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Proceedings Papers

Further Investigation of Neutron Noise Under the Condition of Fuel Failure Based on Frequency Domain Finite Element Method

Baoxin Yuan, Huiyi Lv, Herong Zeng, Jie Zheng, Zihan Chen, Huan Huang, Songbao Zhang, Dazhi Qian
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A005, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132052
https://doi.org/10.1115/ICONE31-132052
View Paper titled, Further Investigation of Neutron Noise Under the Condition of Fuel Failure Based on Frequency Domain Finite Element Method
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Topics: Damage, Failure, Finite element methods, Fuels, Neutrons, Noise (Sound)
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

Numerical Simulation Research on Irradiation-Thermal-Mechanical Behavior of CDM Fuel in Different Types of Reactors

Changbing Tang, Yuanming Li, Haoyu Liao
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A044, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135696
https://doi.org/10.1115/ICONE31-135696
View Paper titled, Numerical Simulation Research on Irradiation-Thermal-Mechanical Behavior of CDM Fuel in Different Types of Reactors
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Topics: Computer simulation, Failure, Fuels, Irradiation (Radiation exposure)
Proceedings Papers

A Nonlocal Meso-Scale Damage Model for Nuclear Graphite

Yan Ma, Yue Qian, Yuchen Hao, Musen Lin, Yue Li, Jinhua Wang, Haitao Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A029, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134775
https://doi.org/10.1115/ICONE31-134775
View Paper titled, A Nonlocal Meso-Scale Damage Model for Nuclear Graphite
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Topics: Damage, Failure, Graphite
Proceedings Papers

Three-Dimensional Temperature Field Monitoring of Heat Pipe Reactor Core

Shidi Wang, Youqi Zheng, Xiayu Wang, Lunhe Fan, Bowen Xiao
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A032, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134519
https://doi.org/10.1115/ICONE31-134519
View Paper titled, Three-Dimensional Temperature Field Monitoring of Heat Pipe Reactor Core
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Topics: Failure, Heat pipes, Temperature
Proceedings Papers

Application of Global Importance Measures in RISMC for Dynamic Risk Assessment

Liye Ma, He Wang, Longcong Wang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A065, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136084
https://doi.org/10.1115/ICONE31-136084
View Paper titled, Application of Global Importance Measures in RISMC for Dynamic Risk Assessment
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Topics: Risk, Risk assessment, Safety, Uncertainty, Nuclear power stations, Accidents, Alternating current (Electricity), Design, Engineering simulation, Failure
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

Analysis of Common Cause Events in Multiple Reactor Site Initiation Events

Wanxin Feng, Zecong Li, Yu Yu, Fenglei Niu
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A017, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134811
https://doi.org/10.1115/ICONE31-134811
View Paper titled, Analysis of Common Cause Events in Multiple Reactor Site Initiation Events
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Topics: Failure, Fault tree analysis, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Probabilistic safety assessment, Redundancy (Engineering), Risk
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

Thermal Hydraulics Simulation of a Typical Pressurized Water Reactor Coolant System Using CFD Method

Mingqian Zhang, Run Lin
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A015, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132452
https://doi.org/10.1115/ICONE31-132452
View Paper titled, Thermal Hydraulics Simulation of a Typical Pressurized Water Reactor Coolant System Using CFD Method
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Topics: Computational fluid dynamics, Coolants, Domes (Structural elements), Nuclear reactor coolants, Pressurized water reactors, Simulation, Swirling flow, Thermal hydraulics, Pumps, Reactor vessels
Proceedings Papers

Manufacturing Challenges for Hot Isostatic Pressing Large-Scale Vessels

John Sulley, David Stewart
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T10A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136240
https://doi.org/10.1115/ICONE31-136240
View Paper titled, Manufacturing Challenges for Hot Isostatic Pressing Large-Scale Vessels
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Topics: Hot pressing, Manufacturing, Vessels, Failure, Nuclear power stations, Alloy steel, Contamination, Cycles, Design, Fracture toughness
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

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

Comparative Analysis of Loss of Coolant Accidents for GEN-III PWRs Based on ACME and ATLAS Facilities

Yuhang Huang, Xueyan Zhang, Jun Yang
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A008, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134823
https://doi.org/10.1115/ICONE31-134823
View Paper titled, Comparative Analysis of Loss of Coolant Accidents for GEN-III PWRs Based on ACME and ATLAS Facilities
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Topics: Loss of coolant accidents, Pressurized water reactors, Safety, Accidents, Test facilities, Vessels, China, Cooling systems, Design, Failure
Proceedings Papers

Numerical Analysis of Three-Dimensional Flow Field Impact Under Strong Transient Conditions in Advanced Reactors

Jian Zhao, Jing Zhang, Yingwei Wu, Guanghui Su, Wenxi Tian, Suizheng Qiu
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A060, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135397
https://doi.org/10.1115/ICONE31-135397
View Paper titled, Numerical Analysis of Three-Dimensional Flow Field Impact Under Strong Transient Conditions in Advanced Reactors
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Topics: Accidents, Flow (Dynamics), Numerical analysis, Sodium fast reactors, Transients (Dynamics), Reactor vessels, Pressure, Sodium, Cavities, Vapors
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

Research on Natural Frequency Characteristics of Spiral Tube Bundles

Xiaoxi Li, Jiming Wen, Puzhen Gao, Yibo Yin
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A044, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134953
https://doi.org/10.1115/ICONE31-134953
View Paper titled, Research on Natural Frequency Characteristics of Spiral Tube Bundles
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Topics: Boilers, Computational fluid dynamics, Cylinders, Economics , Failure, Feedwater, Flow-induced vibrations, Fluids, Heat transfer, Liquid metals
Proceedings Papers

Research on the Criteria for Single Protection Channel Power Failure in Nuclear Power Plants

Xiuchun Zhang, Hong Xia, Yongkang Liu, Shaomin Zhu, Jiyu Zhang, Junjun Xu, Yingying Jiang, Wenzhe Yin, Jie Zhang, Jie Liu
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A030, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135415
https://doi.org/10.1115/ICONE31-135415
View Paper titled, Research on the Criteria for Single Protection Channel Power Failure in Nuclear Power Plants
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Topics: Failure, Nuclear power stations
Proceedings Papers

Research on the Localization Method of Loose Components in Nuclear Power Plants Based on Hilbert-Huang Signal Processing

Jiming Jiang, Yu Liu, Daogang Lu
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A022, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135066
https://doi.org/10.1115/ICONE31-135066
View Paper titled, Research on the Localization Method of Loose Components in Nuclear Power Plants Based on Hilbert-Huang Signal Processing
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Topics: Monitoring systems, Nuclear power stations, Signal processing, Signals, Circuits, Failure, Algorithms, Building renovation, Collisions (Physics), Construction