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Proceedings Papers

Safety Evaluation and Optimization of Nuclear Power Plant Under Adaptive Sampling

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Linfeng Li, Zhen Zhang, Anqi Xu, Ting Wen, Xiaomeng Dong, Ming Yang, Linxian Chen, Yong Liu
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T12A019, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136531
https://doi.org/10.1115/ICONE31-136531
View Paper titled, Safety Evaluation and Optimization of Nuclear Power Plant Under Adaptive Sampling
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Topics: Nuclear power stations, Optimization, Probabilistic safety assessment, Risk, Safety, Support vector machines
Proceedings Papers

Fault Diagnosis Based on KPCA and RUSboost for Nuclear Power Plants

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Yiqing Wang, Peiwei Sun
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A082, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92163
https://doi.org/10.1115/ICONE29-92163
View Paper titled, Fault Diagnosis Based on KPCA and RUSboost for Nuclear Power Plants
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Topics: Fault diagnosis, Nuclear power stations, Algorithms, Sensors, Nonlinear systems, Nuclear reactors, Pressurized water reactors, Process monitoring, Support vector machines
Proceedings Papers

Research on GIL Fault Diagnosis and Location Method Based on Partial Discharge and Vibration Monitoring

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Sen Liu
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A020, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92174
https://doi.org/10.1115/ICONE29-92174
View Paper titled, Research on GIL Fault Diagnosis and Location Method Based on Partial Discharge and Vibration Monitoring
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Topics: Fault diagnosis, Vibration, Signals, Metals, Transmission lines, Eigenvalues, Sensors, Simulation, Economics , Fault location (Engineering)
Proceedings Papers

Machine Learned Metamodeling of a Computationally Intensive Accident Simulation Code

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Landon Conner, Clarence L. Worrell, James P. Spring, Jun Liao
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A035, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-66619
https://doi.org/10.1115/ICONE28-66619
View Paper titled, Machine Learned Metamodeling of a Computationally Intensive Accident Simulation Code
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Topics: Accidents, Machinery, Metamodeling, Simulation, Artificial neural networks, Machine learning, Manufacturing, Nuclear industry, Optimization, Safety
Proceedings Papers

Anomaly Detection of Electric Gate Valve Based on Multi-Kernel Support Vector Machine

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Jing Luo, Hang Wang, Minjun Peng
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A064, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64766
https://doi.org/10.1115/ICONE28-64766
View Paper titled, Anomaly Detection of Electric Gate Valve Based on Multi-Kernel Support Vector Machine
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Topics: Gates (Closures), Support vector machines, Valves
Proceedings Papers

Vertical-Downward Two-Phase Flow Regime Identification by Probabilistic Neural Network (PNN) and Nonlinear Support Vector Machine (SVM)

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Wenyi Zhong, Shouxu Qiao, Sijia Hao, Xupeng Li, Sichao Tan
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A069, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65467
https://doi.org/10.1115/ICONE28-65467
View Paper titled, Vertical-Downward Two-Phase Flow Regime Identification by Probabilistic Neural Network (PNN) and Nonlinear Support Vector Machine (SVM)
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Topics: Artificial neural networks, Flow (Dynamics), Support vector machines, Two-phase flow
Proceedings Papers

A Brief Review of Computational Intelligence Techniques for Critical Heat Flux Prediction

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B. T. Jiang, Y. N. Liu
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A050, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82325
https://doi.org/10.1115/ICONE26-82325
View Paper titled, A Brief Review of Computational Intelligence Techniques for Critical Heat Flux Prediction
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Topics: Critical heat flux, Design, Nuclear reactors, Artificial neural networks, Fuel rods, Nuclear power stations, Safety, Temperature, Water, Economics
Proceedings Papers

Pump Bearing Fault Detection Based on EMD and SVM

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Yi Feng, Xianling Li, Zhiwu Ke, Zhaoxu Chen, Mo Tao
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T01A008, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81584
https://doi.org/10.1115/ICONE26-81584
View Paper titled, Pump Bearing Fault Detection Based on EMD and SVM
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Topics: Bearings, Flaw detection, Pumps, Support vector machines, Signals, Coolants, Failure, Flow (Dynamics), Fluids, Heat transfer
Proceedings Papers

Two-Phase Flow Regime Identification Using Fluctuating Force Signals Under Machine Learning Techniques

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Yuta Saito, Shuhei Torisaki, Shuichiro Miwa
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A019, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81288
https://doi.org/10.1115/ICONE26-81288
View Paper titled, Two-Phase Flow Regime Identification Using Fluctuating Force Signals Under Machine Learning Techniques
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Topics: Machine learning, Signals, Two-phase flow, Flow (Dynamics), Artificial neural networks, Support vector machines, Algorithms, Databases, Design, Heat
Proceedings Papers

