: https://doi.org/10.1115/ICONE26-81143

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Topics: Cavity flows, Evaluation methods, Pipes, Thermal stratification, Flow (Dynamics), Water, Fatigue, High temperature, Temperature, Temperature profiles

Proceedings Papers

A Numerical Study on Graphite Dust Deposition on Steam Generator Tubes in the High-Temperature Gas-Cooled Reactor (HTGR)

Mingzhe Wei, Yiyang Zhang, Zhu Fang, Xinxin Wu, Libin Sun

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A024, July 22–26, 2018

Paper No: ICONE26-82043

DOI: https://doi.org/10.1115/ICONE26-82043

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Topics: Boilers, Dust, Graphite, Very high temperature reactors, Particulate matter, Adhesion, Finite element methods, Simulation, Accidents, Collisions (Physics)

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

DOI: https://doi.org/10.1115/ICONE26-81938

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Topics: Noise (Sound), Pipes, Steam, Transients (Dynamics), Valves, Flow (Dynamics), Collapse, Energy dissipation, Friction, High pressure (Physics)

Proceedings Papers

Research on Cooling Methods of Voice Coil Motor

Pu Zhou, Yue Zhang, Xuechang Dai, Qiang Wang, Weiliang Wu

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, V001T04A012, July 2–6, 2017

Paper No: ICONE25-66475

DOI: https://doi.org/10.1115/ICONE25-66475

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Topics: Cooling, Engines, Motors, Temperature, Energy dissipation, Flow (Dynamics), Heat, Mechanical properties, Servomechanisms, Weight (Mass)

Proceedings Papers

A Heat Dissipation Simulation Study in a CFD Way on Spent Nuclear Fuel Dry Stored in Underground Vertical Shaft

Zhang Hong-jian, Yu Ren, Liu Xiao-fan

Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A045, July 2–6, 2017

Paper No: ICONE25-67926

DOI: https://doi.org/10.1115/ICONE25-67926

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Topics: Computational fluid dynamics, Energy dissipation, Heat, Simulation, Spent nuclear fuels, Storage, Forced convection, Reliability, Safety, Security

Proceedings Papers

Research on Approval of Domestic and International Transport Container Application of Radioactive Material

Wang Yue, Zhan Lechang, Ma Wenjuan, Zhang Yongxin, Ma Li

Paper No: ICONE25-66279

DOI: https://doi.org/10.1115/ICONE25-66279

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Topics: Containers, Radioactive substances, Safety, Licensing, China, Radiation (Physics), Regulations, Commercial air transport, Design, Manufacturing

Proceedings Papers

Methodology for Assessing Shock Effect due to Aircraft Impact Considering the Nonlinear of Impact Zone and Soil-Structure Interaction

Yugang Sun, Shujian Cheng, Honghui Ge, Xiaowen Wang, Fang Yuan, Shuaixi Li

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A068, July 2–6, 2017

Paper No: ICONE25-66874

DOI: https://doi.org/10.1115/ICONE25-66874

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Topics: Aircraft, Shock (Mechanics), Soil, Spectra (Spectroscopy), Damage, Cooling, Damage assessment, Design, Dynamic analysis, Earthquakes

Proceedings Papers

Technology of Protection Against the Dynamic Effect of Nuclear Pipe Rupture

Feng He, Feng Yuan, Honglei Ai, Xinjun Wang, Xifeng Lu, Yongbo Lv

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A042, July 2–6, 2017

Paper No: ICONE25-66381

DOI: https://doi.org/10.1115/ICONE25-66381

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Topics: Pipes, Rupture, Energy budget (Physics), Finite element analysis, Deformation, Thrust, Damage, Energy dissipation, Finite element model, Hinges

Proceedings Papers

Thermodynamic Performance of 5MW Space Nuclear Power System Based on Liquid Metal Rankine Cycle

Xian-Wei Cheng, Hao-Chun Zhang, Xiao-Qi Li, Chen-Xu Zhang, Guang-Bo Zhao

Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A034, July 2–6, 2017

Paper No: ICONE25-67265

DOI: https://doi.org/10.1115/ICONE25-67265

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Topics: Liquid metals, Nuclear power, Rankine cycle, Exergy, Energy dissipation, Fast neutron reactors, Lithium, Power conversion systems, Power systems (Machinery), Temperature

Proceedings Papers

Performance Test and Simulation Study on the Air Path of CAP1400 Passive Containment Cooling System

Pan Xinxin, Huang Jingyu, Song Chunjing

Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A011, July 2–6, 2017

Paper No: ICONE25-66321

DOI: https://doi.org/10.1115/ICONE25-66321

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Topics: Containment, Cooling systems, Simulation, Testing performance, Air flow, Wind, Computational fluid dynamics, Wind tunnels, Annulus, Wind velocity

