Topics: Nuclear power stations , Sensors , Signal reconstruction , Instrumentation , Control systems , Pressurized water reactors , Reliability , Signals , Steam

Research on a Circuit Health Assessment Technology Combining Mechanism Knowledge and Data Driven Technology

Guilian Shi, Huang Xiaojin, Mo Changyu

ICONE 2022; V001T01A007https://doi.org/10.1115/ICONE29-89387

Abstract

View Articletitled, Research on a Circuit Health Assessment Technology Combining Mechanism Knowledge and Data Driven Technology

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Topics: Circuits , Failure , Physics , Electronic equipment , Hardware , Design , Failure mechanisms , Nuclear power , Nuclear power stations , Time series

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

Yaoxin Ye, Pengtao Fu, Zhijun Li

ICONE 2022; V001T01A008https://doi.org/10.1115/ICONE29-89461

Abstract

View Articletitled, Research on the Influence of Degassing on the Release of Fission Gases in PWRs

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

Cause Analysis of Oil Leakage of the Skeleton Oil Seal for a Diesel Engine Pre-Lubricated Oil Pump

Binsheng Lai, Zhi Chen, Jianming Li, Xin Zhou

ICONE 2022; V001T01A009https://doi.org/10.1115/ICONE29-89465

Abstract

View Articletitled, Cause Analysis of Oil Leakage of the Skeleton Oil Seal for a Diesel Engine Pre-Lubricated Oil Pump

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Topics: Diesel engines , Leakage , Oil pumps

Seismic Analysis of Fuel Transfer Tube Gate Valve

Su Ziwei, Zhang Xin

ICONE 2022; V001T01A010https://doi.org/10.1115/ICONE29-89869

Abstract

View Articletitled, Seismic Analysis of Fuel Transfer Tube Gate Valve

PDF

Topics: Design , Fuels , Gates (Closures) , Seismic analysis , Valves

Multiplication Factor Prediction Feasibility Study for the BEAVRS Core Based on the LSTM Algorithm

Ren Chang-an, Lei Ji-chong, Yang Xiao-hua

ICONE 2022; V001T01A011https://doi.org/10.1115/ICONE29-90164

Abstract

View Articletitled, Multiplication Factor Prediction Feasibility Study for the BEAVRS Core Based on the LSTM Algorithm

PDF

Topics: Algorithms , Cycles , Engineering simulation , Errors , Machine learning , Simulation

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

Zhang Liu-Huan, Wu Xiang, Ouyang Dong-Fang

ICONE 2022; V001T01A012https://doi.org/10.1115/ICONE29-90517

Abstract

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

PDF

Topics: Boilers , Feedback , Hydrogen

Proposal of Detailed Procedures of Determining Rational In-Service Inspection Requirements Based on System Based Code Concept

Hiroki Yada, Shigeru Takaya, Kyoichi Morohoshi, Shinobu Yokoi

ICONE 2022; V001T01A013https://doi.org/10.1115/ICONE29-90542

Abstract

View Articletitled, Proposal of Detailed Procedures of Determining Rational In-Service Inspection Requirements Based on System Based Code Concept

PDF

Topics: In-service inspection , Inspection , Sodium fast reactors

Design Verification of Minimum Flow Valve of the Main Feed Water Pump Based on the Full-Range Simulation Platform of CPR 1000

Zhenhua Zhang, Bo Zhang, Chaoying Zheng

ICONE 2022; V001T01A014https://doi.org/10.1115/ICONE29-90543

Abstract

View Articletitled, Design Verification of Minimum Flow Valve of the Main Feed Water Pump Based on the Full-Range Simulation Platform of CPR 1000

PDF

Topics: Design , Feedwater , Flow (Dynamics) , Pumps , Simulation , Valves

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

Zhenhua Zhang, Bo Zhang, Chaoying Zheng

ICONE 2022; V001T01A015https://doi.org/10.1115/ICONE29-90544

Abstract

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

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Topics: Design , Heat , Nuclear power stations , Water

