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Proceedings Papers

Proceedings Volume Cover
2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
  • Nuclear Engineering Division
ISBN:
978-0-7918-5779-3
Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors

Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant

Analysis and Research on Diagnosis Methods of AFA 3G Fuel Assembly Leakage
Wei Xiaohui
ICONE 2017; V001T01A001https://doi.org/10.1115/ICONE25-66024
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Topics: Fuels , Leakage , Manufacturing , Cladding systems (Building) , Design , Failure , Nuclear fission
Application of Joint Boring Technique in Solving RCL Wall Thickness Problem
Huadong Zhu
ICONE 2017; V001T01A002https://doi.org/10.1115/ICONE25-66026
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Topics: Wall thickness , Design , In-service inspection , Inspection , Nuclear power , Nuclear power stations , Nuclear reactor coolants , Reactor vessels , Welded joints , Boilers
Nuclear Power Project Performance Management System Research Based on the KPIs
Wenzhao Zhao, Hang Yu, Limin Tian, Xiaobing Li, Guangyi Yan
ICONE 2017; V001T01A003https://doi.org/10.1115/ICONE25-66073
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Topics: Nuclear power , Project management , Feedback , Nuclear industry , Performance , Performance evaluation , Process control
A Criterion for Evaluating Plastic Collapse Load: Plastic Work-Tangent Criterion
Ying Zhang
ICONE 2017; V001T01A004https://doi.org/10.1115/ICONE25-66116
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Topics: Collapse , Stress , Design , Finite element analysis , Nozzles , Pressure vessels , Reactor vessels
Studies on Safety Assessment Method for Operating License Extension of Nuclear Power Plants in China
Zhilin Chen, Ping Huang, Chunhui Wang, Zhiyuan Chi, Fangjie Shi, Yong Wang, Yinghui An, Yanwei Zhang, Jun Wang, Fei Xue
ICONE 2017; V001T01A005https://doi.org/10.1115/ICONE25-66173
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Topics: China , Licensing , Nuclear power stations , Safety
Torsional Vibration Monitoring on Half-Speed Turbine of Nuclear Power Plant
Zhaojie Li, Pengcheng Zhao, Qiuhua Ni, Xuejie Han, Xiangxiang Dong
ICONE 2017; V001T01A006https://doi.org/10.1115/ICONE25-66177
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Topics: Nuclear power stations , Turbines , Vibration , Power grids , Vibration monitors
Nuclear Power Plant Flexible Power Operation Capability Analysis
Ye Cheng, Wang Minglu, Qiu Zhongming, Wang Yong
ICONE 2017; V001T01A007https://doi.org/10.1115/ICONE25-66185
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Topics: Nuclear power stations , Stress , Renewable energy sources , Safety , Stability
CANDU PHWR Feeder Pipe FAC Mitigation Design Modification and Validation During Operation
Tang Jiongran, Shang Junmin, Yang Yue, Yuan Jianzhong
ICONE 2017; V001T01A008https://doi.org/10.1115/ICONE25-66205
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Topics: Design , Heavy water reactors , Pipes , Corrosion , Flow (Dynamics) , Heat , In-service inspection , Nuclear power , Nuclear power stations , Service life (Equipment)
Economic and Operational Characteristics of PWR Unit Participation in Grid Peak-Load Regulation
Ning Xiao, Qingchuan Zhang, Zhiyuan Xu, Yanna Li
ICONE 2017; V001T01A009https://doi.org/10.1115/ICONE25-66237
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Topics: Peak load , Pressurized water reactors , Power grids , Stress , Power stations , China , Economics , Nuclear power , Wind , Energy efficiency
Advanced Gen III PWR NPP General Operation Strategy Design Based on Function Analysis and Task Analysis Technology
Xu Zhao, Miao Zhuang
ICONE 2017; V001T01A010https://doi.org/10.1115/ICONE25-66259
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Topics: Design , Nuclear power stations , Pressurized water reactors , Task analysis
Boring Analysis in Solving Out-of-Tolerance of Wall Thickness of Surge Line in Nuclear Power Project
Huadong Zhu
ICONE 2017; V001T01A011https://doi.org/10.1115/ICONE25-66339
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Topics: Nuclear power , Surges , Wall thickness , Design , Pipes , Nuclear reactor coolants , Pressure , Engineering drawings , Fittings , Heating
Application of Laser Measurement and Modeling Technology in Nuclear Power Project RCL Installation
Huadong Zhu
ICONE 2017; V001T01A012https://doi.org/10.1115/ICONE25-66340
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Topics: Lasers , Modeling , Nuclear power , Cutting , Boilers , Computer simulation , Construction , Delays , Manufacturing , Nuclear power stations
Neutron Embrittlement Analysis of Qinshan 320MWe RPV on OLE
Tao Hongxin, He Yinbiao, Cao Ming, Shen Rui
ICONE 2017; V001T01A013https://doi.org/10.1115/ICONE25-66361
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Topics: Embrittlement , Neutrons , Fracture (Materials) , Fracture (Process) , Irradiation (Radiation exposure) , Pressurized water reactors , Safety , Service life (Equipment) , Fracture mechanics , High pressure (Physics)
