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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

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

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

Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature

Xiangyu Wei, Wenhua Zhang, Yingchun Zhao

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A079, August 8–12, 2022

Paper No: ICONE29-93417

DOI: https://doi.org/10.1115/ICONE29-93417

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Topics: Atmospheric pressure, Fuels, Ropes, Temperature, Cladding systems (Building), Stress, Fuel rods, Irradiation (Radiation exposure), Pressure, Sensitivity analysis

Proceedings Papers

Research on the Influence of Degassing on the Release of Fission Gases in PWRs

Yaoxin Ye, Pengtao Fu, Zhijun Li

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A008, August 8–12, 2022

Paper No: ICONE29-89461

DOI: https://doi.org/10.1115/ICONE29-89461

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Topics: Failure, Fuels, Gases, Nuclear fission, Pressurized water reactors, Coolants, Nuclear power stations, Cladding systems (Building), Nuclear fuel cycle, Rods

Proceedings Papers

Numerical Simulation of Fuel Relocation at High Burnup With Discrete Element Method

Zehua Ma, Ren Liang, Zhikang Lin, Yong Ouyang, Xianghui Lu, Guanghui Su

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A029, August 8–12, 2022

Paper No: ICONE29-91377

DOI: https://doi.org/10.1115/ICONE29-91377

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Topics: Accidents, Computer simulation, Coolants, Discrete element methods, Fuels

Proceedings Papers

A Digital Proof of Concept (POC) for Simulating the Coupled Phenomena Between Neutronics, Structural and Fluid Dynamics in a Reactor Core

Jie Liu, Chunyu Zhang, Zhihao Zheng, Jiesheng Min

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A073, August 8–12, 2022

Paper No: ICONE29-93008

DOI: https://doi.org/10.1115/ICONE29-93008

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Topics: Fluid dynamics, Physics, Simulation, Computational fluid dynamics, Structural analysis, American Petroleum Institute, Computation, Computer simulation, Computer software, Computer-aided engineering

Proceedings Papers

Hydrogenation of Zircaloy-4 in a Defective Fuel Pellet for Pressurized Water Reactors

Doctor Enivweru, Qingyu Wang, Abiodun Ayodeji, John Njoroge

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A021, August 8–12, 2022

Paper No: ICONE29-90736

DOI: https://doi.org/10.1115/ICONE29-90736

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Topics: Corrosion, Fuels, Hydrogen embrittlement, Pressurized water reactors, Cladding systems (Building), Hydrogen, Temperature, Accidents, Boundary-value problems, Coolants

Proceedings Papers

Investigation of Model-Based Anomaly Detection Method for the Full-Power Natural Circulation Small Modular Reactor NHR200-II

Canxing Huang, Huasheng Xiong, Junting Feng

Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A014, August 8–12, 2022

Paper No: ICONE29-91509

DOI: https://doi.org/10.1115/ICONE29-91509

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Topics: Accidents, Boilers, Control systems, Coolants, Heating, Nuclear power, Pressurized water reactors, Pumps, Radioactivity, Safety

Proceedings Papers

Applying Machine Learning to Improve BOA Analysis of CIPS/CILC

Jun Liao, Alexander Mace, Guoqiang Wang, Jesse S. Fisher

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A095, August 8–12, 2022

Paper No: ICONE29-94480

DOI: https://doi.org/10.1115/ICONE29-94480

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Topics: Machine learning, Boron, Corrosion, Fuels, Nuclear power stations, Algorithms, Calibration, Chemistry, Cladding systems (Building), Computers

Proceedings Papers

Event Tree Analysis for Material Relocation on Core Catcher in a Sodium-Cooled Fast Reactor

Hidemasa Yamano, Shigenobu Kubo, Taro Kan, Akihiro Shibata, Edouard Hourcade, Jean François Dirat

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A011, August 8–12, 2022

Paper No: ICONE29-91505

DOI: https://doi.org/10.1115/ICONE29-91505

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Topics: Accidents, Sodium fast reactors, Design, Coolants, Fuels, Probability, Sodium, Vessels

Proceedings Papers

Performance Experimental Study on Siphon Breaker of CFR600

Ping Zhou, Zhenxin Ding, Xiaoguang Qi, Xuefeng Zhang, Song Yu, Xiaoyao Ma

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A027, August 8–12, 2022

Paper No: ICONE29-92812

DOI: https://doi.org/10.1115/ICONE29-92812

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Topics: Circuits, Containers, Coolants, Data acquisition, Design, Flow (Dynamics), Leakage, Pipes, Risk, Safety

Proceedings Papers

Data Driven Methods for Break Size and Location Estimation in LOCA Based on Deep Learning

Peng Yuan, Jian Deng, Zhifang Qiu, Qinglan Xu, Dahuan Zhu, Tao Huang, Zhongchun Li, Peng Du