Research on Optimization of Reload Startup Physics Tests in Sanmen Nuclear Power Plant

Jianfeng Shi, Qingxiang Yang, Lihua Wang, Lijiang Chen, Ang Li

ICONE 2022; V001T01A016https://doi.org/10.1115/ICONE29-90570

Abstract

View Articletitled, Research on Optimization of Reload Startup Physics Tests in Sanmen Nuclear Power Plant

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Topics: Equilibrium (Physics) , Leakage , Nuclear power stations , Optimization , Physics , Sensors , Economics , Design , Risk , Simulation

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

ICONE 2022; V001T01A017https://doi.org/10.1115/ICONE29-90677

Abstract

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

PDF

Topics: Boilers , Dynamic response , Heat transfer , Time-domain analysis , Stress , Modal analysis , Dynamic response analysis , Emission spectroscopy , Finite element model , Frequency-domain analysis

Logic Equation of Operating Situations and Man-Machine Interface Design for NPP

Tianqi Si, Yuqi Wang, Yu Du

ICONE 2022; V001T01A018https://doi.org/10.1115/ICONE29-90725

Abstract

View Articletitled, Logic Equation of Operating Situations and Man-Machine Interface Design for NPP

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Topics: Design , Nuclear power stations , User interfaces

Research on Standardization System of Smart Site for Nuclear Power Plant Construction

Changchun Ren, Gang Wu

ICONE 2022; V001T01A019https://doi.org/10.1115/ICONE29-91252

Abstract

View Articletitled, Research on Standardization System of Smart Site for Nuclear Power Plant Construction

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Topics: Nuclear construction

Deuterization Process and Result Analysis of Resin in Heavy Water Purification System of a Reactor

Wen Juan Zhang, Fengxia Xu, Xiao Hua

ICONE 2022; V001T01A020https://doi.org/10.1115/ICONE29-91360

Abstract

View Articletitled, Deuterization Process and Result Analysis of Resin in Heavy Water Purification System of a Reactor

PDF

Topics: Resins , Water treatment

Study on Maintenance Method of Design Basis in Operating Nuclear Power Plants

Guangjun Wu, Wei Xiao

ICONE 2022; V001T01A021https://doi.org/10.1115/ICONE29-91484

Abstract

View Articletitled, Study on Maintenance Method of Design Basis in Operating Nuclear Power Plants

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Topics: Design , Maintenance , Nuclear power stations , Safety

Developing Intelligent Equipment Monitoring System of Nuclear Power Plants to Improve Plant Performance

Jianming Yu, Yibiao Cai

ICONE 2022; V001T01A022https://doi.org/10.1115/ICONE29-91638

Abstract

View Articletitled, Developing Intelligent Equipment Monitoring System of Nuclear Power Plants to Improve Plant Performance

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Topics: Condition monitoring , Fault diagnosis , Maintenance , Monitoring systems , Nuclear power stations , Pattern recognition , Economics , Safety , Carbon , Construction

Effect of Carbon Content on the Resistance to Intergranular Corrosion of Alloy 800H

Qiang Zhong, Man Wang, Wen-Qiang Sun, Jun-Jie Wu, Jiong Qian, Sen-Sen Ning

ICONE 2022; V001T01A023https://doi.org/10.1115/ICONE29-91676

Abstract

View Articletitled, Effect of Carbon Content on the Resistance to Intergranular Corrosion of Alloy 800H

PDF

Topics: Alloys , Carbon , Computer software , Corrosion , Precipitation , Simulation

