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Proceedings Papers

Isotopic Measurement of HTR-10 Irradiated Fuels Based on Anti-Compton Gamma Spectroscopic Method

Weijian Zhang, Haiyan Xiao, Jingang Liang, Ruihan Li, Liguo Zhang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A009, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132758
https://doi.org/10.1115/ICONE31-132758
View Paper titled, Isotopic Measurement of HTR-10 Irradiated Fuels Based on Anti-Compton Gamma Spectroscopic Method
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Topics: Fuel management, Fuels, Spent nuclear fuels, Very high temperature reactors, Calibration, China, Isotopes, Measurement uncertainty, Nuclear fission, Optimization
Proceedings Papers

Research on Operating Reliability of Multi-Modular High Temperature Gas-Cooled Reactor Nuclear Power Plant Based on Equipment State

Chao Guo, Jianghai Li, Qianqian Jia, Ronghong Qu, Xiaojin Huang
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A016, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135387
https://doi.org/10.1115/ICONE31-135387
View Paper titled, Research on Operating Reliability of Multi-Modular High Temperature Gas-Cooled Reactor Nuclear Power Plant Based on Equipment State
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Topics: Markov processes, Nuclear power stations, Reliability, Very high temperature reactors
Proceedings Papers

Optimal Sensor Placement in Nuclear Power Steam Water System Based on Signed Directed Graph

Tianyang Xing, Chunyang Zeng, Bin Han, Mudi Jiang, Yunze He, Shenghui Liu, Junling Huang, Xiaoliang Zhu
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A019, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135960
https://doi.org/10.1115/ICONE31-135960
View Paper titled, Optimal Sensor Placement in Nuclear Power Steam Water System Based on Signed Directed Graph
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Topics: Nuclear power, Nuclear power stations, Pareto optimization, Sensor placement, Steam, Water, Sensors, Flaw detection, Reliability, Computer simulation
Proceedings Papers

Study on Parameters Design Methodology for Rolling and Pitching Test of Control Rod Hydraulic Drive System

Yanlin Li, Benke Qin, Hanliang Bo
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A008, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-130895
https://doi.org/10.1115/ICONE31-130895
View Paper titled, Study on Parameters Design Methodology for Rolling and Pitching Test of Control Rod Hydraulic Drive System
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Topics: Design methodology, Hydraulic drive systems, Rods, Stress, Accidents, Design, Fluids, Heating, Marine engineering, Naval architecture
Proceedings Papers

Evaluation of Three-Dimensional Initial Dynamics of the Decompression Wave at LB LOCA in the Advanced Supercritical Reactor ECC-SMART

Vladislav Filonov, Yaroslav Dubyk, Oleksandr Kovalenko, Yuliia Filonova, Dmitriy Fedorov
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A068, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136271
https://doi.org/10.1115/ICONE31-136271
View Paper titled, Evaluation of Three-Dimensional Initial Dynamics of the Decompression Wave at LB LOCA in the Advanced Supercritical Reactor ECC-SMART
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Topics: Computational fluid dynamics, Dynamics (Mechanics), Loss of coolant accidents, Pressure, Waves, Modeling, Approximation, Design, Dynamic analysis, Outflow
Proceedings Papers

Preliminary Core Design Analysis of Core Criticality and Heat Transfer of the All-Solid State Micro-Reactor

Takeshi Koike, Koji Asano, Mizuki Yamada, Satoru Kamohara, Tadakatsu Yodo, Nozomu Murakami
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A037, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135017
https://doi.org/10.1115/ICONE31-135017
View Paper titled, Preliminary Core Design Analysis of Core Criticality and Heat Transfer of the All-Solid State Micro-Reactor
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Topics: Design, Heat transfer, Neutrons, Safety, Reliability, Carbon, Fuels, Graphite, Heat, Light water reactors
Proceedings Papers

The Influence of Seasonal Variation on AP1000 Reliability Under LOOP Accident

Guanyu Liu, Mingzhu Zhang, Bingbing Wang, Yu Yu, Niu Fenglei
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A024, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135100
https://doi.org/10.1115/ICONE31-135100
View Paper titled, The Influence of Seasonal Variation on AP1000 Reliability Under LOOP Accident
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Topics: Accidents, Probabilistic safety assessment, Reliability, Safety, Nuclear power stations, Failure, Power stations, Risk, Containment, Cooling systems
Proceedings Papers

Research on the Applicability of the IWF Model to Coupled Heat Transfer Between Intra- and Inter-Assembly in LFR

Di Wu, Minyang Gui, Jie Cheng, Jianjun Wang
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A007, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131238
https://doi.org/10.1115/ICONE31-131238
View Paper titled, Research on the Applicability of the IWF Model to Coupled Heat Transfer Between Intra- and Inter-Assembly in LFR
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Topics: Heat transfer, Manufacturing, Numerical analysis, Safety, Flow (Dynamics), Fluids, Accuracy and precision, Boundary-value problems, Design, Energy generation
Proceedings Papers

Experimental Studies on Two-Layer Stratified Molten Pool Heat Transfer With Water and 1-Octanol

