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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 titled, Design of Combined Water System of Demineralized Water and Boiler Make-Up Water in Nuclear Engineering
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Topics: Boilers, Design, Nuclear engineering, Water, Nuclear power, Manufacturing, Combined heat and power, Heating boilers, Water pollution, Water supply
Proceedings Papers

Experience Feedback Report on Hydrogen Meter Discontinuity of Steam Generator Overflow Tube

Zhang Liu-Huan, Wu Xiang, Ouyang Dong-Fang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A012, August 8–12, 2022
Paper No: ICONE29-90517
DOI: https://doi.org/10.1115/ICONE29-90517
View Paper titled, Experience Feedback Report on Hydrogen Meter Discontinuity of Steam Generator Overflow Tube
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Topics: Boilers, Feedback, Hydrogen
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
View Paper titled, Sensitivity Calculation of Lower Shell Pressure Parameters in Advanced Nuclear Power Plant Accidents
Click here to open pdf in another window PDF for Sensitivity Calculation of Lower Shell Pressure Parameters in Advanced Nuclear Power Plant Accidents
Topics: Containment, Nuclear reactor accidents, Pressure, Shells, Temperature, Accidents, Boilers, Circuits, Coolants, Design
Proceedings Papers

Crack Propagation Analysis of Dissimilar Metal Weld for Steam Generator Nozzle Safety End

Shuang Qi, Wenxin Xiang, Ping Huang, Fangmao Ning, Minyu Fan, Lei Qi, Mingya Chen, Jun Xu
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A074, August 8–12, 2022
Paper No: ICONE29-93289
DOI: https://doi.org/10.1115/ICONE29-93289
View Paper titled, Crack Propagation Analysis of Dissimilar Metal Weld for Steam Generator Nozzle Safety End
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Topics: Boilers, Crack propagation, Metals, Nozzles, Safety
Proceedings Papers

Study on Analysis Method of LOCA Dynamic Response for Steam Generator Heat Transfer Tube

Xifeng Lu, Furui Xiong, Xinjun Wang, Honglei Ai, Bingjin Li, Xuejiao Shao, Kang Yang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A017, August 8–12, 2022
Paper No: ICONE29-90677
DOI: https://doi.org/10.1115/ICONE29-90677
View Paper titled, Study on Analysis Method of LOCA Dynamic Response for Steam Generator Heat Transfer Tube
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Topics: Boilers, Dynamic response, Heat transfer, Time-domain analysis, Stress, Modal analysis, Dynamic response analysis, Emission spectroscopy, Finite element model, Frequency-domain analysis
Proceedings Papers

Study on the Influence of Power Reduction Process on the Leakage Rate of Steam Generator

Zhao Zhang, Jun-Jie Yan, Wen-Bo Wang, Dao-Tong Chong, Min-Hua Su, Zi-Chun Wang, Rong-Fa Shen
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A087, August 8–12, 2022
Paper No: ICONE29-93629
DOI: https://doi.org/10.1115/ICONE29-93629
View Paper titled, Study on the Influence of Power Reduction Process on the Leakage Rate of Steam Generator
Click here to open pdf in another window PDF for Study on the Influence of Power Reduction Process on the Leakage Rate of Steam Generator
Topics: Boilers, Leakage
Proceedings Papers

Experimental Study on Pressure Pulsation of RCP With Steam Generator

Song Huang, Yu Song, Junlian Yin, Rui Xu, Dezhong Wang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A081, August 8–12, 2022
Paper No: ICONE29-93423
DOI: https://doi.org/10.1115/ICONE29-93423
View Paper titled, Experimental Study on Pressure Pulsation of RCP With Steam Generator
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Topics: Boilers, Nuclear reactor coolants, Pressure, Pumps
Proceedings Papers

An Assessment Method of Digital Human-Machine Interaction Complexity in Nuclear Power Plants: EHMIC

Xueyang Liu, Lu Cao
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A034, August 8–12, 2022
Paper No: ICONE29-93218
DOI: https://doi.org/10.1115/ICONE29-93218
View Paper titled, An Assessment Method of Digital Human-Machine Interaction Complexity in Nuclear Power Plants: EHMIC
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Topics: Boilers, Entropy, Machinery, Nuclear power stations, Rupture
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
View Paper titled, Investigation of Model-Based Anomaly Detection Method for the Full-Power Natural Circulation Small Modular Reactor NHR200-II
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Topics: Accidents, Boilers, Control systems, Coolants, Heating, Nuclear power, Pressurized water reactors, Pumps, Radioactivity, Safety
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 titled, UTSG Water Level Prediction Model Based on LSTM and GRU Algorithms
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Topics: Algorithms, Boilers, Water
Proceedings Papers

Analysis of Different Requirements of Dissimilar Metal Joint Welding Procedure Qualification Between RCC-M and ASME BPVC

Wang Pei, Chen Dongxu, Yang Shumin
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A007, August 8–12, 2022
Paper No: ICONE29-91363
DOI: https://doi.org/10.1115/ICONE29-91363
View Paper titled, Analysis of Different Requirements of Dissimilar Metal Joint Welding Procedure Qualification Between RCC-M and ASME BPVC
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Topics: ASME Boiler and Pressure Vessel Code, Boilers, Metals, Welding
Proceedings Papers

Research on Measurement Method of a Device for Measuring the Perpendicularity of Tubesheet Hole

Xianghua Xu, Guihong Hu
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A046, August 8–12, 2022
Paper No: ICONE29-93045
DOI: https://doi.org/10.1115/ICONE29-93045
View Paper titled, Research on Measurement Method of a Device for Measuring the Perpendicularity of Tubesheet Hole
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Topics: Accuracy and precision, Boilers, Bridges (Structures), Dimensions, Errors, Heat, Inspection, Manufacturing, Surface roughness
Proceedings Papers