Reliability Analysis of Off-Plant Power for Multi-Units

Chen Honghao, Ren Cheng, Wu Jian, Liu Deyi, Luo Yang, Zou Shengjia, Wang Zilong

ICONE 2022; V001T01A024https://doi.org/10.1115/ICONE29-91870

Abstract

View Articletitled, Reliability Analysis of Off-Plant Power for Multi-Units

PDF

Topics: Accidents , Emergencies , Event history analysis , Failure , Modeling , Nuclear power , Nuclear power stations , Power grids , Probabilistic safety assessment , Reliability

Research on Operation Life Extension Time Limited Aging Analysis Key Method for Electrical Penetration Assembly of Nuclear Power Plants

Binfeng Wang, Zhilin Chen, Ping Huang, Zhenhao Shi, Yanwei Zhang, Tao Liu

ICONE 2022; V001T01A025https://doi.org/10.1115/ICONE29-91884

Abstract

View Articletitled, Research on Operation Life Extension Time Limited Aging Analysis Key Method for Electrical Penetration Assembly of Nuclear Power Plants

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Topics: Licensing , Life extension , Manufacturing , Nuclear power stations

Fault Diagnosis of CRDM Based on EEMD-Wavelet Threshold Denoising and WOA-KELM

Luo Jingdong, Chen Ling, Zhang Liming

ICONE 2022; V001T01A026https://doi.org/10.1115/ICONE29-91936

Abstract

View Articletitled, Fault Diagnosis of CRDM Based on EEMD-Wavelet Threshold Denoising and WOA-KELM

PDF

Topics: Fault diagnosis , Wavelets

Optimization Design About Generating or Removing Vapor Space Of The Primary Loop Pressurizer

Fan Ke

ICONE 2022; V001T01A027https://doi.org/10.1115/ICONE29-91960

Abstract

View Articletitled, Optimization Design About Generating or Removing Vapor Space Of The Primary Loop Pressurizer

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Topics: Design , Optimization , Vapors

The Effect of Specimen Size and Surface Roughness on Tensile Strength of Nuclear Graphite

Yuxin Guan, Yingjie Zhan, Shuiyong Wang, Qingwu Wang, Wenxin Ti, Bing Gong

ICONE 2022; V001T01A028https://doi.org/10.1115/ICONE29-91966

Abstract

View Articletitled, The Effect of Specimen Size and Surface Roughness on Tensile Strength of Nuclear Graphite

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Topics: Graphite , Size effect , Surface roughness , Tensile strength

Analysis Method and Application of Maintenance Rules for Main Steam System in Qinshan no.1 Nuclear Power Plant

Yan Jun Jin

ICONE 2022; V001T01A029https://doi.org/10.1115/ICONE29-92056

Abstract

View Articletitled, Analysis Method and Application of Maintenance Rules for Main Steam System in Qinshan no.1 Nuclear Power Plant

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Topics: Maintenance , Nuclear power stations , Reliability , Steam

Construction and Lean Management of Filters Cycle Life Cycle in Nuclear Safety-Related Ventilation Systems

Jianxing Du, Caiyuan Deng

ICONE 2022; V001T01A030https://doi.org/10.1115/ICONE29-92076

Abstract

View Articletitled, Construction and Lean Management of Filters Cycle Life Cycle in Nuclear Safety-Related Ventilation Systems

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Topics: Construction , Cycles , Filters , Safety , Ventilation , Ventilation equipment

Analysis and Mitigation Strategy on the Decreasing Opening of Thermal Pressurizer Pilot Operated Safety Relief Valves

Wensheng Hu, Chaofan Guo, Haisheng Zhao, Zhaoji Ruan, Jidong Min, Pencheng Du, Xinxin Wang

ICONE 2022; V001T01A031https://doi.org/10.1115/ICONE29-92099

Abstract

View Articletitled, Analysis and Mitigation Strategy on the Decreasing Opening of Thermal Pressurizer Pilot Operated Safety Relief Valves

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Topics: Leakage , Relief valves , Safety

