Search Results | ICONE | ASME Digital Collection

1-20 of 1592

Sort by

Sort Order Select

Proceedings Papers

A Comparative Approach of a Seismic Response Analysis Based on Housner Model and Added Mass Model for a Nuclear Water Storage Tank

Chengzhuo Yang, Thomas Metais, Zihao Zheng, Yang Dai, Jiesheng Min

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A070, August 8–12, 2022

Paper No: ICONE29-93230

DOI: https://doi.org/10.1115/ICONE29-93230

View Paper

Topics: Water, Water storage, Sloshing, Fluid structure interaction, Center of mass, Convection, Displacement, Dynamic response, Finite element analysis, Finite element model

Proceedings Papers

The Research on the Interception Engineering Layout of Active Intercepting and Guiding in Water Intake Open Channel of Nuclear Power Plant

Jia Yang, Ranran Cao, Wei Bai

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A053, August 8–12, 2022

Paper No: ICONE29-92760

DOI: https://doi.org/10.1115/ICONE29-92760

View Paper

Topics: Flow (Dynamics), Nuclear power stations, Open channels (Hydraulics), Water

Proceedings Papers

Study on the Applicability of Flat Ceramic Membrane in Simulated Primary Coolant Water Environment of PWR Nuclear Power Plant

Yuxin Guan, Jiguo Chen, Guodong Zhang, Xuqiu Ren

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A033, August 8–12, 2022

Paper No: ICONE29-92184

DOI: https://doi.org/10.1115/ICONE29-92184

View Paper

Topics: Ceramics, Coolants, Membranes, Nuclear power stations, Pressurized water reactors, Water

Proceedings Papers

Design of Combined Water System of Demineralized Water and Boiler Make-Up Water in Nuclear Engineering

Kechen Xu, Rui Wang, Hongmei Yan, Wei Bai

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A032, August 8–12, 2022

Paper No: ICONE29-92140

DOI: https://doi.org/10.1115/ICONE29-92140

View Paper

Topics: Boilers, Design, Nuclear engineering, Water, Nuclear power, Manufacturing, Combined heat and power, Heating boilers, Water pollution, Water supply

Proceedings Papers

Design Overview for Process System of Large-Scale Seawater Desalination and Demineralized Water Production in the Nuclear Heating Plant

Rui Wang, Kechen Xu, Kehao Zeng, Hongmei Yan, Wei Bai, Jing Li

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A039, August 8–12, 2022

Paper No: ICONE29-92381

DOI: https://doi.org/10.1115/ICONE29-92381

View Paper

Topics: Design, Heating, Water, Water desalination

Proceedings Papers

Research on Precision Water Reactor Fuel Servo Operation System

Li Ping, Peiqiang Deng, Wei Qian, Kaiyu Yang, Jiansong Zhai, Shuiyang Huang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A041, August 8–12, 2022

Paper No: ICONE29-92493

DOI: https://doi.org/10.1115/ICONE29-92493

View Paper

Topics: Nuclear fuels, Nuclear power stations, Servomechanisms, Water, Engines, Motors, Permanent magnets, Algorithms, Control algorithms, Control theory

Proceedings Papers

Study on the Water Intake of Heat Trap Blocked by Marine Life in Nuclear Power Plant

Zhenhua Zhang, Bo Zhang, Chaoying Zheng

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A015, August 8–12, 2022

Paper No: ICONE29-90544

DOI: https://doi.org/10.1115/ICONE29-90544

View Paper

Topics: Design, Heat, Nuclear power stations, Water

Proceedings Papers

Effect of Contact Stress on Fretting Corrosion Behavior of Alloy 690 Tube Exposed to Simulated Secondary Water

Wenhua Zhuang, Zhongli Han, Xianglong Guo, Lefu Zhang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A054, August 8–12, 2022

