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Proceedings Papers

PID Parameter Tuning Method for Steam Generator Level Control Based on Ant Colony Algorithm

Yulong Wang, Xinyu Wei, PeiWei Sun
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A021, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136009
https://doi.org/10.1115/ICONE31-136009
View Paper titled, PID Parameter Tuning Method for Steam Generator Level Control Based on Ant Colony Algorithm
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Topics: Algorithms, Artificial neural networks, Boilers, Control systems, Differential equations, Transfer functions, Calibration, Neural network models, Nuclear power stations, Optimization
Proceedings Papers

Surrogate Modeling Advancements in Nuclear Fuel Engineering: Bridging the Gap Between Accuracy and Efficiency

Salvatore Angelo Cancemi, Michela Angelucci, Rosa Lo Frano, Sandro Paci
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A070, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135798
https://doi.org/10.1115/ICONE31-135798
View Paper titled, Surrogate Modeling Advancements in Nuclear Fuel Engineering: Bridging the Gap Between Accuracy and Efficiency
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Topics: Metamodeling, Nuclear fuels, Artificial neural networks, Cladding systems (Building), Simulation, Temperature, Algorithms, Safety, Computer simulation, Design
Proceedings Papers

Reliability Analysis of Active Reactor Pit Flooding Function of EHR DFT System of a NPP Using an Enhanced Component-Connection Method

Dingqing Guo, Shaoxuan Wang, Daochuan Ge, Lili Tong, Xuewu Cao
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A020, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91669
https://doi.org/10.1115/ICONE29-91669
View Paper titled, Reliability Analysis of Active Reactor Pit Flooding Function of EHR DFT System of a NPP Using an Enhanced Component-Connection Method
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Topics: Event history analysis, Floods, Nuclear power stations, Reliability, Safety, Failure, Probability, Design, Redundancy (Engineering), Trains
Proceedings Papers

The Research on the Risk Monitor With Specific Plant Configuration at Shutdown Mode for VVER Nuclear Reactor

Fangyu Dong, Jinyan Du, Chao Ma, Wei Deng, Qingqing Xu, Rui Zhang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A019, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91663
https://doi.org/10.1115/ICONE29-91663
View Paper titled, The Research on the Risk Monitor With Specific Plant Configuration at Shutdown Mode for VVER Nuclear Reactor
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Topics: Heat, Nuclear reactors, Probabilistic safety assessment, Risk, Risk monitoring, Risk management, Design, Nuclear power stations, Decision making, Maintenance
Proceedings Papers

Nuclear Power Plant Design Optimization Based on Risk-Informed Method

Wenjing Li, Yu Liu, Gaopeng Wang, Xinli Yu
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A005, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89268
https://doi.org/10.1115/ICONE29-89268
View Paper titled, Nuclear Power Plant Design Optimization Based on Risk-Informed Method
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Topics: Nuclear design, Optimization, Risk, Design, Nuclear power stations, Accidents, Cavities, Vessels, China, Damage
Proceedings Papers

Post-hoc Interpretability Based Parameter Selection for Data Oriented Nuclear Reactor Accident Diagnosis System

Chengyuan Li, Meifu Li, Zhifang Qiu
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A014, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92505
https://doi.org/10.1115/ICONE29-92505
View Paper titled, Post-hoc Interpretability Based Parameter Selection for Data Oriented Nuclear Reactor Accident Diagnosis System
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Topics: Artificial neural networks, Errors, Nuclear power stations, Nuclear reactor accidents, Probability, Reliability, Thermal hydraulics, Trains, Transients (Dynamics), Uncertainty
Proceedings Papers

Single Point Vulnerabilities Management Strategy of Qinshan Nuclear Power Plant

Wang Hanlin
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A005, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16491
https://doi.org/10.1115/ICONE2020-16491
View Paper titled, Single Point Vulnerabilities Management Strategy of Qinshan Nuclear Power Plant
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Topics: Maintenance, Nuclear power stations, Reliability, Risk management, Stress, Trains
Proceedings Papers

Pump Bearing Fault Detection Based on EMD and SVM

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

Research on the Neutron Multiplicity Pulse Trains Computer Simulation

Sufen Li, Quanhu Zhang, Yonggang Huo, Man Zhou
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A038, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82262
https://doi.org/10.1115/ICONE26-82262
View Paper titled, Research on the Neutron Multiplicity Pulse Trains Computer Simulation
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Topics: Computer simulation, Neutrons, Trains, Simulation, Nondestructive evaluation
Proceedings Papers