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

Kechen Xu, Rui Wang, Hongmei Yan, Wei Bai

ICONE 2022; V001T01A032https://doi.org/10.1115/ICONE29-92140

Abstract

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

PDF

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

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

ICONE 2022; V001T01A033https://doi.org/10.1115/ICONE29-92184

Abstract

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

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

Study on the Feasibility of Power Supply Migration in Production Preparation Area of the Nuclear Power Station

Lin Yonggang

ICONE 2022; V001T01A034https://doi.org/10.1115/ICONE29-92186

Abstract

View Articletitled, Study on the Feasibility of Power Supply Migration in Production Preparation Area of the Nuclear Power Station

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Topics: Energy generation , Nuclear power stations , Economics , Energy consumption , Heating , Hydropower , Nuclear power , Power grids

Analysis of Single-Line Fast Starting Technology for Emergency Diesel Generators in Nuclear Power Plants

Hongzhou Li

ICONE 2022; V001T01A035https://doi.org/10.1115/ICONE29-92194

Abstract

View Articletitled, Analysis of Single-Line Fast Starting Technology for Emergency Diesel Generators in Nuclear Power Plants

PDF

Topics: Diesel generators , Emergencies , Nuclear power stations

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

ICONE 2022; V001T01A036https://doi.org/10.1115/ICONE29-92209

Abstract

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

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

Reactor Pit Injection Isolation Design Modification and Experience Feedback of UK HPR1000 In-Vessel Retention

Hua Zheng, Shuhong Wei

ICONE 2022; V001T01A037https://doi.org/10.1115/ICONE29-92239

Abstract

View Articletitled, Reactor Pit Injection Isolation Design Modification and Experience Feedback of UK HPR1000 In-Vessel Retention

PDF

Topics: Design , Feedback , Vessels , Nuclear power stations , Safety , Accident management , Accidents , Construction , Control panels , Control rooms

Development and Verification of New Drum Filter Equipment for Nuclear Power Plants

Huang Xiaojie, Lin Yishan, Xie Honghu, Li Yanqing, Yang Jinchun

ICONE 2022; V001T01A038https://doi.org/10.1115/ICONE29-92243

Abstract

View Articletitled, Development and Verification of New Drum Filter Equipment for Nuclear Power Plants

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Topics: Cooling , Engineering prototypes , Filters , Nuclear power stations , Safety , Seismic analysis

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

ICONE 2022; V001T01A039https://doi.org/10.1115/ICONE29-92381

Abstract

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

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Topics: Design , Heating , Water , Water desalination

Discussion on Setting Value and Grounding Mode of Grounding Protection for the Construction of a Nuclear Power Plant Power Loop Network

Wang Yuhan, Wang Zhijian

ICONE 2022; V001T01A040https://doi.org/10.1115/ICONE29-92480

Abstract

View Articletitled, Discussion on Setting Value and Grounding Mode of Grounding Protection for the Construction of a Nuclear Power Plant Power Loop Network

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Topics: Construction , Nuclear power stations

Research on Precision Water Reactor Fuel Servo Operation System

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

ICONE 2022; V001T01A041https://doi.org/10.1115/ICONE29-92493

Abstract

View Articletitled, Research on Precision Water Reactor Fuel Servo Operation System

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

Analysis of Contribution Degree of Vibration Transmission of Bolted Structure

Shuai Liu, Wanyou Li, Xuan Huang, Furui Xiong, Xiaozhou Jiang, Liwei Deng

ICONE 2022; V001T01A042https://doi.org/10.1115/ICONE29-92499

Abstract

View Articletitled, Analysis of Contribution Degree of Vibration Transmission of Bolted Structure

PDF

Topics: Vibration

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

Xiaolin Liu, Wei Meng, Li Lu, Jianwen Li

ICONE 2022; V001T01A043https://doi.org/10.1115/ICONE29-92507

Abstract

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

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

Comparison Of Radiation Embrittlement Prediction Models for Reactor Pressure Vessel