Paper No: ICONE29-92395

DOI: https://doi.org/10.1115/ICONE29-92395

View Paper

Topics: Alloys, Corrosion, Stress, Water, Wear

Proceedings Papers

Development and Application of a Support Device for Checking Leakage of Heat Exchange Tubes of Spring Base Supporting Condenser in the Form of Filling Water

Jianning Xie

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A062, August 8–12, 2022

Paper No: ICONE29-93036

DOI: https://doi.org/10.1115/ICONE29-93036

View Paper

Topics: Condensers (steam plant), Heat, Leakage, Springs, Water

Proceedings Papers

Research on the Prevention and Control System of Jellyfish in Nuclear Power Plants Cooling Water System

Xiaolin Liu, Wei Meng, Li Lu, Jianwen Li

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A043, August 8–12, 2022

Paper No: ICONE29-92507

DOI: https://doi.org/10.1115/ICONE29-92507

View Paper

Topics: Control systems, Cooling, Nuclear power stations, Water

Proceedings Papers

Corrosion Behavior of a Novel Alumina Forming Austenitic Steel Exposed to Supercritical Water

Dayun Sun, Yang Gao, Shuo Cong, Xianglong Guo

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A057, August 8–12, 2022

Paper No: ICONE29-92471

DOI: https://doi.org/10.1115/ICONE29-92471

View Paper

Topics: Corrosion, Steel, Water

Proceedings Papers

A Systematic Research on Prevention and Control Measures to Blockages of Cooling Water Intake System in Coastal Nuclear Power Plant

Ranran Cao, Jia Yang, Wei Bai

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A036, August 8–12, 2022

Paper No: ICONE29-92209

DOI: https://doi.org/10.1115/ICONE29-92209

View Paper

Topics: Cooling, Nuclear power stations, Safety, Shorelines, Water

Proceedings Papers

Study on Out-Pile Performance of CZ Zirconium Alloy Guide Tube

Changyuan Gao, Lin Shi, Guoliang Zhang, Yang Xu, Minli Chen, Liutao Chen, Jun Tan

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A089, August 8–12, 2022

Paper No: ICONE29-93816

DOI: https://doi.org/10.1115/ICONE29-93816

View Paper

Topics: Corrosion, Creep, Zirconium alloys, Alloys, Zirconium, Corrosion resistance, Stress, Temperature, Mechanical testing, Particulate matter

Proceedings Papers

Numerical Study of the Effect of δ-Ferrite on Crack-Tip Mechanical Field

Yule Wu, Lefu Zhang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A060, August 8–12, 2022

Paper No: ICONE29-92656

DOI: https://doi.org/10.1115/ICONE29-92656

View Paper

Topics: Ferrites (Magnetic materials), Fracture (Materials), Stress, Cracking (Materials), Fracture (Process), Embrittlement, Finite element analysis, Finite element methods, Finite element model, High temperature

Proceedings Papers

Study on Synthesis of the Organophosphorus Functionalized MCM-41 And its Adsorption Property for Dy(III)

Cong Mao, Hongji Sang, Jiawei Zheng, Yan Wu

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A077, August 8–12, 2022

Paper No: ICONE29-93196

DOI: https://doi.org/10.1115/ICONE29-93196

View Paper

Topics: Composite materials, Fittings, Metals, Sewage, Temperature, Water, Zirconium

Proceedings Papers

Study on Properties of Aging and Immersion in Boric Acid Water of PEEK Insulation Material

Jing An, Shan Jin, Li-Qin Zhang, Hao Wu

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A093, August 8–12, 2022

Paper No: ICONE29-93867

DOI: https://doi.org/10.1115/ICONE29-93867

View Paper

Topics: Insulation, Mechanical properties, Water

Proceedings Papers

UTSG Water Level Prediction Model Based on LSTM and GRU Algorithms

Qingyun He, Bin Li, Sitao Peng

Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A015, August 8–12, 2022

Paper No: ICONE29-91798

DOI: https://doi.org/10.1115/ICONE29-91798

View Paper

Topics: Algorithms, Boilers, Water

Proceedings Papers

Research on the PID Parameter Self-Tuning of the Pressurizer Control System of Nuclear Power Plant