Application of Underwater Electric Discharge Machining in Nuclear Power Plant
Xiangming Huang, Ran Huang
ICONE 2017; V001T01A014https://doi.org/10.1115/ICONE25-66572
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Topics: Electrical discharge machining , Nuclear power stations , Cutting , Irradiation (Radiation exposure) , Machining , Welding , Design , Electrodes , Electronic systems , Erosion
Ionizing/Displacement Synergistic Effects in Bipolar Operational Amplifiers Induced by Mixed Reactor Neutron and Gamma Irradiation
Chenhui Wang, Wei Chen, Xiaoming Jin, Yan Liu, Chao Qi, Shanchao Yang, Chenghui Wan
ICONE 2017; V001T01A015https://doi.org/10.1115/ICONE25-66575
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Topics: Displacement , Irradiation (Radiation exposure) , Neutrons , Gamma rays , Control systems , Nuclear reactors , Failure , Instrumentation , Radiation (Physics) , Radiation damage
Exploration on Ranking Obsolescence Issues of High Priority for Nuclear Power Plant Based on AHP
Wenmin Yu, Chun Gui, Ge Tao, Fangming Lv
ICONE 2017; V001T01A016https://doi.org/10.1115/ICONE25-66587
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Topics: Nuclear power stations
A Fast Particle Swarm Optimization (PSO) Method for Detecting Control Valve Stiction
Dongming Zhang, Guangxin Zhang, Xu Wang
ICONE 2017; V001T01A017https://doi.org/10.1115/ICONE25-66608
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Topics: Particle swarm optimization , Stiction , Valves , Feedwater , Fluids , Maintenance , Nuclear power stations , Oscillations , Sprays
Experimental Research and Assessment for Thermal Fatigue in T-Junction With Mixing Flows
Chen Yinqiang, Zhao Xinglei, Gan Guohua, Xu Kaili, Wang Yanzhi, Zou Jinqiang, Gui Chun
ICONE 2017; V001T01A018https://doi.org/10.1115/ICONE25-66636
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Topics: Fatigue , Flow (Dynamics) , Junctions , Pipes , Fatigue life , Nuclear power stations , Stress concentration , Temperature , Accidents , Computational methods
Improvement of the Total Beta Monitoring Channel of the Radioactive Gaseous Effluent in HTR-10
Liqiang Wei, Feng Xie, Jian Zheng, Ling Liu, Chuangguo Hu
ICONE 2017; V001T01A019https://doi.org/10.1115/ICONE25-66652
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Topics: Circuits , Design , Ionization chambers , Printed circuit boards , Radiation measurement , Radioactive substances , Reliability , Sensors , Stability , Very high temperature reactors
Research on Analysis and Experiment of Multistage Orifice Throttle in Nuclear Power Plant
Yan Liu, Xue-long Yang, Xian-yuan Wang, Rui-feng Tian
ICONE 2017; V001T01A020https://doi.org/10.1115/ICONE25-66670
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Topics: Design , Manufacturing , Nuclear power stations , Regression analysis
Ageing Inspection for Cross-Linked Polyolefin Insulation Cable in NPP Using Dielectric Property
Zhang Yizhou, Wang Lei, Zhao Pengyu, Wang Liang, Gao Xuan, Tao Ge, Ma Huiming
ICONE 2017; V001T01A021https://doi.org/10.1115/ICONE25-66673
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Topics: Cables , Inspection , Insulation , Nuclear power stations , Irradiation (Radiation exposure) , Chain , Dielectric losses , Electrical properties , Elongation , Fourier transforms
Root Cause Analysis of a Leak Off Tube of the Primary Loop in a CANDU 6 Unit
Liang Zhao, Kunjie Luo
ICONE 2017; V001T01A022https://doi.org/10.1115/ICONE25-66710
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Topics: Leakage , Root cause analysis , Fracture (Materials) , Fluids , Corrosion , Design , Fatigue cracks , Heat , Maintenance , Stress corrosion cracking
The Research of XLPE Cable Comprehensive Performance Evaluation Based on VLF Technology
Gao Xuan, Zheng Zheng, Zhang Yizhou, Wang Liang, Yun Hao, Tao Ge, Ma Huiming, Xue Kun
ICONE 2017; V001T01A023https://doi.org/10.1115/ICONE25-66720
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Topics: Cables , Performance evaluation , Dielectric losses , Insulation , Nuclear power stations
Operation Feasibility Study of Adding Fourth Main Feedwater Pump to CAP1000
Ke Xiao
ICONE 2017; V001T01A024https://doi.org/10.1115/ICONE25-66738
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Topics: Feedwater , Pumps , Stress , Design , Transients (Dynamics) , Turbines , Economics , Probability , Risk , Transient analysis
Stress Improvement by Laser Peening in the Air
Souichi Ueno, Akihiro Tsuji, Hiroyuki Adachi, Tatsuya Naito
ICONE 2017; V001T01A025https://doi.org/10.1115/ICONE25-66754
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Topics: Laser hardening , Stress , Lasers , Water , Irradiation (Radiation exposure) , Nozzles , Alloys , Density , Laser beams , Abrasion
Transition From Time–Based Preventive Maintenance to Condition–Based Maintenance
Liu Xiaonian, Wang Liangsheng
ICONE 2017; V001T01A026https://doi.org/10.1115/ICONE25-66757
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Topics: Maintenance , Failure , Failure mechanisms , Nuclear industry , Public utilities , Pulse width modulation , Reliability