Kexin Cai, Ping Huang, Wangjie Qian, Minyu Fan, Shuang Qi, Guodong Zhang, Yanwei Zhang

ICONE 2022; V001T01A044https://doi.org/10.1115/ICONE29-92513

Abstract

View Articletitled, Comparison Of Radiation Embrittlement Prediction Models for Reactor Pressure Vessel

PDF

Topics: Embrittlement , Radiation (Physics) , Reactor vessels

Research on the Reactor and Turbine Matching Key Technology of CPR1000 Nuclear Power Plant for Industrial Steam Supply

Zhou Mingjia, Wang Kai, Zhang Wei, Zhu Jianmin, Mao Yulong

ICONE 2022; V001T01A045https://doi.org/10.1115/ICONE29-92527

Abstract

View Articletitled, Research on the Reactor and Turbine Matching Key Technology of CPR1000 Nuclear Power Plant for Industrial Steam Supply

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Topics: Nuclear power , Nuclear power stations , Steam , Turbines

Study on Technology and Application for Health Assessment of Electronic Equipment

Shi Guilian, Huang Xiaojin, Zhao Xiaopeng

ICONE 2022; V001T01A046https://doi.org/10.1115/ICONE29-92632

Abstract

View Articletitled, Study on Technology and Application for Health Assessment of Electronic Equipment

PDF

Topics: Electronic equipment

Research on Technical Scheme of Rapid Power Reduction System Based on Gray Control Rods

Wei Li, Jianfeng Shi, Yulong Qin, Lihua Wang

ICONE 2022; V001T01A047https://doi.org/10.1115/ICONE29-92633

Abstract

View Articletitled, Research on Technical Scheme of Rapid Power Reduction System Based on Gray Control Rods

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Topics: Feedwater , Pumps , Rods , Nuclear power stations , Turbines

Study on Ultrasonic Inspection Technology of Fastening Bolts of Reactor Internals

Jianbang Tang, Yukun Wu, Weiqiang Wang, Guanbing Ma, Chenming Zeng, Junlong Xu

ICONE 2022; V001T01A048https://doi.org/10.1115/ICONE29-92644

Abstract

View Articletitled, Study on Ultrasonic Inspection Technology of Fastening Bolts of Reactor Internals

PDF

Topics: Inspection , Nuclear power stations , Nondestructive evaluation , Design , High pressure (Physics) , High temperature , In-service inspection , Irradiation (Radiation exposure) , Nuclear fuels , Probes

Research and Treatment of Pressure Regulation Defects in Fuel Circuit of Emergency Diesel Engine of One Nuclear Power Plant

Guo Feng

ICONE 2022; V001T01A049https://doi.org/10.1115/ICONE29-92726

Abstract

View Articletitled, Research and Treatment of Pressure Regulation Defects in Fuel Circuit of Emergency Diesel Engine of One Nuclear Power Plant

PDF

Topics: Circuits , Diesel engines , Emergencies , Fuels , Nuclear power stations , Pressure , Valves

Shutdown Seal Improvement Feasibility Analysis for CPR1000 Reactor Coolant Pump

Zhang Hengrui, Huang Qian, Fu Peiren, Zhang Daoke, Cai Rui, Sun Lei, Chen Qiuyang, Xue Feng

ICONE 2022; V001T01A050https://doi.org/10.1115/ICONE29-92727

Abstract

View Articletitled, Shutdown Seal Improvement Feasibility Analysis for CPR1000 Reactor Coolant Pump

PDF

Topics: Damage , Nuclear reactor coolants , Pumps

State Monitoring of Electric Gate Valve of Nuclear Power Plant Based on Kernel Principal Component Analysis and Jensen-Shannon Divergence

Xiaokun Wang, Hang Wang, Qiang Deng, Renyi Xu

ICONE 2022; V001T01A051https://doi.org/10.1115/ICONE29-92733

Abstract

View Articletitled, State Monitoring of Electric Gate Valve of Nuclear Power Plant Based on Kernel Principal Component Analysis and Jensen-Shannon Divergence

