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Proceedings Papers

Retracted: “Power Control System Design for Heat Pipe Cooled Reactor Based on Model Predictive Control” [2022 29th International Conference on Nuclear Engineering, Volume 15] Shenzhen, China and Virtual, Online, August 8–12, 2022, Conference Sponsors: Pressure Vessels and Piping Division, ISBN: 978-0-7918-8650-2, Copyright © 2022 by ASME. Paper No. ICONE29-89495, V015T16A014; 8 pages; doi: https://doi.org/10.1115/ICONE29-89495

ASME

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A014, August 8–12, 2022

Paper No: ICONE29-89495

DOI: https://doi.org/10.1115/ICONE29-89495

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Topics: China, Control systems, Design, Heat pipes, Nuclear engineering, Pipes, Predictive control, Pressure vessels

Proceedings Papers

Study on the Added Mass of the Double-Fixed Constrained Flexible Coaxial Cylindrical Shells With Liquid in the Narrow Gap

Donghao Li, Daogang Lu, Yuxuan Zhu, Yu Liu

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A032, August 8–12, 2022

Paper No: ICONE29-92137

DOI: https://doi.org/10.1115/ICONE29-92137

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Topics: Fluid structure interaction, Pipes, Shells, Vibration, Finite element model, Fluids, Water, Computer software, Fast neutron reactors, Heat shielding

Proceedings Papers

High-Precision Subchannel Model for Single and Two Phase Flow in PWR Rod Bundles With Mixing Grids

Li Jiang, Jianqiang Shan

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A038, August 8–12, 2022

Paper No: ICONE29-93217

DOI: https://doi.org/10.1115/ICONE29-93217

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Topics: Fuel rods, Pressurized water reactors, Turbulence, Two-phase flow, Critical heat flux, Axial flow, Convection, Fluids, Pipes, Temperature

Proceedings Papers

The Influence of Impurity Water for CHF on the Downward Facing Boiling Surface

Bo Lin, Xiangyu Yun, Junying Xu, Dongshan Wei, Huiyong Zhang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A055, August 8–12, 2022

Paper No: ICONE29-93157

DOI: https://doi.org/10.1115/ICONE29-93157

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Topics: Boiling, Coating processes, Coatings, Concretes, Critical heat flux, Glass reinforced plastics, Water, Coolants, Accidents, Construction

Proceedings Papers

On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads

Masaki Morishita, Akihito Otani

Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A002, August 8–12, 2022

Paper No: ICONE29-90172

DOI: https://doi.org/10.1115/ICONE29-90172

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Topics: Cycles, Earthquake resistant design, Earthquakes, Fatigue, Pipes, Piping systems, Stress, Excitation, ASME Boiler and Pressure Vessel Code, Deformation

Proceedings Papers

Effect of the Plasticity of Piping and Support Structures on the Seismic Response of Piping Systems

Takahiro Okuda, Hideki Takahashi, Tomoyoshi Watakabe, Masaki Morishita

Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A001, August 8–12, 2022

Paper No: ICONE29-89097

DOI: https://doi.org/10.1115/ICONE29-89097

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Topics: Earthquake resistant design, Pipes, Piping systems, Plasticity

Proceedings Papers

Research on Heat Transfer Performance of Heat Pipe in Mobile Small Reactor

Huaichang Lu, Tao Zhou, Wenbin Liu, Jianyu Tang, Tianyu Gao

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A024, August 8–12, 2022

Paper No: ICONE29-91655

DOI: https://doi.org/10.1115/ICONE29-91655

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Topics: Heat pipes, Heat transfer, Temperature, Thermal resistance, Computer simulation, Computer software, Heat, Heat transfer coefficients, High temperature, Mechanical admittance