The Research on Ultrasonic Testing Technology for Bottom Part of Reactor Pressure Vessel
Ge Liang, Xu Xuguang, Cai Jiafan, Cheng Zhaoyu
ICONE 2017; V001T01A027https://doi.org/10.1115/ICONE25-66984
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Topics: Reactor vessels , Ultrasonic testing , Probes , Inspection , Alloys , Nuclear power stations , Accuracy and precision , Circuits , Corrosion , Design
In-Service Inspection Technology Research on CANOPY Seal Weld of Control Rod Drive Mechanism in PWR
Zhou Lifeng, Cheng Zhaoyu, Cai Jiafan, Tang Yi
ICONE 2017; V001T01A028https://doi.org/10.1115/ICONE25-66999
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Topics: In-service inspection , Pressurized water reactors , Fracture (Materials) , Inspection , ASME Standards , Failure , Probes , Signals , Testing , Water
The Chemistry Experience Summary During the Engineering Commissioning Period of Fujian Ningde Nuclear Power Plant
Heng Liu, Yue Chen, Fuping Li, Hui Liu, Shunlong Yang
ICONE 2017; V001T01A029https://doi.org/10.1115/ICONE25-67040
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Topics: Chemistry , Nuclear power stations , Construction , Instrumentation , Maintenance , Water chemistry , Water pollution , Aluminum , Design , Fuels
Prestressed Time-Limited Aging Analyses of Concrete Containment Structure
Dahua Cai, Yonghuan Wang, Jiangtao Zhang, Lin Yang, Hua Rong, Jiwa Li, Zhiming Wu
ICONE 2017; V001T01A030https://doi.org/10.1115/ICONE25-67107
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Topics: Concretes , Containment , Tendons , Computer simulation , Finite element model , Pressure , Prestressed concrete , Safety
Machine GTAW Ambient Temperature Temper Bead Technique for Ni-Based Weld Overlay Repairs of Nuclear Components: Assessment of Hydrogen Cracking by Implant Test
Marcello Consonni, Claire Verdon
ICONE 2017; V001T01A031https://doi.org/10.1115/ICONE25-67160
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Topics: Gas tungsten arc welding , Hydrogen embrittlement , Machinery , Maintenance , Overlays (Materials engineering) , Temperature , Heating , Welding , Cracking (Materials) , Fracture (Process)
RtCM Technology Approach and Application Practice
Yang Lifei, Chen Yu
ICONE 2017; V001T01A032https://doi.org/10.1115/ICONE25-67214
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Topics: Flow (Dynamics) , Maintenance , Reliability
Hybrid Nuclear Thermal Energy Storage System Revenue With Design and Market Uncertainty
W. Neal Mann, Erich A. Schneider
ICONE 2017; V001T01A033https://doi.org/10.1115/ICONE25-67335
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Topics: Design , Thermal energy storage , Uncertainty , Natural gas , Nuclear power stations , Storage
Determination of Fracture Toughness From Small Punch Test Using Inverse Finite Element Method for In-Service Equipment
Kaishu Guan, Tong Xu, Linling Guo, Mingxue Fu, Huadong Zhu
ICONE 2017; V001T01A034https://doi.org/10.1115/ICONE25-67406
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Topics: Finite element methods , Fracture toughness , Displacement , Stress , Pressure equipment , Mechanical properties , Databases , Mechanical testing , Artificial neural networks , Computer simulation
Development of Shearing Device for Reducing the Storage Volume of the Spent Fuel Associated Assemblies in Nuclear Power Plants
Zhang Bin, Qiao Su-kai, Hao Qing-jun, Huang Hong-zhi, Ding Ming, Liu Pan
ICONE 2017; V001T01A035https://doi.org/10.1115/ICONE25-67447
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Topics: Die cutting , Nuclear power stations , Shearing (Deformation) , Spent nuclear fuels , Storage , Spent fuel storage , Shear (Mechanics) , Bearings , Blades , Extruding
Vibration Alarm Analysis and Treatment of Main Coolant Pump in Nuclear Power Plant
Zhen Li, Pengcheng Du, Gujian Ma
ICONE 2017; V001T01A036https://doi.org/10.1115/ICONE25-67481
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Topics: Coolants , Nuclear power stations , Pumps , Vibration , Water , Flow (Dynamics) , Vibration analysis , Design , Engines , Motors
Daya Bay Nuclear Power Plant Main Generator Inner Stator Replacement
Li Yujian, Guo Zhenwu, Lu Min
ICONE 2017; V001T01A037https://doi.org/10.1115/ICONE25-67482
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Topics: Generators , Nuclear power stations , Stators , Nuclear power , Stainless steel , Water
Research on Fatigue Monitoring System Development for Nuclear Power Plant
Zhao Chuanli, Chen Yinqiang, Xu Feng, Ji Yuanyuan, Wang Jiangguo
ICONE 2017; V001T01A038https://doi.org/10.1115/ICONE25-67483
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Topics: Fatigue , Monitoring systems , Nuclear power stations , Fatigue damage , Stress , Pipelines , Accidents , Fatigue failure , Pressure , Transients (Dynamics)
Ultra Large Diameter Glass Reinforced Plastic Pipe Outsourcing of Concrete Structure for Conventional Island Construction Management Practices
Wang Mengwu, Xia Hongjun, Yang Yong, Zhang Xiaofei, Gao Zhaopu
ICONE 2017; V001T01A039https://doi.org/10.1115/ICONE25-67490