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Topics: Gates (Closures) , Nuclear power stations , Principal component analysis , Valves

Simulation Analysis of Main and Auxiliary Switching and Motor Starting in Nuclear Power Plants

Zhang Xingzhen, Sun Hui

ICONE 2022; V001T01A052https://doi.org/10.1115/ICONE29-92755

Abstract

View Articletitled, Simulation Analysis of Main and Auxiliary Switching and Motor Starting in Nuclear Power Plants

PDF

Topics: Motors , Nuclear power stations , Simulation , Simulation analysis , Stress

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

ICONE 2022; V001T01A053https://doi.org/10.1115/ICONE29-92760

Abstract

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

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

A Study on Health Assessment Technology for Sensor of Nuclear Power Plant Based on Dissimilarity of Residual Distribution

Wei Li, Yiwang Zhang, Yidan Yuan

ICONE 2022; V001T01A054https://doi.org/10.1115/ICONE29-92805

Abstract

View Articletitled, A Study on Health Assessment Technology for Sensor of Nuclear Power Plant Based on Dissimilarity of Residual Distribution

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Topics: Nuclear power stations , Sensors , State estimation , Instrumentation , Maintenance , Safety , Signals

Stable Feature Reweighting Transformer for Out-Of-Distribution Bearing Fault Diagnosis

Hao Chen, Jie Nie, Shusong Yu, Chenglong Wang, Peizhe Yin, Kun Yang

ICONE 2022; V001T01A055https://doi.org/10.1115/ICONE29-92830

Abstract

View Articletitled, Stable Feature Reweighting Transformer for Out-Of-Distribution Bearing Fault Diagnosis

PDF

Topics: Bearings , Fault diagnosis , Manufacturing , Aerospace industry , Nuclear engineering , Rolling bearings , Signals

Analysis and Simulation in Rotating Rectifier in Brushless Excitation of Nuclear Power Plant

Zhang Xingzhen, Sun Hui, Zhao Yanjun, Shi Xianzuo

ICONE 2022; V001T01A056https://doi.org/10.1115/ICONE29-92834

Abstract

View Articletitled, Analysis and Simulation in Rotating Rectifier in Brushless Excitation of Nuclear Power Plant

PDF

Topics: Excitation , Excitation systems , Nuclear power stations , Simulation , Bridges (Structures) , Maintenance , Failure , Nuclear power , Accidents , Construction

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

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

ICONE 2022; V001T01A057https://doi.org/10.1115/ICONE29-92871

Abstract

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

PDF

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

Research on Intelligent Classification Method of Primary Loop Transient in Nuclear Power Plant

Run Ze Zhang, Zhi Lin Chen, Yong Qiang Huang, Xin Chen

ICONE 2022; V001T01A058https://doi.org/10.1115/ICONE29-92874

Abstract

View Articletitled, Research on Intelligent Classification Method of Primary Loop Transient in Nuclear Power Plant

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Topics: Machine learning , Nuclear power stations , Transients (Dynamics)

Safety Analysis About Combined Heat and Power Generation of Nuclear Power Plant

Shiyao Liu

ICONE 2022; V001T01A059https://doi.org/10.1115/ICONE29-92883

Abstract

View Articletitled, Safety Analysis About Combined Heat and Power Generation of Nuclear Power Plant

PDF

Topics: Combined heat and power , Nuclear power stations , Safety

Study on the Influence of Roughness on Fuel Rod Gap Heat Transfer

Weichao Liu, Guoliang Zhang, Changzheng Li, Jin Cao, Shaofang Lin, Xiangang Fu, Lihong Nie, Yongjun Deng

ICONE 2022; V001T01A060https://doi.org/10.1115/ICONE29-93004

Abstract

View Articletitled, Study on the Influence of Roughness on Fuel Rod Gap Heat Transfer

