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Proceedings Papers

A Brief Introduction to Several Important Design Optimizations of Passive Nuclear Power Plants in China

Baisong Ma, Zhengqiang Miao, Yuanhua Ma
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A008, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134488
https://doi.org/10.1115/ICONE31-134488
View Paper titled, A Brief Introduction to Several Important Design Optimizations of Passive Nuclear Power Plants in China
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Topics: China, Control rooms, Design, Gates (Closures), Nuclear power, Nuclear power stations
Proceedings Papers

Multiple Knowledge Exploration Functions for Advanced Reactor Design and Safety in Knowledge Management System Implemented in the ARKADIA

Akiyuki Seki, Yuki Kondo, Ryuta Hashidate, Masanori Yoshikawa, Kenji Yokoyama, Shigeru Takaya, Yasuhiro Enuma, Taira Hazama, Takashi Wakai, Tai Asayama
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A012, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131784
https://doi.org/10.1115/ICONE31-131784
View Paper titled, Multiple Knowledge Exploration Functions for Advanced Reactor Design and Safety in Knowledge Management System Implemented in the ARKADIA
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Topics: Design, Knowledge management, Safety, Computer-aided design, Information retrieval, Sodium fast reactors, Artificial intelligence, Carbon, Computer simulation, Engineering drawings
Proceedings Papers

AWCC Simulations Based on Monte Carlo Code RMC

Yuanhao Gou, Zhaoyuan Liu, Conglong Jia, Dacai Zhang, Hao Luo, Kan Wang
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A004, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132066
https://doi.org/10.1115/ICONE31-132066
View Paper titled, AWCC Simulations Based on Monte Carlo Code RMC
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Topics: Design, Emissions, Engineering simulation, Gates (Closures), Instrumentation, Neutrons, Nuclear fission, Simulation, Uranium
Proceedings Papers

Quantifying Software Safety in Nuclear Power Plants: A Framework for Requirements Phase Assessment

Boyuan Li, Duo Li, Jianghai Li, Chao Guo, Huasheng Xiong, Shuqiao Zhou, Xiaojin Huang
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T12A013, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135382
https://doi.org/10.1115/ICONE31-135382
View Paper titled, Quantifying Software Safety in Nuclear Power Plants: A Framework for Requirements Phase Assessment
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Topics: Computer software, Gates (Closures), Hazards, Nuclear power stations, Safety
Proceedings Papers

Seismic Analysis of Fuel Transfer Tube Gate Valve

Su Ziwei, Zhang Xin
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A010, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89869
https://doi.org/10.1115/ICONE29-89869
View Paper titled, Seismic Analysis of Fuel Transfer Tube Gate Valve
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Topics: Design, Fuels, Gates (Closures), Seismic analysis, Valves
Proceedings Papers

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
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A051, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92733
https://doi.org/10.1115/ICONE29-92733
View Paper titled, 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
Proceedings Papers

PSA Analysis of Switch Port Disabled on DCS Layer 1

Yang Luo, Deyi Liu, Shengjia Zou, Yong Cao
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T13A008, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64597
https://doi.org/10.1115/ICONE28-64597
View Paper titled, PSA Analysis of Switch Port Disabled on DCS Layer 1
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Topics: Switches, Failure, Control systems, Gates (Closures), Nuclear power stations, Radioactive substances, Reactor protection systems, Risk, Safety
Proceedings Papers

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

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

Experimental Validation of CFD Models Capturing the Thermal-Hydraulics in Liquid Metal Cooled Reactor Plena

Brendan Ward, Thomas Hopkins, Hitesh Bindra
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A037, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16661
https://doi.org/10.1115/ICONE2020-16661
View Paper titled, Experimental Validation of CFD Models Capturing the Thermal-Hydraulics in Liquid Metal Cooled Reactor Plena
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Topics: Computational fluid dynamics, Liquid metals, Thermal hydraulics, Computer simulation, Fluids, Gates (Closures), Safety, Simulation, Acoustics, Backscattering
Proceedings Papers

Condition Fault Tree: An Extension of Traditional Fault Tree to Handle Uncertainty

Zhenxu Zhou, Qin Zhang
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A014, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81243
https://doi.org/10.1115/ICONE26-81243
View Paper titled, Condition Fault Tree: An Extension of Traditional Fault Tree to Handle Uncertainty
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Topics: Uncertainty, Gates (Closures), Computational methods, Fourier transform spectroscopy, Probability, Reliability
Proceedings Papers

Study on Protection Against Large Commercial Aircraft Crash of HPR1000

Xueshuang Zhang, Li Fan, Lijian Cai, Qianwen Liu
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A002, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81397
https://doi.org/10.1115/ICONE26-81397
View Paper titled, Study on Protection Against Large Commercial Aircraft Crash of HPR1000
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Topics: Aircraft, Safety, Design, Shells, Acceptance criteria, Damage, Fire, Hazards, Spent nuclear fuels, Concretes
Proceedings Papers