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Topics: Concretes , Construction , Glass reinforced plastics , Pipes , Design , Nuclear construction , Nuclear power , Quality control , Safety
A New Reliability Assessment Method for Complex Nuclear Power Equipment Based on Goal Oriented Methodology
Yi Xiao-jian, Lu Ming-chao, Mu Hui-na, Shi Jian, Hou Peng
ICONE 2017; V001T01A040https://doi.org/10.1115/ICONE25-67546
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Topics: Nuclear power , Reliability , Failure , Control systems , Event history analysis , Monte Carlo methods , Nuclear power stations , Systems analysis
Method for Measuring Temperature of Inner Wall Surface of Pipeline in Nuclear Power Plant
Ling Jun, Wang Hai-jun, Liu Lang, Chen Tong, Liu Hong-tao, He Da-yu
ICONE 2017; V001T01A041https://doi.org/10.1115/ICONE25-67553
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Topics: Nuclear power stations , Pipelines , Temperature measurement , Temperature , Fatigue , Fluctuations (Physics) , Pipes , Energy conservation , Fluids , Heat
Innovative Methodology of Ranking Cooling Towers Based on Structural Safety Margin
Nhu-Cuong Tran, Charles Toulemonde, François Beaudouin, Christian Meuwisse, Nicolas Schmitt, Abderrazzaq El-Yazidi, Alexis Courtois, Yves Genest, Sylvain Moriceau
ICONE 2017; V001T01A042https://doi.org/10.1115/ICONE25-67596
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Topics: Cooling towers , Safety , Risk , Shells , Columns (Structural) , Failure , Maintenance , Corrosion , Damage , Deformation
A New Reliability Optimization Allocation Method for Nuclear Power Systems Based on Goal Oriented Methodology
Yi Xiao-jian, Xie Yong-cheng, Shi Jian, Mu Hui-na, Hou Peng
ICONE 2017; V001T01A043https://doi.org/10.1115/ICONE25-67777
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Topics: Nuclear power , Optimization , Reliability , Design , Nuclear power stations , Systems analysis
Corrosion Cause Analysis of Electric Feedwater Pump Motor Shaft in Nuclear Power Plants and Relevant Corrective Actions
Che Yinhui, Guan Jianjun, Zu Shuai, Chen Qiang
ICONE 2017; V001T01A044https://doi.org/10.1115/ICONE25-67780
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Topics: Corrective actions , Corrosion , Engines , Feedwater , Motors , Nuclear power stations , Pumps , Bearings , Reliability , Shells
Incident Investigation and Root Cause Analysis Method and Technology Review
Guan Jianjun, Che Yinhui, Ma Lei
ICONE 2017; V001T01A045https://doi.org/10.1115/ICONE25-67834
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Topics: Root cause analysis , Nuclear power , Nuclear power stations
Root Cause Analysis of Pipeline Rupture in the Condensate Extraction System of Nuclear Power Plant
Chen Qiang, Han Ning, Chen Weihan, Che Yinhui
ICONE 2017; V001T01A046https://doi.org/10.1115/ICONE25-67860
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Topics: Condensed matter , Nuclear power stations , Pipelines , Root cause analysis , Rupture , Failure mechanisms , Pressurized water reactors , Circuits , Corrective actions , Corrosion
The Root Cause Analysis of the Bolt Fracture in the Nuclear Power Plant Essential Service Water System
Li Nan, Lao Yi, Che Yinhui
ICONE 2017; V001T01A047https://doi.org/10.1115/ICONE25-67885
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Topics: Fracture (Materials) , Fracture (Process) , Nuclear power stations , Root cause analysis , Water , Corrosion , Pumps , Heat treating (Metalworking) , Spectroscopy , Stainless steel

I&C, Digital Controls, and Influence of Human Factors

Based on Human Behavior Process of Human Error Defensive Management Research for NPP
Shen Yang, Geng Bo, Li Dan
ICONE 2017; V001T04A001https://doi.org/10.1115/ICONE25-66007
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Topics: Errors , Nuclear power stations , Human factors , Quality control charts , Root cause analysis , Buses , Corrective actions , Databases , Defense industry , Innovation
Safety and Operational I&C: Interface Management
Antonio Ciriello, Deeksha Gupta
ICONE 2017; V001T04A002https://doi.org/10.1115/ICONE25-66037
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Topics: Safety , Instrumentation , Engineering standards , Flow (Dynamics) , Separation (Technology)
Design and Development of FES’s HMI for HPR1000 NPP
Caike Zhang, Peibang Liu, Hanjun Gao, Chenglong Xie, Ming Qu
ICONE 2017; V001T04A003https://doi.org/10.1115/ICONE25-66054
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Topics: Design , Nuclear power stations , Computer software , Simulation , Errors , Machinery , Cycles , Feedback , Computers , Data acquisition
Research on Simulation Technology for Supervisory Control Software in NPP DCS
Hanjun Gao, Ming Qu, CaiKe Zhang, Kui Xu, PeiBang Liu, Chenglong Xie
ICONE 2017; V001T04A004https://doi.org/10.1115/ICONE25-66064
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Topics: Computer software , Nuclear power stations , Simulation , Reliability , Engineers , Innovation , Licensing , Process control