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Topics: Cladding systems (Building) , Fuel rods , Heat transfer , Heat transfer coefficients , Surface roughness

The Study of Removal of Secondary Neutron Source of HPR-1000

Huiwen Xiao, Xiang Li, Guoming Liu, Yicheng Zhang, Zeng Shao, Min Xu, Xuan Yi, Haifeng Yang

ICONE 2022; V001T01A061https://doi.org/10.1115/ICONE29-93024

Abstract

View Articletitled, The Study of Removal of Secondary Neutron Source of HPR-1000

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Topics: Neutron sources , Spent nuclear fuels

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

ICONE 2022; V001T01A062https://doi.org/10.1115/ICONE29-93036

Abstract

View Articletitled, 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

PDF

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

Development and Application of Nuclear Power Plant Life Cycle Management Database Platform

Cao Guochang, Liu Zhao, Lv Fangming, Yang Zhenzhong, Jilang He, Cui Yixin

ICONE 2022; V001T01A063https://doi.org/10.1115/ICONE29-93061

Abstract

View Articletitled, Development and Application of Nuclear Power Plant Life Cycle Management Database Platform

PDF

Topics: Databases , Failure , Life cycle management , Nuclear power stations

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

ICONE 2022; V001T01A064https://doi.org/10.1115/ICONE29-93082

Abstract

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

PDF

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

Maintenance Strategy Optimization Based on AP-913 in Relay Protection Field

Yu Zhao, Ping Li, Kunpeng Tian, Xingwei Fei

ICONE 2022; V001T01A065https://doi.org/10.1115/ICONE29-93089

Abstract

View Articletitled, Maintenance Strategy Optimization Based on AP-913 in Relay Protection Field

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Topics: Maintenance , Optimization

Practical Issue Analysis of Miniature Circuit Breaker Implementation

Fei Xingwei, Tian Kunpeng, Zhao Yu, Li Ping

ICONE 2022; V001T01A066https://doi.org/10.1115/ICONE29-93092

Abstract

View Articletitled, Practical Issue Analysis of Miniature Circuit Breaker Implementation

PDF

Topics: Circuit breakers , Circuits

Analysis of the Influence of RCCA Swelling on Rod Falling and Study on Mitigation Measures

Zhipeng Lv, Guoliang Zhang, Changzheng Li, Weichao Liu, Shaofang Lin, Lihong Nie, Zhijun Li, Anlong Zhang

ICONE 2022; V001T01A067https://doi.org/10.1115/ICONE29-93095

Abstract

View Articletitled, Analysis of the Influence of RCCA Swelling on Rod Falling and Study on Mitigation Measures

PDF

Topics: Absorption , Cladding systems (Building) , Deformation , Design , Irradiation (Radiation exposure) , Neutrons , Pressurized water reactors , Rods , Safety , Shock absorbers

The Test of Leakage Current of Terminal Stator Winding of the 4# Generator and Defects Treatment

Kunpeng Tian, Ping Li, Yu Zhao, Xingwei Fei

ICONE 2022; V001T01A068https://doi.org/10.1115/ICONE29-93102

Abstract

View Articletitled, The Test of Leakage Current of Terminal Stator Winding of the 4# Generator and Defects Treatment

PDF

Topics: Generators , Leakage , Stators , Winding (process)

An Insulation Structure With Noise Reduction Function

Zhang Yicheng, Bian Pengfei, Zhang Kai

ICONE 2022; V001T01A069https://doi.org/10.1115/ICONE29-93144

Abstract

View Articletitled, An Insulation Structure With Noise Reduction Function

PDF

Topics: Acoustics , Insulation , Noise control , Thermal insulation , Nuclear power , Acoustical materials , Glass , Pipelines , Damping , Density