Passive System Reliability Analysis Based on Improved Support Vector Machine

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Hao Ding, Qi Cai, Yongfa Zhang, Lizhi Jiang
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A037, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67621
https://doi.org/10.1115/ICONE25-67621
View Paper titled, Passive System Reliability Analysis Based on Improved Support Vector Machine
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Topics: Event history analysis, Support vector machines, Failure, Approximation, Artificial neural networks, Failure mechanisms, Nuclear reactors, Polynomials, Probability, Reliability
Proceedings Papers

Intelligent Fault Diagnosis Method Based on Operating Parameters in Nuclear Power Plant

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Zhiwu Ke, Xu Hu, Dawei Teng, Mo Tao
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T04A015, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66494
https://doi.org/10.1115/ICONE25-66494
View Paper titled, Intelligent Fault Diagnosis Method Based on Operating Parameters in Nuclear Power Plant
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Topics: Fault diagnosis, Nuclear power stations, Feedwater, Safety, Artificial neural networks, Support vector machines, Valves, Algorithms, Delays, Errors
Proceedings Papers

Application of Fuzzy Weighted Support Vector Regression to Accidents Condition Monitoring of Nuclear Power Plant

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B. T. Jiang, J. W. Hines, F. Y. Zhao
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T07A014, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60983
https://doi.org/10.1115/ICONE24-60983
View Paper titled, Application of Fuzzy Weighted Support Vector Regression to Accidents Condition Monitoring of Nuclear Power Plant
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Topics: Accidents, Condition monitoring, Nuclear power stations, Support vector machines, Artificial neural networks, Fuels, Temperature, Transients (Dynamics), Boron, Computers
Proceedings Papers

Fault Diagnosis of Feedwater Pump in Nuclear Power Plants Using Parameter-Optimized Support Vector Machine

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Rui Yu, Xianling Li, Mo Tao, Zhiwu Ke
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T03A013, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60334
https://doi.org/10.1115/ICONE24-60334
View Paper titled, Fault Diagnosis of Feedwater Pump in Nuclear Power Plants Using Parameter-Optimized Support Vector Machine
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Topics: Fault diagnosis, Feedwater, Nuclear power stations, Pumps, Support vector machines, Circuits, Condition monitoring, Signals, Vibration
Proceedings Papers

Uncertainty Assessment of Component Degradation Model Based on Support Vector Regression

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Chunzhen Yang, Jingquan Liu, Yuyun Zeng, Muhammad Saeed
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T01A012, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-61114
https://doi.org/10.1115/ICONE24-61114
View Paper titled, Uncertainty Assessment of Component Degradation Model Based on Support Vector Regression
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Topics: Support vector machines, Uncertainty, Modeling, Nuclear power stations, Algorithms, Carbon steel, In-service inspection, Maintenance, Pipes, Sampling methods
Proceedings Papers

Genetic Algorithm Optimization of a Dynamic Uncertain Causality Graph (DUCG) for Fault Diagnosis in Nuclear Power Plants

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Yue Zhao, Francesco Di Maio, Enrico Zio, Qin Zhang, Chunling Dong
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T14A010, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60199
https://doi.org/10.1115/ICONE24-60199
View Paper titled, Genetic Algorithm Optimization of a Dynamic Uncertain Causality Graph (DUCG) for Fault Diagnosis in Nuclear Power Plants
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Topics: Fault diagnosis, Genetic algorithms, Nuclear power stations, Optimization, Construction, Artificial neural networks, China, Nuclear power, Support vector machines
Proceedings Papers

An Alternative Approach to Prediction of Critical Heat Flux: Projection Support Vector Regression

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Botao Jiang, Fuyu Zhao
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A030, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30747
https://doi.org/10.1115/ICONE22-30747
View Paper titled, An Alternative Approach to Prediction of Critical Heat Flux: Projection Support Vector Regression
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Topics: Critical heat flux, Support vector machines, Artificial neural networks, Boilers, Boiling, Cooling systems, Design, Fuels, Trains
Proceedings Papers

On the Use of Support Vector Regression Technique for the Analysis of Rod Ejection Accidents

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Botao Jiang, Yang Liu, Fuyu Zhao
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 99-102, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54266
https://doi.org/10.1115/ICONE20-POWER2012-54266
View Paper titled, On the Use of Support Vector Regression Technique for the Analysis of Rod Ejection Accidents
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Topics: Accidents, Support vector machines, Artificial neural networks, Pressurized water reactors, Trains, Computers, Design, Machine learning, Nuclear engineering, Power stations