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A006, August 8–12, 2022

Paper No: ICONE29-92380

DOI: https://doi.org/10.1115/ICONE29-92380

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Topics: Accidents, Algorithms, Artificial neural networks, China, Coolants, Design, Flow (Dynamics), Machine learning, Nuclear power stations, Nuclear reactors

Proceedings Papers

Study on Time-Dependent Co-58 and Co-60 Activities in the Primary Coolant of CPR1000 PWRs

Xiaoqian Zhang, Pengtao Fu

Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A034, August 8–12, 2022

Paper No: ICONE29-92822

DOI: https://doi.org/10.1115/ICONE29-92822

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Topics: Boiling, Coolants, Corrosion, Pressurized water reactors, Radioisotopes, Cycles, Circuits, Maintenance, Shapes, Cobalt

Proceedings Papers

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

Tiexin Fan, Xianbin Zeng, Qi Niu, Bin Tu, Dongshan Huang, Zhengjie Liu

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A065, August 8–12, 2022

Paper No: ICONE29-93513

DOI: https://doi.org/10.1115/ICONE29-93513

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Topics: Computational fluid dynamics, Computer simulation, Containment, Design, Temperature measurement, Temperature, Computer software, Computer-aided design, Nuclear power stations, Accidents

Proceedings Papers

Optimization of the Tritium Production and Discharge in HPR1000

Pengtao Fu, Mingliang Dai

Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A033, August 8–12, 2022

Paper No: ICONE29-92816

DOI: https://doi.org/10.1115/ICONE29-92816

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Topics: Boron, Conformity assessment, Coolants, Cycles, Design, Neutron sources, Optimization, Pressurized water reactors, Radioactivity, Radioisotopes

Proceedings Papers

Optimizing Material/Component Fabrication Processing for Improving Service Performance in Nuclear Power Plant Coolants

Zhanpeng Lu

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A030, August 8–12, 2022

Paper No: ICONE29-92321

DOI: https://doi.org/10.1115/ICONE29-92321

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Topics: Coolants, Cracking (Materials), Fracture (Process), Manufacturing, Nuclear power stations, Pressurized water reactors, Stress corrosion cracking

Proceedings Papers

Preliminary Study on the Migration of Polonium-210 in Lead-Based Fast Reactor

Yali Qiu, Qin Zeng, Hongli Chen

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A031, August 8–12, 2022

Paper No: ICONE29-92104

DOI: https://doi.org/10.1115/ICONE29-92104

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Topics: Fast neutron reactors, Radioisotopes, Coolants, Volatility, Accidents, Circuits, Computational fluid dynamics, Containment, Hazards, Irradiation (Radiation exposure)

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

Comparison of Numerical Analysis Methods of Coolant Environmental Fatigue Based on Strain Rate Control

Xuejiao Shao, Hai Xie, Yixiong Zhang, Furui Xiong, Xinjun Wang, Kaikai Shi, Mingda Yu, Xuan Huang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A064, August 8–12, 2022

Paper No: ICONE29-93631

DOI: https://doi.org/10.1115/ICONE29-93631

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Topics: Coolants, Fatigue, Numerical analysis, Stainless steel

Proceedings Papers

Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients

Qingwen Xiong, Gongle Song, Peng Du, Tao Huang, Jian Deng

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A006, August 8–12, 2022

Paper No: ICONE29-89017

DOI: https://doi.org/10.1115/ICONE29-89017

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Topics: Accidents, Coolants, Nuclear reactors, Sensitivity analysis, Transients (Dynamics), Cladding systems (Building), Nuclear reactor accidents, Temperature, B-splines, Regression analysis

2 3 4 5

NARROW

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

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

Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature

Research on the Influence of Degassing on the Release of Fission Gases in PWRs

Numerical Simulation of Fuel Relocation at High Burnup With Discrete Element Method

A Digital Proof of Concept (POC) for Simulating the Coupled Phenomena Between Neutronics, Structural and Fluid Dynamics in a Reactor Core

Hydrogenation of Zircaloy-4 in a Defective Fuel Pellet for Pressurized Water Reactors

Investigation of Model-Based Anomaly Detection Method for the Full-Power Natural Circulation Small Modular Reactor NHR200-II

Applying Machine Learning to Improve BOA Analysis of CIPS/CILC

Event Tree Analysis for Material Relocation on Core Catcher in a Sodium-Cooled Fast Reactor

Performance Experimental Study on Siphon Breaker of CFR600

Data Driven Methods for Break Size and Location Estimation in LOCA Based on Deep Learning

Study on Time-Dependent Co-58 and Co-60 Activities in the Primary Coolant of CPR1000 PWRs

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

Optimization of the Tritium Production and Discharge in HPR1000

Optimizing Material/Component Fabrication Processing for Improving Service Performance in Nuclear Power Plant Coolants

Preliminary Study on the Migration of Polonium-210 in Lead-Based Fast Reactor

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

Comparison of Numerical Analysis Methods of Coolant Environmental Fatigue Based on Strain Rate Control

Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients

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