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

ICONE 2022; V001T01A070https://doi.org/10.1115/ICONE29-93230

Abstract

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

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

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

ICONE 2022; V001T01A071https://doi.org/10.1115/ICONE29-93265

Abstract

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

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

Safety Evaluation of Flowrate Dissymmetry on Nuclear Power Plant Operation

Dongyuan Li, Jinkai Wang, Jiaoshen Xu, Zengpei Zhu, Yaqi Zhang

ICONE 2022; V001T01A072https://doi.org/10.1115/ICONE29-93277

Abstract

View Articletitled, Safety Evaluation of Flowrate Dissymmetry on Nuclear Power Plant Operation

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Topics: Nuclear power plant operations , Nuclear reactor coolants , Nucleate boiling , Safety , Accidents , Flow (Dynamics) , Nuclear power stations , Pressurized water reactors , Feedwater , Steam

Optimization of Transient Control Method for RCV System

Yong Qiang Huang, Zhi Lin Chen, Xin Chen, Zheng Gu, Han Min Chen, Run Ze Zhang

ICONE 2022; V001T01A073https://doi.org/10.1115/ICONE29-93279

Abstract

View Articletitled, Optimization of Transient Control Method for RCV System

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Topics: Optimization , Transients (Dynamics)

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

ICONE 2022; V001T01A074https://doi.org/10.1115/ICONE29-93289

Abstract

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

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Topics: Boilers , Crack propagation , Metals , Nozzles , Safety

Investigation on Methodology of Coastdown Analysis and Design for Reactor Coolant Pump

Yun Zhong

ICONE 2022; V001T01A075https://doi.org/10.1115/ICONE29-93302

Abstract

View Articletitled, Investigation on Methodology of Coastdown Analysis and Design for Reactor Coolant Pump

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Topics: Design , Fluids , Inertia (Mechanics) , Nuclear reactor coolants , Pumps

Analysis and Treatment of Trolley Overload Problem of Fuel Transfer System

Wei Cheng, Zhengyang Liu, Panpan Chai, Zhiming Wang, Lei Wang

ICONE 2022; V001T01A076https://doi.org/10.1115/ICONE29-93315

Abstract

View Articletitled, Analysis and Treatment of Trolley Overload Problem of Fuel Transfer System

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Topics: Conveyor systems , Fuels

Safety Analysis for Transportation of Activated Secondary Neutron Source Assembly

Nanfeng Cao, Shouhai Yang, Enfei Xie, Shunping Jing

ICONE 2022; V001T01A077https://doi.org/10.1115/ICONE29-93332

Abstract

View Articletitled, Safety Analysis for Transportation of Activated Secondary Neutron Source Assembly

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Topics: Manufacturing , Neutron sources , Safety , Storage , Transportation systems

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

ICONE 2022; V001T01A078https://doi.org/10.1115/ICONE29-93343

Abstract

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

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Topics: Corrosion , Feedwater , Pipes , Pumps

Cause Analysis and Improvement of Drain Regulating Valve Blockage in Nuclear Power Plant

Xue Kai, Li Jing, Hu Wensheng, Guo Chaofan, Du Pengcheng

ICONE 2022; V001T01A079https://doi.org/10.1115/ICONE29-93344

Abstract

View Articletitled, Cause Analysis and Improvement of Drain Regulating Valve Blockage in Nuclear Power Plant

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Topics: Design , Nuclear power stations , Valves

Disorders in Fluid Filled Pipeline Structure With Elastic Helmholtz Resonators

Qingna Zeng, Donghui Wang, Fenggang Zang, Yixiong Zhang, Bihao Wang, Zhihao Yuan

ICONE 2022; V001T01A080https://doi.org/10.1115/ICONE29-93421

Abstract

View Articletitled, Disorders in Fluid Filled Pipeline Structure With Elastic Helmholtz Resonators

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Topics: Energy gap , Fluids , Pipelines , Acoustics , Stability , Vibration , Cavities , Design , Engineering systems and industry applications , Finite element methods