Fengyang Quan, Jie Pei, Wei Li, Yidan Yuan
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T11A014, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136323
https://doi.org/10.1115/ICONE31-136323
View Paper titled, Experimental Studies on Two-Layer Stratified Molten Pool Heat Transfer With Water and 1-Octanol
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Topics: Accidents, Heat transfer, Water, High temperature, Low temperature, Rayleigh number, China, Heat, Nuclear engineering, Reliability
Proceedings Papers

Research and First Application of 4D Radiation Dose Calculation in China

Zhaoxing Liu, Ri Zhao, Runcheng Liang, Jing Zhang, Xin Liu, Liye Liu
Proc. ASME. ICONE31, Volume 8: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V008T09A027, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136133
https://doi.org/10.1115/ICONE31-136133
View Paper titled, Research and First Application of 4D Radiation Dose Calculation in China
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Topics: China, Phantoms, Radiation (Physics), Algorithms, Deformation, Nuclear power stations, Computational methods, Maintenance, Nuclear industry, Reliability
Proceedings Papers

Effect of Different Temperature Probability Curve Fitting Methods on the System Reliability for PCCS in AP1000

Yu Yu, Guanyu Liu, Wanxin Feng, Houjian Zhao, Xuefeng Lyu
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T12A015, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135769
https://doi.org/10.1115/ICONE31-135769
View Paper titled, Effect of Different Temperature Probability Curve Fitting Methods on the System Reliability for PCCS in AP1000
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Topics: Curve fitting, Failure, Probability, Reliability, Temperature
Proceedings Papers

Verification and Analysis of Thermal-Hydraulics System Program for a Power Plant Model

Lixin Du, Peng Zhou, Hao Zhang, Yanhua Yang
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A007, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134794
https://doi.org/10.1115/ICONE31-134794
View Paper titled, Verification and Analysis of Thermal-Hydraulics System Program for a Power Plant Model
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Topics: Accidents, Circuits, Computer software, Design, Fluids, Heat transfer, Hydraulic drive systems, Nuclear power, Nuclear power stations, Power stations
Proceedings Papers

Methodology for Acquiring Reliability Data in Novel Nuclear Energy Systems Using a Non-Homogeneous Poisson Process

Zefeng Li, Pu Chen, Tao Liu
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A046, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134981
https://doi.org/10.1115/ICONE31-134981
View Paper titled, Methodology for Acquiring Reliability Data in Novel Nuclear Energy Systems Using a Non-Homogeneous Poisson Process
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Topics: Nuclear power, Reliability, Maintenance, Failure, Modeling, Bayesian network, Chain, Nuclear power plant maintenance, Nuclear power stations, Safety
Proceedings Papers

Reliability Quantification of Passive Containment Cooling System Through Response Surface Methodology

Chen Shikang, Chen Ronghua, Qiu Suizheng
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A039, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134863
https://doi.org/10.1115/ICONE31-134863
View Paper titled, Reliability Quantification of Passive Containment Cooling System Through Response Surface Methodology
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Topics: Containment, Cooling systems, Reliability, Response surface methodology
Proceedings Papers

Investigation of Compressible Flow in Natural Circulation Loops With a Non-Boussinesq Algorithm

Jinsong Zhang, Yongyong Wu, Nan Gui, Zhen Zhang, Xingtuan Yang, Jiyuan Tu, Shengyao Jiang
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A029, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134557
https://doi.org/10.1115/ICONE31-134557
View Paper titled, Investigation of Compressible Flow in Natural Circulation Loops With a Non-Boussinesq Algorithm
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Topics: Algorithms, Compressible flow, Lattice Boltzmann methods, Flow (Dynamics), Temperature, Density, Heat transfer, Nuclear reactors, Pressure, Reliability
Proceedings Papers

Development of Requirements for Demonstrating Structural Integrity of the Highest Reliability Components

Antony Hurst, Louis Chang, Mike Nielsen, Sam Holcroft
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A041, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136097
https://doi.org/10.1115/ICONE31-136097
View Paper titled, Development of Requirements for Demonstrating Structural Integrity of the Highest Reliability Components
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Topics: Design, Reliability, Safety, Failure, Nuclear power, Jets, Missiles, Pressure, Classification, Construction
Proceedings Papers

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

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

Thermal Performance Monitoring and Analysis of Nuclear Power Plant

Jianfei Hou, Xun Zhang, Heino Zimmermann, Zhaohui Xiang
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A011, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91886
https://doi.org/10.1115/ICONE29-91886
View Paper titled, Thermal Performance Monitoring and Analysis of Nuclear Power Plant
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Topics: Nuclear power stations, Instrumentation, Circuits, Computer software, Condensers (steam plant), Damage, Design, Feedwater, High pressure (Physics), Pressure
Proceedings Papers

Study on a High Reliability Power Supply Scheme for Distributed Control System of Nuclear Power Plant

Tian Hongpeng, Zhang Lin
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A014, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91950
https://doi.org/10.1115/ICONE29-91950
View Paper titled, Study on a High Reliability Power Supply Scheme for Distributed Control System of Nuclear Power Plant
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Topics: Control systems, Nuclear power stations, Reliability
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