The Development and Application of the Engineering and Design Analyzer of CAP1400 Nuclear Power Plant
He Yuanlei, Zhang Qijiang, Li Xiaoyan
ICONE 2017; V001T04A005https://doi.org/10.1115/ICONE25-66087
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Topics: Design , Nuclear power stations , Transients (Dynamics) , Control systems , Stress , Human factors , Industrial research , Nuclear engineering
Improvement of the Reactor Control System in AP1000
Dai Chunhui, Wei Xinyu, Tao Mo, Wu Jun, Zhao Zhenxing, Liu Zhouyang, Liu Yong
ICONE 2017; V001T04A006https://doi.org/10.1115/ICONE25-66133
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Topics: Control systems , Signals , Temperature , Coolants , Errors , Nuclear power , Pressurized water reactors , Boron , Construction , Control equipment
The Safety Constraints and Evaluation of I&C Algorithm Configuration Based on SCADE Platform
Hua Liu, Xiao-Hua Yang, Zhao-hui Liu, Jie Liu, Shi-yu Yan, Meng Li, Zhi Chen
ICONE 2017; V001T04A007https://doi.org/10.1115/ICONE25-66327
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Topics: Algorithms , Safety , Design , Reliability , Computer software , Control systems , Errors , Instrumentation , Signals , Testing
Functional Information of System Components Influenced by Operators’ Actions on Emergency Operating Procedure
Tulis Jojok Suryono, Akio Gofuku
ICONE 2017; V001T04A008https://doi.org/10.1115/ICONE25-66354
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Topics: Emergencies , Accidents , Boilers , Computers , Flow (Dynamics) , Modeling , Pressurized water reactors , Rupture
Technical Architecture About Safety I&C System Software V&V in Nuclear Power Plant
Shengchao Wang, Pengfei Gu, Wangping Ye, Weihua Chen
ICONE 2017; V001T04A009https://doi.org/10.1115/ICONE25-66369
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Topics: Computer software , Nuclear power stations , Safety , Failure , Instrumentation , Quality control , China , Computers , Control systems , Regulations
A Study About Software-Implemented Fault Injection Strategy for Digital RPS in Nuclear Power Plant
Wang Xi, Pengfei Gu, Tao Bai, Wei Liu, Weihua Chen
ICONE 2017; V001T04A010https://doi.org/10.1115/ICONE25-66373
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Topics: Computer software , Nuclear power stations , Reactor protection systems , Evaluation methods , Fault tolerance , Reliability , Safety , Design , Errors , Instrumentation
The Reliability Model for the FPGA-Based Instrument and Control System Using Colored Petri Net
Zhanguo Ma, Hidekazu Yoshikawa, Ming Yang
ICONE 2017; V001T04A011https://doi.org/10.1115/ICONE25-66440
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Topics: Control systems , Instrumentation , Reliability , Failure , Hardware , Complex systems , Computer software , Delays , Design , Fault tolerance
Research on Cooling Methods of Voice Coil Motor
Pu Zhou, Yue Zhang, Xuechang Dai, Qiang Wang, Weiliang Wu
ICONE 2017; V001T04A012https://doi.org/10.1115/ICONE25-66475
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Topics: Cooling , Engines , Motors , Temperature , Energy dissipation , Flow (Dynamics) , Heat , Mechanical properties , Servomechanisms , Weight (Mass)
A Quantitative Approach for Reliability Evaluation of Safety I&C Systems in Nuclear Power Plants
Liu Dongxu, Xu Dongling, Zhang Shuhui, Hu Xiaoying
ICONE 2017; V001T04A013https://doi.org/10.1115/ICONE25-66483
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Topics: Nuclear power stations , Reliability , Safety , Probability , Modeling , Algebra , Databases , Hardware , Risk-based design
The Research of the Model-Free Adaptive Control Method of Once-Through Steam Generator in Nuclear Power
Mo Tao, Zhiwu Ke, Xianling Li, Ruotong Qu, Zhenxing Zhao, Jun Wu, Yong Li
ICONE 2017; V001T04A014https://doi.org/10.1115/ICONE25-66489
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Topics: Adaptive control , Boilers , Nuclear power , Steam , Valves , Pressure , Circuits , Control equipment , Pumps , Security
Intelligent Fault Diagnosis Method Based on Operating Parameters in Nuclear Power Plant
Zhiwu Ke, Xu Hu, Dawei Teng, Mo Tao
ICONE 2017; V001T04A015https://doi.org/10.1115/ICONE25-66494
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Topics: Fault diagnosis , Nuclear power stations , Feedwater , Safety , Artificial neural networks , Support vector machines , Valves , Algorithms , Delays , Errors
Component and Integration Test of an FPGA-Based PWR Protection Sub-System Using UVM
Xuanxuan Shui, Yichun Wu, Junyi Zhou, Yuanfeng Cai
ICONE 2017; V001T04A016https://doi.org/10.1115/ICONE25-66526
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Topics: Pressurized water reactors , Simulation , Safety , Gates (Closures) , Nuclear industry , Nuclear power stations , Teams , Coolants , Engineering standards , Flow (Dynamics)
Conceptual Formation of Advanced HIS Design Method for Digital I&C + HMIT
Hidekazu Yoshikawa, Zhanguo Ma, Amjad Nawaz, Ming Yang
ICONE 2017; V001T04A017https://doi.org/10.1115/ICONE25-66530
