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Proceedings Papers

TRISO Particle Behavior Analyses of an HTR-10 Type Reactor Employing the OTTO Operation Scheme

Junxiao Zhang, Songyang Liu, Junhao Xie, Tian Zhang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A053, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136107
https://doi.org/10.1115/ICONE31-136107
View Paper titled, TRISO Particle Behavior Analyses of an HTR-10 Type Reactor Employing the OTTO Operation Scheme
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Topics: Fuels, High temperature, Particulate matter, Nuclear fission, Temperature, Very high temperature reactors, Diffusion (Physics), Failure, Flow (Dynamics), Safety
Proceedings Papers

Influence of Nuclear Power Plant Interface Complexity on Operator Performance: A Modeling Study

Pu Chen, Jiejuan Tong
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134997
https://doi.org/10.1115/ICONE31-134997
View Paper titled, Influence of Nuclear Power Plant Interface Complexity on Operator Performance: A Modeling Study
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Topics: Control rooms, Machinery, Modeling, Network models, Nuclear power stations, Optimization, Stress, Accidents, Design, Engineering simulation
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

Dynamic Event Tree Analysis of SGTR Accidents Considering HRA

Nianchun Qu, He Wang
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A030, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136092
https://doi.org/10.1115/ICONE31-136092
View Paper titled, Dynamic Event Tree Analysis of SGTR Accidents Considering HRA
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Topics: Accidents, Boilers, Errors, Human reliability analysis, Probability, Rupture, Safety, Modeling, Event history analysis, Human factors
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 Heat Transfer Calculation of Ellipsoidal Melt Pool

Peng Liu, Tao Zhou, Haolei Zhang, Xiaofang Liu
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T11A003, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134536
https://doi.org/10.1115/ICONE31-134536
View Paper titled, Research on Heat Transfer Calculation of Ellipsoidal Melt Pool
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Topics: Failure, Heat flux, Heat transfer, Pressure vessels, Metals, Wall thickness, Accidents, Heat, Pressurized water reactors, Ablation (Vaporization technology)
Proceedings Papers

Typical Sequence Analysis of SLOCA Accidents in a Third Generation Nuclear Power Plant Based on RISMC Method

Churan Feng, Jingxiang Zhan, Lin Yan, Yiming Wang, Jinghua Zhou
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T12A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135096
https://doi.org/10.1115/ICONE31-135096
View Paper titled, Typical Sequence Analysis of SLOCA Accidents in a Third Generation Nuclear Power Plant Based on RISMC Method
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Topics: Accidents, Nuclear power stations, Safety, Failure, Damage, Design, Feedwater, Probability, Risk, Uncertainty
Proceedings Papers

Human Reliability Analysis for a Passive NPP and Application in Plant Operating Procedure Optimization

Yongping Qiu, Xiao Tan
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T12A012, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135379
https://doi.org/10.1115/ICONE31-135379
View Paper titled, Human Reliability Analysis for a Passive NPP and Application in Plant Operating Procedure Optimization
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Topics: Errors, Human reliability analysis, Nuclear power stations, Optimization, Probability, Risk
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

Functional Reliability Investigation on Capacity of Reactor Core Natural Circulation Cooling in XAPR Under MLOCA

Baosheng Wang, Tengyue Ma, Lihong Bao, Zhenhui Ma, Pan Hu, Da Li, Chunlei Su, Lixin Chen, Xiuhuan Tang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A061, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93526
https://doi.org/10.1115/ICONE29-93526
View Paper titled, Functional Reliability Investigation on Capacity of Reactor Core Natural Circulation Cooling in XAPR Under MLOCA
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Topics: Cooling, Probability, Reliability
Proceedings Papers