Development of Instrumentation and Control Systems for UK ABWR

Itsuki Naito, Taisuke Koyamada, Keisuke Yamamoto, Kingo Igarashi, Hideo Harada, Hirotsugu Suzuki
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, V001T04A048, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67866
https://doi.org/10.1115/ICONE25-67866
View Paper titled, Development of Instrumentation and Control Systems for UK ABWR
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Topics: Control systems, Instrumentation, Safety, Boiling water reactors, Design, Regulations, Accidents, Computers, Construction, Gates (Closures)
Proceedings Papers

The Reliability Model for the FPGA-Based Instrument and Control System Using Colored Petri Net

Zhanguo Ma, Hidekazu Yoshikawa, Ming Yang
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, V001T04A011, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66440
https://doi.org/10.1115/ICONE25-66440
View Paper titled, The Reliability Model for the FPGA-Based Instrument and Control System Using Colored Petri Net
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Topics: Control systems, Instrumentation, Reliability, Failure, Hardware, Complex systems, Computer software, Delays, Design, Fault tolerance
Proceedings Papers

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

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

Accident at Fukushima Dai-Ichi Nuclear Power Plant: Lessons Learned for the Czech Republic

Ladislav Vesely, Vaclav Dostal
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A065, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31160
https://doi.org/10.1115/ICONE22-31160
View Paper titled, Accident at Fukushima Dai-Ichi Nuclear Power Plant: Lessons Learned for the Czech Republic
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Topics: Accidents, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Errors, Cooling, Damage, Fuels, Condensers (steam plant), Coolants, Delays
Proceedings Papers

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

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

Study of Station Blackout Accident Process in Taishan Nuclear Power Plant

Yu Li, Huiyong Zhang, Yehong Liao, Jiming Lin, Dekui Zhan
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T01A031, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16214
https://doi.org/10.1115/ICONE21-16214
View Paper titled, Study of Station Blackout Accident Process in Taishan Nuclear Power Plant
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Topics: Accidents, Nuclear power stations, Pumps, Diesel generators, Emergencies, Boilers, Control rooms, Coolants, Design, Feedwater
Proceedings Papers

The Discussion of Nuclear Power Plant’s Cooling Chain Design for Freezing Site

Jian Hu, Xulun Jiang, Ting Yang, Wei Xiao, Zhengguang Wang
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T01A009, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15136
https://doi.org/10.1115/ICONE21-15136
View Paper titled, The Discussion of Nuclear Power Plant’s Cooling Chain Design for Freezing Site
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Topics: Chain, Cooling, Design, Freezing, Nuclear power, Nuclear power stations, China, Heat, Safety, Stress
Proceedings Papers

Fire PRA Insights

James R. Chapman
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T06A049, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16832
https://doi.org/10.1115/ICONE21-16832
View Paper titled, Fire PRA Insights
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Topics: Fire, Failure, Defense industry, Design, Accidents, Coolants, Diesel generators, Emergencies, Fire risk, Licensing
Proceedings Papers

Analysis for Low Pressure Cooling Injection System Suction Hydrodynamics for a Boiling Water Reactor

Basar Ozar, Rodney Harvill, Christopher E. Henry, Deborah A. Norton
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 825-832, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55255
https://doi.org/10.1115/ICONE20-POWER2012-55255
View Paper titled, Analysis for Low Pressure Cooling Injection System Suction Hydrodynamics for a Boiling Water Reactor
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Topics: Boiling water reactors, Cooling, Hydrodynamics, Pressure, Suction, Steam, Pipes, Valves, Transients (Dynamics), Temperature
Proceedings Papers

Application of Computer-Based Operating Procedure to the US-APWR Human-System Interface

Satoshi Hanada, Koji Ito, Kenji Mashio, Masashi Hirahatake, Robert E. Hall
Proc. ASME. ICONE20-POWER2012, Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes, 669-675, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55080
https://doi.org/10.1115/ICONE20-POWER2012-55080
View Paper titled, Application of Computer-Based Operating Procedure to the US-APWR Human-System Interface
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Topics: Computers, Design, Safety, Ergonomics, Navigation, Control systems, Data collection, Instrumentation, Licensing, Pressurized water reactors
Proceedings Papers

A CO 2 Compression and Dehydration System Utilizing Absorption Chillers and Heat Recovery Concepts

David Hasler, David Stopek, Roger Smith, John Klumpyan
Proc. ASME. ICONE20-POWER2012, Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes, 809-813, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54576
https://doi.org/10.1115/ICONE20-POWER2012-54576
View Paper titled, A CO 2 Compression and Dehydration System Utilizing Absorption Chillers and Heat Recovery Concepts
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Topics: Absorption, Carbon dioxide, Compression, Heat recovery, Water, Carbon capture and storage, Trains, Waste heat, Carbon steel, Cooling