Proceedings Papers

Experimental Study of Performance of Cold Crucible Induction Melter in Melting Corium Simulant

Caixin Sun, Ying Chen, Lian Chen, Huajian Chang, Jie Pei, Fang Tian, Xinchen Xu

Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A030, July 2–6, 2017

Paper No: ICONE25-67527

DOI: https://doi.org/10.1115/ICONE25-67527

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Topics: Electromagnetic induction, Melting, Heating, Zirconium, Cooling, Temperature, Water, Circuits, Copper, Design

Proceedings Papers

Assessment of the Turbulent Prandtl Number Effect on Simulating Heat Transfer Characteristics of Supercritical Water Flow in Bare Tubes

Amjad Farah, Glenn Harvel, Igor Pioro

Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A101, July 2–6, 2017

Paper No: ICONE25-67601

DOI: https://doi.org/10.1115/ICONE25-67601

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Topics: Flow (Dynamics), Heat transfer, Prandtl number, Turbulence, Water, Computational fluid dynamics, Kinetic energy, Buoyancy, Energy dissipation, Fluids

Proceedings Papers

Water Level Control for Steam Generator in Nuclear Power Based on Port-Controlled Hamiltonian Method

Mo Tao, Rui Yu, Xianling Li, Zhiwu Ke, Zhenxing Zhao, Qi Xiao

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, V001T04A007, June 26–30, 2016

Paper No: ICONE24-60274

DOI: https://doi.org/10.1115/ICONE24-60274

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Topics: Boilers, Nuclear power, Water, Control modeling, Control equipment, Control systems, Energy dissipation, Equilibrium (Physics), Modeling, Process control

Proceedings Papers

Modifications of Generic Pressurized-Water Reactor Units to Increase Cycle Efficiency

Paul Ponomaryov, Yifeng Zhou, Cristina-Maria Mazza, Igor Pioro

Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A021, June 26–30, 2016

Paper No: ICONE24-60353

DOI: https://doi.org/10.1115/ICONE24-60353

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Topics: Cycles, Water, Turbines, Heavy water reactors, Thermal efficiency, Pressurized water reactors, Boiling water reactors, Molten salt reactors, Nuclear power stations, Steam

Proceedings Papers

Experimental Study of Helix-Finned Surface for Nucleate Pool Boiling

Kailun Chen, Changqi Yan, Cable Kurwitz, Kun Cheng, Haozhi Bian

Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A003, June 26–30, 2016

Paper No: ICONE24-60106

DOI: https://doi.org/10.1115/ICONE24-60106

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Topics: Additive manufacturing, Atmospheric pressure, Boiling, Bubbles, Cavities, Dimensions, Energy dissipation, Fins, Heat, Heat flux

NARROW

Development and Verification of Heat Pipe and Fin Radiation Heat Dissipation Program Based on MOOSE Platform

Analysis of Energy Dissipation Effects of Resistance Components in the Water Hammer Process

Numerical Simulation Analysis of the Air Temperature Measurement Scheme for Big Space in Containment

Natural-Convective Transport Model of Radon From Building From Building Materials Into Indoor Atmosphere

Research on Hydraulic Model Test of Pumping Station Forebay

Development of Evaluation Method for Thermal Stratification by Cavity Flow in a Vertical Branch Pipe With Elbow and Horizontal Section: Experimental Results

A Numerical Study on Graphite Dust Deposition on Steam Generator Tubes in the High-Temperature Gas-Cooled Reactor (HTGR)

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

Research on Cooling Methods of Voice Coil Motor

A Heat Dissipation Simulation Study in a CFD Way on Spent Nuclear Fuel Dry Stored in Underground Vertical Shaft

Research on Approval of Domestic and International Transport Container Application of Radioactive Material

Methodology for Assessing Shock Effect due to Aircraft Impact Considering the Nonlinear of Impact Zone and Soil-Structure Interaction

Technology of Protection Against the Dynamic Effect of Nuclear Pipe Rupture

Thermodynamic Performance of 5MW Space Nuclear Power System Based on Liquid Metal Rankine Cycle

Performance Test and Simulation Study on the Air Path of CAP1400 Passive Containment Cooling System

Experimental Study of Performance of Cold Crucible Induction Melter in Melting Corium Simulant

Assessment of the Turbulent Prandtl Number Effect on Simulating Heat Transfer Characteristics of Supercritical Water Flow in Bare Tubes

Water Level Control for Steam Generator in Nuclear Power Based on Port-Controlled Hamiltonian Method

Modifications of Generic Pressurized-Water Reactor Units to Increase Cycle Efficiency

Experimental Study of Helix-Finned Surface for Nucleate Pool Boiling

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