A Location Algorithm for Orphan Radioactive Source

Qianxi Xiao, Jiejin Cai
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A115, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93592
https://doi.org/10.1115/ICONE29-93592
View Paper titled, A Location Algorithm for Orphan Radioactive Source
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Topics: Algorithms, Robots, Probability, Radiation (Physics), Gaussian distribution, Mobile robots, Path planning, Safety, Simulation experiments, Switches
Proceedings Papers

Development of Adaptive Sampling Software Based on Relap5

Haoyin Chen, He Wang, Mohamedelmogtabh Omer Elfadni Suliman, Xinyue Wang, Qiang Zhao
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A094, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92454
https://doi.org/10.1115/ICONE29-92454
View Paper titled, Development of Adaptive Sampling Software Based on Relap5
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Topics: Computer software, Nuclear power stations, Accidents, Failure, Probability, Safety, Dynamic response, Industrial research, Probabilistic safety assessment
Proceedings Papers

Quantitative Probabilistic Safety Analysis of Locking Mechanism of Nuclear Power Control System Products

Zhirui Jiang
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A019, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92012
https://doi.org/10.1115/ICONE29-92012
View Paper titled, Quantitative Probabilistic Safety Analysis of Locking Mechanism of Nuclear Power Control System Products
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Topics: Control systems, Nuclear power, Probabilistic safety assessment, Simulation, Algorithms, Failure, Failure mechanisms, Probability, Reliability, Deformation
Proceedings Papers

Event Tree Analysis for Material Relocation on Core Catcher in a Sodium-Cooled Fast Reactor

Hidemasa Yamano, Shigenobu Kubo, Taro Kan, Akihiro Shibata, Edouard Hourcade, Jean François Dirat
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A011, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91505
https://doi.org/10.1115/ICONE29-91505
View Paper titled, Event Tree Analysis for Material Relocation on Core Catcher in a Sodium-Cooled Fast Reactor
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Topics: Accidents, Sodium fast reactors, Design, Coolants, Fuels, Probability, Sodium, Vessels
Proceedings Papers

Application of First-Order Method to Estimate Structural Integrity in a Probabilistic Form of Component Subjected to Thermal Transient for Optimization of Design Parameter

Satoshi Okajima, Takero Mori, Norihiro Kikuchi, Masaaki Tanaka, Masashi Miyazaki
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A001, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-88933
https://doi.org/10.1115/ICONE29-88933
View Paper titled, Application of First-Order Method to Estimate Structural Integrity in a Probabilistic Form of Component Subjected to Thermal Transient for Optimization of Design Parameter
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Topics: Design, Failure, Optimization, Probability, Transients (Dynamics)
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

Numerical Model for Subcooled Flow Boiling Heat Transfer and Critical Heat Flux Based on Probability of Bubble Interaction

Shichang Dong, Shengjie Gong
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A058, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93755
https://doi.org/10.1115/ICONE29-93755
View Paper titled, Numerical Model for Subcooled Flow Boiling Heat Transfer and Critical Heat Flux Based on Probability of Bubble Interaction
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Topics: Boiling, Bubbles, Computer simulation, Critical heat flux, Flow (Dynamics), Heat transfer, Probability, Subcooling
Proceedings Papers

Fire Probability Safety Analysis for a Compact Small Modular Reactor

Yanzhu Chen
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A017, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91381
https://doi.org/10.1115/ICONE29-91381
View Paper titled, Fire Probability Safety Analysis for a Compact Small Modular Reactor
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Topics: Fire, Probability, Safety, Small modular reactors, Design, Damage, Nuclear power stations
Proceedings Papers

On Line Monitoring of Sensor Failure in Nuclear Power Plant Based on Sequential Probability Ratio Test

Fangxiaozhi Yu, Xintong Ma, Zhuang Miao, Min Zhang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A005, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89215
https://doi.org/10.1115/ICONE29-89215
View Paper titled, On Line Monitoring of Sensor Failure in Nuclear Power Plant Based on Sequential Probability Ratio Test
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Topics: Failure, Nuclear power stations, Probability, Sensors
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