Kunpeng Xing, Hongrui Wang, Tao Zou, Zhijia Yang, Jingyang Wang, Pengbin Zhang

Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A027, August 8–12, 2022

Paper No: ICONE29-92849

DOI: https://doi.org/10.1115/ICONE29-92849

View Paper

Topics: Control systems, Nuclear power stations, Control equipment, Particle swarm optimization, Algorithms, Errors, Nuclear power, Pressure, Steam, Water

Proceedings Papers

Thermal-Hydraulic Analysis of HL-2M Cooling Water System for Toroidal Field Coils

Jiaqi Wang, Yanfeng Xie, Xiaolong Liu, Jianpeng Meng, Ruibao Jia, Qiang Li, Xin Chen

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A032, August 8–12, 2022

Paper No: ICONE29-92917

DOI: https://doi.org/10.1115/ICONE29-92917

View Paper

Topics: Cooling, Water

Proceedings Papers

Assessment of Passive Cooling Capability of the Westinghouse Lead Fast Reactor Under Station Blackout Conditions

Emre Tatli, Sung Jin Lee, Jun Liao, Paolo Ferroni

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A020, August 8–12, 2022

Paper No: ICONE29-91821

DOI: https://doi.org/10.1115/ICONE29-91821

View Paper

Topics: Cooling, Fast neutron reactors, Computational fluid dynamics, Design, Heat, Reactor vessels, Vessels, Water, Accidents, Accounting

NARROW

A Comparative Approach of a Seismic Response Analysis Based on Housner Model and Added Mass Model for a Nuclear Water Storage Tank

The Research on the Interception Engineering Layout of Active Intercepting and Guiding in Water Intake Open Channel of Nuclear Power Plant

Study on the Applicability of Flat Ceramic Membrane in Simulated Primary Coolant Water Environment of PWR Nuclear Power Plant

Design of Combined Water System of Demineralized Water and Boiler Make-Up Water in Nuclear Engineering

Design Overview for Process System of Large-Scale Seawater Desalination and Demineralized Water Production in the Nuclear Heating Plant

Research on Precision Water Reactor Fuel Servo Operation System

Study on the Water Intake of Heat Trap Blocked by Marine Life in Nuclear Power Plant

Effect of Contact Stress on Fretting Corrosion Behavior of Alloy 690 Tube Exposed to Simulated Secondary Water

Development and Application of a Support Device for Checking Leakage of Heat Exchange Tubes of Spring Base Supporting Condenser in the Form of Filling Water

Research on the Prevention and Control System of Jellyfish in Nuclear Power Plants Cooling Water System

Corrosion Behavior of a Novel Alumina Forming Austenitic Steel Exposed to Supercritical Water

A Systematic Research on Prevention and Control Measures to Blockages of Cooling Water Intake System in Coastal Nuclear Power Plant

Study on Out-Pile Performance of CZ Zirconium Alloy Guide Tube

Numerical Study of the Effect of δ-Ferrite on Crack-Tip Mechanical Field

Study on Synthesis of the Organophosphorus Functionalized MCM-41 And its Adsorption Property for Dy(III)

Study on Properties of Aging and Immersion in Boric Acid Water of PEEK Insulation Material

UTSG Water Level Prediction Model Based on LSTM and GRU Algorithms

Research on the PID Parameter Self-Tuning of the Pressurizer Control System of Nuclear Power Plant

Thermal-Hydraulic Analysis of HL-2M Cooling Water System for Toroidal Field Coils

Assessment of Passive Cooling Capability of the Westinghouse Lead Fast Reactor Under Station Blackout Conditions

Journals

Conference Proceedings

eBooks

Resources

Opportunities

Journals

Conference Proceedings

eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only