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Topics: Accidents , Computer simulation , Coolants , Defense industry , Design , Design methodology , Nuclear power stations , Nuclear reactor accidents , Pressurized water reactors , Risk monitoring
Measurement Method of Equivalent Water Level for Nuclear Steam Generator Based on Data Fusion
Xianling Li, Zhiwu Ke, Mo Tao
ICONE 2017; V001T04A018https://doi.org/10.1115/ICONE25-66539
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Topics: Data fusion , Nuclear reactor steam generators , Water , Control equipment , Sensors , Boilers , Feedwater , Filters , Flow (Dynamics) , Low-pass filters
Dynamic Model Identification of Once-Through Steam Generation System Based on PEM Method
He Jinliang, Tao Mo, Wang Wei, Song Feifei
ICONE 2017; V001T04A019https://doi.org/10.1115/ICONE25-66555
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Topics: Dynamic models , Proton exchange membranes , Steam , Heat transfer , Feedwater , Modeling , Pressure , Water , Flow (Dynamics) , Nuclear power stations
Co-Verification Method of NPP Protection System Based on FPGA Platform and SCADE Model
Ke Chen, Leilei Xu, Zhende Zhou
ICONE 2017; V001T04A020https://doi.org/10.1115/ICONE25-66606
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Topics: Nuclear power stations , Safety , Hardware , Maintainability , Reliability , Security
Control System Design for NuScale
Kai Wang, Peiwei Sun
ICONE 2017; V001T04A021https://doi.org/10.1115/ICONE25-66629
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Topics: Control systems , Design , Coolants , Boilers , Feedwater , Pressure , Temperature , Dynamic models , Flow (Dynamics) , Steam
Architecture and Suppression Design of Alarm System in HTR-PM
Chao Guo, Qianqian Jia, Xiaojin Huang, Shuqiao Zhou
ICONE 2017; V001T04A022https://doi.org/10.1115/ICONE25-66681
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Topics: Design , Nuclear power stations , Accidents , Tiles , Control rooms , Safety , Steam turbines , China , Construction , Human factors
Small Pressurized Water Reactor (SPWR) Simulation Platform Development for its Design Verification
Peiwei Sun, Huanhuan Zhao, Jianmin Zhang
ICONE 2017; V001T04A023https://doi.org/10.1115/ICONE25-66730
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Topics: Design , Pressurized water reactors , Simulation , Software development , Control systems , Boilers , Matlab , Transients (Dynamics) , Accidents , Control equipment
Linear Active Disturbance Rejection Control for Fast Nuclear Reactor
Liu Feng-ming, Shen Cong, Zhang Hua-xia, Zhou Shi-liang, Liu Yu-yan, Li Yu-rong, Wang Xiaoruo, Mohanned Khalid
ICONE 2017; V001T04A024https://doi.org/10.1115/ICONE25-66768
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Topics: Nuclear reactors , Control equipment , Neutrons , Control systems , Dynamics (Mechanics) , Fast neutron reactors , Robustness , Simulation results , State estimation , Thermal hydraulics
The Study on Hydraulic Oil Property Influences on Motion Performances of the Main Steam Isolation Valve and its Driving Device
Dalei Pan, Hongbo Kuang, Shenjie Gu, Hua Zhong, Guangyue Guo
ICONE 2017; V001T04A025https://doi.org/10.1115/ICONE25-66781
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Topics: Steam , Valves , Simulation , Cycles , Design
Operating Reliability Assessment of FPGA-Based NPP I&C Systems: Approach, Technique and Implementation
Eugene Babeshko, Ievgenii Bakhmach, Vyacheslav Kharchenko, Eugene Ruchkov, Oleksandr Siora
ICONE 2017; V001T04A026https://doi.org/10.1115/ICONE25-66862
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Topics: Nuclear power stations , Reliability , Design , Integrated circuits , Blanks , Control systems , Event history analysis , Failure mechanisms , Gates (Closures) , Instrumentation
Design Verification for Control Logic in Nuclear Power Plant
Hui Li, Guangxin Zhang
ICONE 2017; V001T04A027https://doi.org/10.1115/ICONE25-66878
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Topics: Design , Nuclear power stations , Control systems , Electronic systems , HVAC equipment , Testing
Development of TMSR-SF1 Protection System Prototype
Jie Hou, Ye Liu, Bingying Li, Yongbo Wei, Guoqing Huang, Guimin Liu
ICONE 2017; V001T04A028https://doi.org/10.1115/ICONE25-66982
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Topics: Engineering prototypes , Design , Reactor protection systems , Conceptual design , Emergencies , Fuels , Hardware , Molten salt reactors , Redundancy (Engineering) , Reliability
Markov/CCMT Dynamic Reliability Analysis of the Main and Startup Feedwater Control System in Nuclear Power Plant
Wentao Li, Danying Gu, Henan Zhang
ICONE 2017; V001T04A029https://doi.org/10.1115/ICONE25-67041
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Topics: Control systems , Event history analysis , Feedwater , Nuclear power stations , Failure , Computer software , Probability , Uncertainty , Failure mechanisms , Reliability
A Development of Human-System Interaction in Digital NPPs
Jiachuan Lu, Longtao Liao, Bo Feng, Yifen Chen, Junwei Hao, Kai Ye, Jianxiang Zheng
ICONE 2017; V001T04A030https://doi.org/10.1115/ICONE25-67212