Proceedings Papers

Numerical Simulation Study of Steam Condensation in Vertical Tube

Gao Chenyang, Xue Ruojun, Qi Yiqi, Jing Furu

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A023, August 8–12, 2022

Paper No: ICONE29-92772

DOI: https://doi.org/10.1115/ICONE29-92772

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Topics: Computer simulation, Condensation, Pipes, Steam

Proceedings Papers

Research of Probabilistic Safety Assessment of CPR1000 Considering Aging Effects

Xiaoming Zhang, Lijuan Wang

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A037, August 8–12, 2022

Paper No: ICONE29-92459

DOI: https://doi.org/10.1115/ICONE29-92459

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Topics: Failure, Probabilistic safety assessment, Risk, Accidents, Damage, Cables, China, Coolants, Nuclear power, Pipes

Proceedings Papers

Numerical investigation of particle erosion characteristics in supercritical carbon dioxide in elbow pipe channels

Peng Xu, Tao Zhou, Zhongguang Fu, Juan Chen

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A003, August 8–12, 2022

Paper No: ICONE29-88843

DOI: https://doi.org/10.1115/ICONE29-88843

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Topics: Erosion, Particulate matter, Pipes, Supercritical carbon dioxide

Proceedings Papers

Review of Flow Characteristics in Narrow Rectangular Channels Under Marine Conditions

Enpei Wang, Lei Li, Mingjun Wei, Yongsheng Wen, Bowen Zhou

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A116, August 8–12, 2022

Paper No: ICONE29-93743

DOI: https://doi.org/10.1115/ICONE29-93743

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Topics: Flow (Dynamics), Heat transfer, Pressure drop, Heat exchangers, Heat, Nuclear power stations, Nuclear reactors, Ocean engineering, Pipes, Power stations

Proceedings Papers

Bubble Behaviors in Saturated Flow Boiling Based on the VOF Model

Deyang Gao, Wen He, Hanliang Bo

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A095, August 8–12, 2022

Paper No: ICONE29-92489

DOI: https://doi.org/10.1115/ICONE29-92489

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Topics: Boiling, Bubbles, Flow (Dynamics), Pipes

Proceedings Papers

Phase Distribution Characteristics of Bubbly to Slug Flow Transition Region in a 10mm ID Vertical Round Pipe

Wangtao Xu, Qingche He, Tao Huang, Shuhua Ding, Meiyue Yan, Luteng Zhang, Liangming Pan

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A111, August 8–12, 2022

Paper No: ICONE29-93313

DOI: https://doi.org/10.1115/ICONE29-93313

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Topics: Pipes, Porosity, Slug flows, Two-phase flow

Proceedings Papers

Anomalies Detection in Structures, System and Components for Supporting Nuclear Long Term Operation Program

Salvatore Angelo Cancemi, Rosa Lo Frano

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A110, August 8–12, 2022

Paper No: ICONE29-93193

DOI: https://doi.org/10.1115/ICONE29-93193

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Topics: Algorithms, Digital twin, Failure, Finite element analysis, Machine learning, Maintenance, Nuclear power stations, Nuclear reactors, Pipes, Pressure

Proceedings Papers

Cause Analysis and Treatment Measures for Corrosion of Warm-Up Pipe of Hualong no.1 Main Feed Water Pump System

Zhiming Wu, Yixin Ling, Xing Liu, Dongdong Fei, Xiaoyu Hou, Xue Wen

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A078, August 8–12, 2022

Paper No: ICONE29-93343

DOI: https://doi.org/10.1115/ICONE29-93343

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Topics: Corrosion, Feedwater, Pipes, Pumps

Proceedings Papers

Research on Spacing Design Method of Condenser Half-Side Operation in Pressurized Water Reactor Nuclear Power Plant

Zhao Qingsen, Liang Junqin, Zhou Shuai, Chen Jie, Zeng Weipeng, Zhang Qiang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A071, August 8–12, 2022

Paper No: ICONE29-93265

DOI: https://doi.org/10.1115/ICONE29-93265

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Topics: Condensers (steam plant), Cooling, Design methodology, Nuclear power stations, Pipes, Pressurized water reactors

