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Proceedings Papers

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

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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