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Topics: Nuclear power stations , Design , Control systems , Instrumentation , China , Complex systems , Computer software , Computers , Data acquisition , Nuclear power
Digital Human-Machine Interface Design for Marine Nuclear Power Plant Based on Task-Oriented
Zhi-tong Liu, Shao-ming Wang, Long-fei Zhang, Guang Yang, Meng Lv, Hong-jian Zhang
ICONE 2017; V001T04A031https://doi.org/10.1115/ICONE25-67244
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Topics: Design , Machinery , Nuclear power stations , Control rooms , Safety , Control panels , Accidents , China , Electronic systems , Hardware
The Research on Effects of the Medium Blocking on Motion Performances of Main Steam and Feed Water Isolation Valves With its Driving Device
Dalei Pan, Hua Zhong, Shenjie Gu, Guangyue Guo, Hongbo Kuang
ICONE 2017; V001T04A032https://doi.org/10.1115/ICONE25-67258
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Topics: Feedwater , Steam , Valves , Nuclear power stations , Simulation models , Simulation results
Confluent Modeling of Heterogeneous Safety and Operational I&C Systems
Mithil Parekh, Yuan Gao, Mariana Jockenhoevel-Barttfeld, Karl Waedt
ICONE 2017; V001T04A033https://doi.org/10.1115/ICONE25-67333
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Topics: Modeling , Safety , Nuclear power stations , Security , Computer software , Control rooms , Data collection , Electronic systems , Engineering disciplines , Engineering instruments
The Construction of Abnormal Event Recognition Expert System for HTR NPP
Xiaona Xu, Xiaojin Huang
ICONE 2017; V001T04A034https://doi.org/10.1115/ICONE25-67334
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Topics: Construction , Expert systems , Nuclear power stations , Computer programming , Simulation
The Measurement of Parameters of Zero Power Experiments Based on MNSR
Hong Jingyan, Peng Dan, Wu Xiaobo, Lu Jin, Li Yiguo
ICONE 2017; V001T04A035https://doi.org/10.1115/ICONE25-67386
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Topics: Engineering prototypes , Neutron sources , Stress , Uranium
Design of a Human Error Analysis Experiment for Soft Control in MCR of Nuclear Power Plant Using Eye Tracking Technology
Wang Jun-bo, Yang Kun-ze, Zhang Yu-xin, Hidekazu Yoshikawa
ICONE 2017; V001T04A036https://doi.org/10.1115/ICONE25-67435
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Topics: Design , Error analysis , Nuclear power stations , Errors , Control rooms , Machinery , Probabilistic safety assessment , Statistics
Hierarchical Structure Modeling for the Analysis of I&C System Software Reliability
Zou Bo-wen, Yang Ming, Yan Zhen-yu, Dai Xin-yu, Yoshikawa Hidekazu
ICONE 2017; V001T04A037https://doi.org/10.1115/ICONE25-67439
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Topics: Computer software , Modeling , Reliability , Cycles , Design
Guided Waves As an Online Monitoring Technology for Long Term Operation in NPPs: New Experimental Results on a Steam Discharge Pipe
Francesco Bertoncini, Mauro Cappelli, Francesco Cordella, Marco Raugi
ICONE 2017; V001T04A038https://doi.org/10.1115/ICONE25-67444
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Topics: Nuclear power stations , Pipes , Steam , Waves , Probes , Sensors , Testing , Circuits , Echoes , Engineering simulation
Analysis of Impact on Core Level Monitoring System due to Judgement of Main Coolant Pump Status During LOCA
Jiang Xialan, Liu Yi, Liu Taili, Zhang Xuan
ICONE 2017; V001T04A039https://doi.org/10.1115/ICONE25-67459
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Topics: Coolants , Monitoring systems , Pumps , Control systems , Errors , Water , Accidents , Cooling , Leakage , Nuclear power stations
Sensitivity Analysis for Human Errors of a Chemical and Volume Control System at Nuclear Power Plant by Soft Control
Zhang Yuxin, Yang Kunze
ICONE 2017; V001T04A040https://doi.org/10.1115/ICONE25-67460
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Topics: Control systems , Errors , Nuclear power stations , Sensitivity analysis , Control rooms , Countermeasures , Failure mechanisms , Pressurized water reactors , Probability , Task analysis
Modeling DCS of Nuclear Power Plant With Extended GO-FLOW Methodology
Lu Hongxing, Yang Ming, Dai Xinyu, Li Wei, Yoshikawa Hidekazu
ICONE 2017; V001T04A041https://doi.org/10.1115/ICONE25-67540
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Topics: Flow (Dynamics) , Modeling , Nuclear power stations , Control systems , Hardware , Reliability , Engineering drawings , Event history analysis
Hierarchical Modeling of GO-FLOW Models for Online Risk Monitoring of Nuclear Power Plants
Dai Xinyu, Yang Ming, Zou Bowen, Lu Hongxing
ICONE 2017; V001T04A042https://doi.org/10.1115/ICONE25-67543
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Topics: Flow (Dynamics) , Modeling , Nuclear power stations , Risk monitoring , Reliability , Failure , Risk assessment , Event history analysis , Accidents , Algorithms
Design of a Platform for Safety Justification of Safety-Critical Software
Guo Jia, Yang Ming