FMEDA and FIT-Based Safety Assessment of NPP I&C Systems Considering Expert Uncertainty

Alexander Yasko, Eugene Babeshko, Vyacheslav Kharchenko
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, V001T04A014, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82048
https://doi.org/10.1115/ICONE26-82048
View Paper titled, FMEDA and FIT-Based Safety Assessment of NPP I&C Systems Considering Expert Uncertainty
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Topics: Nuclear power stations, Safety, Uncertainty, Computer software, Reliability, Failure mechanisms, Testing, Aerospace industry, Errors, Failure data
Proceedings Papers

Simulation of Behaviors of a One-Third Scale Containment Model Test

Guopeng Ren, Rong Pan, Feng Sun
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A113, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67779
https://doi.org/10.1115/ICONE25-67779
View Paper titled, Simulation of Behaviors of a One-Third Scale Containment Model Test
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Topics: Containment, Simulation, Tendons, Concretes, Finite element model, Pressure, Deformation, Nuclear power stations, Design, Safety
Proceedings Papers

Numerical Simulation of Flow Instability in Vortex Diodes

Junrong Wang, Qi Xiao, Hanbing Ke, Xu Hu, Shaodan Li, Zhiguo Wei
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A015, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66512
https://doi.org/10.1115/ICONE25-66512
View Paper titled, Numerical Simulation of Flow Instability in Vortex Diodes
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Topics: Computer simulation, Flow instability, Vortices, Flow (Dynamics), Engineering simulation, Simulation, Pressure, Transients (Dynamics), Circuits, Fluids
Proceedings Papers

Numerical and Experimental Investigation on Influence Factors of the Leakage Rate for a Large-Size Pressure Gate With Rubber O-Ring Sealing Structure

Huang Hao, Huang Xiaoming, Xu Guoliang, Fang Lin, Shi Chunyu, Sun Jiawei, Lv Xiangkui
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A040, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67735
https://doi.org/10.1115/ICONE25-67735
View Paper titled, Numerical and Experimental Investigation on Influence Factors of the Leakage Rate for a Large-Size Pressure Gate With Rubber O-Ring Sealing Structure
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Topics: Gates (Closures), Leakage, Pressure, Rubber, Sealing (Process), Seals, Finite element methods, Accidents, Design, Mechanical behavior
Proceedings Papers

Component and Integration Test of an FPGA-Based PWR Protection Sub-System Using UVM

Xuanxuan Shui, Yichun Wu, Junyi Zhou, Yuanfeng Cai
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, V001T04A016, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66526
https://doi.org/10.1115/ICONE25-66526
View Paper titled, Component and Integration Test of an FPGA-Based PWR Protection Sub-System Using UVM
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Topics: Pressurized water reactors, Simulation, Safety, Gates (Closures), Nuclear industry, Nuclear power stations, Teams, Coolants, Engineering standards, Flow (Dynamics)
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

FPGA-Based Technologies Improving the Efficiency of Point to Point Communications in Safety-Related DCSs

Le Li, Zhaoyang Ma, Fei Zhou
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, V001T04A054, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67903
https://doi.org/10.1115/ICONE25-67903
View Paper titled, FPGA-Based Technologies Improving the Efficiency of Point to Point Communications in Safety-Related DCSs
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Topics: Safety, Nuclear reactors, China, Control systems, Gates (Closures), Intellectual property, Nuclear power stations, Reactor protection systems, Reliability
Proceedings Papers

Single Event Effect Characteristics Analysis of Typical Circuit Elements in Spacecraft Power Systems

Zhao Wen, He Chaohui, Chen Wei, Guo Xiaoqiang, Cong Peitian, Zhang Fengqi, Chen Rongmei
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A035, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67728
https://doi.org/10.1115/ICONE25-67728
View Paper titled, Single Event Effect Characteristics Analysis of Typical Circuit Elements in Spacecraft Power Systems
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Topics: Circuits, Power systems (Machinery), Space vehicles, Transients (Dynamics), Gates (Closures), Modeling, Simulation, Capacitance, Chain, Computer simulation
Proceedings Papers

Operating Reliability Assessment of FPGA-Based NPP I&C Systems: Approach, Technique and Implementation

Eugene Babeshko, Ievgenii Bakhmach, Vyacheslav Kharchenko, Eugene Ruchkov, Oleksandr Siora
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, V001T04A026, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66862
https://doi.org/10.1115/ICONE25-66862
View Paper titled, Operating Reliability Assessment of FPGA-Based NPP I&C Systems: Approach, Technique and Implementation
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Topics: Nuclear power stations, Reliability, Design, Integrated circuits, Blanks, Control systems, Event history analysis, Failure mechanisms, Gates (Closures), Instrumentation