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Proceedings Papers

Predictions of Component Remaining Useful Life Using Bayesian LSTM for Reactor Coolant Pump

Renyi Xu, Yan Wang, Minjun Peng, Huaiming Cui, Hang Wang, Chengxiao Kuang
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A032, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135439
https://doi.org/10.1115/ICONE31-135439
View Paper titled, Predictions of Component Remaining Useful Life Using Bayesian LSTM for Reactor Coolant Pump
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Topics: Nuclear reactor coolants, Pumps, Service life (Equipment), Uncertainty
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

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

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

Verification of the RMC-SaraGR Nuclear Design Code System Based on the HTTR Benchmark

Yuan Yuan, Guoming Liu, Peng Zhang
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A013, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135368
https://doi.org/10.1115/ICONE31-135368
View Paper titled, Verification of the RMC-SaraGR Nuclear Design Code System Based on the HTTR Benchmark
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Topics: Neutrons, Nuclear design, Uncertainty, Very high temperature reactors, Cross section (Physics), Fuels, Modeling, Rods
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

Geometric Uncertainty Analysis of Fuel Assembly Based on Sub-Channel Model

Deyan Kong, Zhibo Gao, Di Wu, Jie Cheng, Jianjun Wang
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T12A001, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131992
https://doi.org/10.1115/ICONE31-131992
View Paper titled, Geometric Uncertainty Analysis of Fuel Assembly Based on Sub-Channel Model
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Topics: Fuels, Manufacturing, Uncertainty, Uncertainty analysis, Fuel rods, Temperature, Coolants, Pressurized water reactors, Machining, Rods
Proceedings Papers

Uncertainty and Sensitivity Analysis of Phebus FPT-1 Experiment Based on Severe Accident Analysis Code ISAA

Hao Yang, Bin Zhang, Jishen Li, Pengcheng Gao, Zhiran Zhang, Fan Miao
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A078, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136230
https://doi.org/10.1115/ICONE31-136230
View Paper titled, Uncertainty and Sensitivity Analysis of Phebus FPT-1 Experiment Based on Severe Accident Analysis Code ISAA
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Topics: Accidents, Sensitivity analysis, Uncertainty, Uncertainty analysis
Proceedings Papers

Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies

Jian Li, Ruihan Li, Ding She, Jin'gang Liang, Lei Shi
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A008, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89241
https://doi.org/10.1115/ICONE29-89241
View Paper titled, Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies
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Topics: Heat, Pressurized water reactors, Spent nuclear fuels, Fuels, Neutrons, Boiling water reactors, Collapse, Cooling, Cross section (Physics), Density
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

Comparative Machine Learning Study for Estimating Peak Cladding Temperature in AP1000 Under LOFW

Merouane Najar, He Wang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A022, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91516
https://doi.org/10.1115/ICONE29-91516
View Paper titled, Comparative Machine Learning Study for Estimating Peak Cladding Temperature in AP1000 Under LOFW
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Topics: Cladding systems (Building), Machine learning, Temperature, Algorithms, Uncertainty quantification, Accidents, Safety, Uncertainty, Databases, Errors
Proceedings Papers

Uncertainty and Sensitivity Analysis on Loss-of-Flow Accident for Small Integrated Pressurized Water Reactor

Ang Li, Yuqing Chen
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A027, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90347
https://doi.org/10.1115/ICONE29-90347
View Paper titled, Uncertainty and Sensitivity Analysis on Loss-of-Flow Accident for Small Integrated Pressurized Water Reactor
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Topics: Accidents, Flow (Dynamics), Pressurized water reactors, Sensitivity analysis, Uncertainty
Proceedings Papers

Estimation of the 1F2 Core Thermal Status During the Core Heat-Up Phase With MELCOR-2.2

Shotaro Osako, Xin Li, Akifumi Yamaji
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A009, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89102
https://doi.org/10.1115/ICONE29-89102
View Paper titled, Estimation of the 1F2 Core Thermal Status During the Core Heat-Up Phase With MELCOR-2.2
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Topics: Accidents, Fuels, Fukushima nuclear disaster, Japan, 2011, Heat, Oxidation, Melting, Temperature, Leakage, Nuclear decommissioning, Nuclear power stations
Proceedings Papers

A Chinese 300MWe Two-Loop PWR NPP LBLOCA Analysis Based on the Deterministic Realistic Hybrid Methodology

Yuhan Li, Bo Kuang
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A009, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92431
https://doi.org/10.1115/ICONE29-92431
View Paper titled, A Chinese 300MWe Two-Loop PWR NPP LBLOCA Analysis Based on the Deterministic Realistic Hybrid Methodology
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Topics: Nuclear power stations, Pressurized water reactors, Safety, Accidents, Life extension, Uncertainty, China, Cladding systems (Building), Coolants, Design
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

Study for the Optimization of the Decommissioning Project of Nuclear Facilities

Yukihiro Iguchi, Daisuke Kawasaki, Satoshi Yanagihara
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A001, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-88888
https://doi.org/10.1115/ICONE29-88888
View Paper titled, Study for the Optimization of the Decommissioning Project of Nuclear Facilities
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Topics: Nuclear decommissioning, Nuclear power stations, Optimization, Risk, Uncertainty
Proceedings Papers

Disorders in Fluid Filled Pipeline Structure With Elastic Helmholtz Resonators

Qingna Zeng, Donghui Wang, Fenggang Zang, Yixiong Zhang, Bihao Wang, Zhihao Yuan
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A080, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93421
https://doi.org/10.1115/ICONE29-93421
View Paper titled, Disorders in Fluid Filled Pipeline Structure With Elastic Helmholtz Resonators
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Topics: Energy gap, Fluids, Pipelines, Acoustics, Stability, Vibration, Cavities, Design, Engineering systems and industry applications, Finite element methods
Proceedings Papers

Security Analysis Based on Probabilistic Safety Analysis Coupled With Deterministic Safety Analysis Used RAVEN

Dabin Sun, Zhijian Zhang, Lei Li, He Wang, Sijuan Chen, Yuhang Zhang, Lixuan Zhang
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A033, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64361
https://doi.org/10.1115/ICONE28-64361
View Paper titled, Security Analysis Based on Probabilistic Safety Analysis Coupled With Deterministic Safety Analysis Used RAVEN
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Topics: Probabilistic safety assessment, Risk, Safety, Security analysis, Uncertainty
Proceedings Papers

Nonlinear Low Bias Current Control for Magnetic Bearing System Using Active Disturbance Rejection Technology

Yichen Yao, Yixin Su, Suyuan Yu
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A083, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65730
https://doi.org/10.1115/ICONE28-65730
View Paper titled, Nonlinear Low Bias Current Control for Magnetic Bearing System Using Active Disturbance Rejection Technology
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Topics: Magnetic bearings, Control equipment, Modeling, Bearings, Design, Energy consumption, Helium, Machinery, Noise control, Poles (Building)
Proceedings Papers

Low Dose Assessment Uncertainty Analysis for Landauer ® nanoDot™ OSLDs

Egemen Aras, Robert Hayes
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A074, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65591
https://doi.org/10.1115/ICONE28-65591
View Paper titled, Low Dose Assessment Uncertainty Analysis for Landauer ® nanoDot™ OSLDs
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Topics: Background radiation, Dosimeters, Radiation (Physics), Safety, Security, Statistics, Uncertainty, Uncertainty analysis