ICONE 2017; V001T04A043https://doi.org/10.1115/ICONE25-67548
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Topics: Computer software , Design , Safety , Reliability , Computer-aided engineering , Accidents , Cycles , Drag (Fluid dynamics) , Graphical user interfaces , Nuclear power stations
A Study of Power Decrease Strategy on CPR1000 Full Scope Simulator
Zhenhua Zhang, Bo Zhang, Qingsong Wang, Chengzhi Wang, Dan Xing
ICONE 2017; V001T04A044https://doi.org/10.1115/ICONE25-67670
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Topics: Boron , Condensed matter , Equilibrium (Physics) , Feedwater , Flow control , Maintenance , Nuclear power stations , Safety , Water
Discussion on STR and PFD Analysis of I&C System
Zhang Chao, Su Yanqin, Li Wei, Chen Wanqing, Chen Qiang
ICONE 2017; V001T04A045https://doi.org/10.1115/ICONE25-67773
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Topics: Design , Event history analysis , Instrumentation , Nuclear power stations , Probability , Reliability , Safety , Semiconductor industry
Task Analysis in Designing the Control Room of Nuclear Power Plant and Safety Reviewing
Yan Feng, Liang Li, Jingbin Liu, Ning Qiao, Yinhui Guo
ICONE 2017; V001T04A046https://doi.org/10.1115/ICONE25-67824
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Topics: Control rooms , Design , Nuclear power stations , Safety , Task analysis , Decision making , Hazards , Maintenance
A Study on Nuclear Plant Safety I&C System Verification and Validation Relevant Regulatory Standards
Ning Qiao, Yan Feng, Jingbin Liu, Yan Lu, Zhongqiu Wang
ICONE 2017; V001T04A047https://doi.org/10.1115/ICONE25-67864
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Topics: Nuclear power stations , Safety , Computer software , Cycles , Control systems , Instrumentation , Testing
Development of Instrumentation and Control Systems for UK ABWR
Itsuki Naito, Taisuke Koyamada, Keisuke Yamamoto, Kingo Igarashi, Hideo Harada, Hirotsugu Suzuki
ICONE 2017; V001T04A048https://doi.org/10.1115/ICONE25-67866
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Topics: Control systems , Instrumentation , Safety , Boiling water reactors , Design , Regulations , Accidents , Computers , Construction , Gates (Closures)
Research on Special Analysis of Verification and Validation in Nuclear Power Instrument and Control System
Jingbin Liu, Yan Feng, Ning Qiao, Yunbo Zhang, Zhongqiu Wang
ICONE 2017; V001T04A049https://doi.org/10.1115/ICONE25-67871
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Topics: Control systems , Instrumentation , Nuclear power , Computer software , China , Cycles , Hazard analysis , Risk analysis , Security analysis , Software verification
Design of the Communication Independence for ACPR1000 Nuclear Power Plant Digital Safety I&C System
Sun Na, Shi Gui-lian, Xie Yi-qin, Li Gang, Jiang Guo-jin
ICONE 2017; V001T04A050https://doi.org/10.1115/ICONE25-67880
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Topics: Design , Nuclear power stations , Safety , Reactor protection systems , Regulations , Failure , Reliability
Application Research of Safety Control and Information Device Based on FirmSys Platform in ACPR1000 Nuclear Power Plant
Li-Ling Zhu, Bin Wu, Gang Li, Yi-Qin Xie, Yong-Bin Sun
ICONE 2017; V001T04A051https://doi.org/10.1115/ICONE25-67882
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Topics: Nuclear power stations , Safety , Computers , Innovation , Instrumentation
The Application of Task Analysis and Task Support Verification in HPR1000 Main Control Room Human System Interface Design
Deng Shiguang, Ming Xiaoyang, Gao Yuan
ICONE 2017; V001T04A052https://doi.org/10.1115/ICONE25-67891
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Topics: Control rooms , Design , Task analysis , Accidents , Human factors , Nuclear power stations , Integrated systems , Safety , Brain , Engineers
Optimization Design Based on Human Factors V&V of Human System Interfaces in Nuclear Power Plant
Ming Xiaoyang, Deng Shiguang, Jiang Xingwei
ICONE 2017; V001T04A053https://doi.org/10.1115/ICONE25-67896
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Topics: Design , Human factors , Nuclear power stations , Optimization , Control rooms , Ergonomics , Integrated systems , Intellectual property , Nuclear power , Plant personnel
FPGA-Based Technologies Improving the Efficiency of Point to Point Communications in Safety-Related DCSs
Le Li, Zhaoyang Ma, Fei Zhou
ICONE 2017; V001T04A054https://doi.org/10.1115/ICONE25-67903
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Topics: Safety , Nuclear reactors , China , Control systems , Gates (Closures) , Intellectual property , Nuclear power stations , Reactor protection systems , Reliability
Study of AP1000 Protection System Based on FirmSys
Zheng Wei-zhi, Sun Hong-tao, Liu Jing-bo, Ma Ji-qiang, Liu Yuan
ICONE 2017; V001T04A055https://doi.org/10.1115/ICONE25-67987
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Topics: Design , Emergencies , Optimization , Reliability , Safety , System architecture
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