High Temperature Gas Cooled Reactor Steam Generator Research on Stress-Rupture Test of High Temperature Materials and Welded Joints

Shimei Bao
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A039, August 8–12, 2022
Paper No: ICONE29-92956
DOI: https://doi.org/10.1115/ICONE29-92956
View Paper titled, High Temperature Gas Cooled Reactor Steam Generator Research on Stress-Rupture Test of High Temperature Materials and Welded Joints
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Topics: Boilers, Gas cooled reactors, High temperature, High temperature materials, Rupture, Stress, Very high temperature reactors, Welded joints
Proceedings Papers

Research on Key Assembling Technology of Tube Bundle Assembly of Hualong-1 Type Steam Generator

Ye Wanbing, Liu Yuanbin, Chen Yaomao, Zhang Sanjun, Wang Aili
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A023, August 8–12, 2022
Paper No: ICONE29-92130
DOI: https://doi.org/10.1115/ICONE29-92130
View Paper titled, Research on Key Assembling Technology of Tube Bundle Assembly of Hualong-1 Type Steam Generator
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Topics: Boilers, Manufacturing, Vibration
Proceedings Papers

Non-Destructive Examination of PWR Steam Generator Tube-Tube Plate Welds After Repairing Melting Damage

Yan Zhang, JianLei Zhang, Zhonghe Cheng
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A045, August 8–12, 2022
Paper No: ICONE29-92978
DOI: https://doi.org/10.1115/ICONE29-92978
View Paper titled, Non-Destructive Examination of PWR Steam Generator Tube-Tube Plate Welds After Repairing Melting Damage
Click here to open pdf in another window PDF for Non-Destructive Examination of PWR Steam Generator Tube-Tube Plate Welds After Repairing Melting Damage
Topics: Boilers, Damage, Maintenance, Melting, Nondestructive evaluation, Pressurized water reactors, Welded joints
Proceedings Papers

Root Cause Analysis of Nonrelevant Indication of Magnetic Particle Test on 18MND5 Steel Welded Joints in the Steam Generator of a Nuclear Power Project

Yanbing Guo, Yanhong Lu, Wang Zhang, Miaosen Yang, Xiyang Liu, Binfeng Lu
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A029, August 8–12, 2022
Paper No: ICONE29-92313
DOI: https://doi.org/10.1115/ICONE29-92313
View Paper titled, Root Cause Analysis of Nonrelevant Indication of Magnetic Particle Test on 18MND5 Steel Welded Joints in the Steam Generator of a Nuclear Power Project
Click here to open pdf in another window PDF for Root Cause Analysis of Nonrelevant Indication of Magnetic Particle Test on 18MND5 Steel Welded Joints in the Steam Generator of a Nuclear Power Project
Topics: Boilers, Magnetic particles, Nuclear power, Root cause analysis, Steel, Welded joints
Proceedings Papers

Design Improvement of the Discharge Proposal Preventing SG Overfill After SGTR in HPR1000 PWR

Qinghua Li, Jun Fang, Yafei Li, Bin Zhao, Guangfei Wang
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A035, August 8–12, 2022
Paper No: ICONE29-93093
DOI: https://doi.org/10.1115/ICONE29-93093
View Paper titled, Design Improvement of the Discharge Proposal Preventing SG Overfill After SGTR in HPR1000 PWR
Click here to open pdf in another window PDF for Design Improvement of the Discharge Proposal Preventing SG Overfill After SGTR in HPR1000 PWR
Topics: Accidents, Design, Flow (Dynamics), Pipelines, Pressurized water reactors, Safety, Boilers, Fluids, Pressure, Testing performance
Proceedings Papers

Design of Liquid Level Control System of Steam Generator Based on Neural Network PID Controller

Longhao Xiao, Peiwei Sun, Xinyu Wei
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A063, August 8–12, 2022
Paper No: ICONE29-91880
DOI: https://doi.org/10.1115/ICONE29-91880
View Paper titled, Design of Liquid Level Control System of Steam Generator Based on Neural Network PID Controller
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Topics: Artificial neural networks, Boilers, Control equipment, Control systems, Design
Proceedings Papers

Dynamic Modeling and Simulation of MHTGR Plant Start-Up and Shutdown System

Bowen Li, Zhe Dong, Junyi Li
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A019, August 8–12, 2022
Paper No: ICONE29-90263
DOI: https://doi.org/10.1115/ICONE29-90263
View Paper titled, Dynamic Modeling and Simulation of MHTGR Plant Start-Up and Shutdown System
Click here to open pdf in another window PDF for Dynamic Modeling and Simulation of MHTGR Plant Start-Up and Shutdown System
Topics: Dynamic modeling, Simulation, Very high temperature reactors, Modeling, Nuclear power stations, Steam, Water, Boilers, Coal, Computer simulation
Proceedings Papers

Numerical Simulation of Two-Phase Flow Using Eulerian-Eulerian Model With One-Group Interfacial Area Transport Equation

Yao Liu, Jinyu Han, Chenru Zhao, Hanliang Bo
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A117, August 8–12, 2022
Paper No: ICONE29-93769
DOI: https://doi.org/10.1115/ICONE29-93769
View Paper titled, Numerical Simulation of Two-Phase Flow Using Eulerian-Eulerian Model With One-Group Interfacial Area Transport Equation
Click here to open pdf in another window PDF for Numerical Simulation of Two-Phase Flow Using Eulerian-Eulerian Model With One-Group Interfacial Area Transport Equation
Topics: Computer simulation, Fluids, Two-phase flow, Flow (Dynamics), Information Analysis Centers, Bubbles, Bubbly flow, Boilers, Nuclear power stations, Simulation results