Proceedings Papers

Sensitivity Calculation of Lower Shell Pressure Parameters in Advanced Nuclear Power Plant Accidents

Zhou Lanyu, Sun Yanyu, Zheng Yuntao, Yang Changjiang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A004, August 8–12, 2022

Paper No: ICONE29-89165

DOI: https://doi.org/10.1115/ICONE29-89165

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Topics: Containment, Nuclear reactor accidents, Pressure, Shells, Temperature, Accidents, Boilers, Circuits, Coolants, Design

Proceedings Papers

A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant

Zihao Zheng, Wenxin Qiu, Yang Dai, Jiesheng Min

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A064, August 8–12, 2022

Paper No: ICONE29-93082

DOI: https://doi.org/10.1115/ICONE29-93082

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Topics: Brittle fracture, Finite element methods, Fracture (Materials), Fracture (Process), Nuclear power stations, Pipes, Radiation (Physics), Computer software, Engineering standards, Engineers

Proceedings Papers

Research on the Technology Accuracy of the On-Line Fracture Assessment of Cracked Pipe in NPPs

Mingya Chen, Min Yu, Hongbo Gao, Shuang Qi, Lei Lin, Decheng Xu, Weiqiang Wang, Jinhua Shi, Qunjia Peng, Guodong Zhang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A003, August 8–12, 2022

Paper No: ICONE29-89057

DOI: https://doi.org/10.1115/ICONE29-89057

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Topics: Computer software, Fracture (Materials), Fracture (Process), Nuclear power stations, Pipes

Proceedings Papers

Rapid Assessment Method for Corrosion Flaws of Seawater Cooling Pipes in Nuclear Power Plants

Zhichao Han, Haijun Chang, Mengling Shen, Zhishen Rong, Zhengpeng Li

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A057, August 8–12, 2022

Paper No: ICONE29-92871

DOI: https://doi.org/10.1115/ICONE29-92871

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Topics: Cooling, Corrosion, Finite element methods, Nuclear power stations, Pipes, Seawater

2 3 4 5

NARROW

Study on the Added Mass of the Double-Fixed Constrained Flexible Coaxial Cylindrical Shells With Liquid in the Narrow Gap

High-Precision Subchannel Model for Single and Two Phase Flow in PWR Rod Bundles With Mixing Grids

The Influence of Impurity Water for CHF on the Downward Facing Boiling Surface

On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads

Effect of the Plasticity of Piping and Support Structures on the Seismic Response of Piping Systems

Research on Heat Transfer Performance of Heat Pipe in Mobile Small Reactor

Numerical Simulation Study of Steam Condensation in Vertical Tube

Research of Probabilistic Safety Assessment of CPR1000 Considering Aging Effects

Numerical investigation of particle erosion characteristics in supercritical carbon dioxide in elbow pipe channels

Review of Flow Characteristics in Narrow Rectangular Channels Under Marine Conditions

Bubble Behaviors in Saturated Flow Boiling Based on the VOF Model

Phase Distribution Characteristics of Bubbly to Slug Flow Transition Region in a 10mm ID Vertical Round Pipe

Anomalies Detection in Structures, System and Components for Supporting Nuclear Long Term Operation Program

Cause Analysis and Treatment Measures for Corrosion of Warm-Up Pipe of Hualong no.1 Main Feed Water Pump System

Research on Spacing Design Method of Condenser Half-Side Operation in Pressurized Water Reactor Nuclear Power Plant

Sensitivity Calculation of Lower Shell Pressure Parameters in Advanced Nuclear Power Plant Accidents

A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant

Research on the Technology Accuracy of the On-Line Fracture Assessment of Cracked Pipe in NPPs

Rapid Assessment Method for Corrosion Flaws of Seawater Cooling Pipes in Nuclear Power Plants

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