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Proceedings Papers

Adaptive Refinement Simulation Model of Condenser Based on the Mechanism-AI Coupling Modeling Paradigm

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Furu Jing, Ruojun Xue, Jiaming Tang, Haofang Chong
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A023, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135134
https://doi.org/10.1115/ICONE31-135134
View Paper titled, Adaptive Refinement Simulation Model of Condenser Based on the Mechanism-AI Coupling Modeling Paradigm
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Topics: Condensers (steam plant), Modeling, Simulation, Simulation models
Proceedings Papers

A Control-Oriented Hybrid Model for Nuclear Reactors Based on Neural Network

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Ze Zhu, Wenlong Liang, Baiqing Ye, Qingfeng Jiang, Pengfei Wang
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A039, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135988
https://doi.org/10.1115/ICONE31-135988
View Paper titled, A Control-Oriented Hybrid Model for Nuclear Reactors Based on Neural Network
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Topics: Algorithms, Artificial neural networks, Modeling, Nuclear reactors
Proceedings Papers

Research on the ODR-VS Method Applicable to Various Geometric Models

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Zhiyuan Feng, Jingang Liang, Wenli Guo, Kan Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A032, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134943
https://doi.org/10.1115/ICONE31-134943
View Paper titled, Research on the ODR-VS Method Applicable to Various Geometric Models
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Topics: Ceramics, Cylinders, Discrete element methods, Ductility, Fuels, Geometric modeling, Metals, Modeling, Neutrons, Nuclear fuels
Proceedings Papers

Bamboo-Frame: An Automatic Modeling Tool for the Two-Step Reactor Core Physics Analysis

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Yuancheng Zhou, Yunzhao Li, Yisong Li, Yilin Liang, Hengrui Zhang, Shilong Zhou, Weiguo Wang, Yuxiang Ou
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A038, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135358
https://doi.org/10.1115/ICONE31-135358
View Paper titled, Bamboo-Frame: An Automatic Modeling Tool for the Two-Step Reactor Core Physics Analysis
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Topics: Modeling, Physics, Pressurized water reactors
Proceedings Papers

The SPIZWURZ Project - Experimental and Modeling Approaches of Hydrogen in Cladding Tubes Under Dry Storage Conditions

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Sarah Weick, Michel Herm, Mirco Grosse, Robert Kilger, Conrado Rössger, Martin Steinbrueck, Juri Stuckert
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A064, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136905
https://doi.org/10.1115/ICONE31-136905
View Paper titled, The SPIZWURZ Project - Experimental and Modeling Approaches of Hydrogen in Cladding Tubes Under Dry Storage Conditions
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Topics: Cladding systems (Building), Hydrogen, Modeling, Storage
Proceedings Papers

Research on Fuel Pebble Modeling Methods Comparison and Eigenvalue Analysis of the Running-in Phase of HTR-PM

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Qianye Yang, Nan Gui, Jiyuan Tu, Shengyao Jiang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A004, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131880
https://doi.org/10.1115/ICONE31-131880
View Paper titled, Research on Fuel Pebble Modeling Methods Comparison and Eigenvalue Analysis of the Running-in Phase of HTR-PM
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Topics: Design, Eigenvalues, Fuels, Modeling, Graphite, Simulation, High temperature, Nuclear fuels, Particulate matter, Safety
Proceedings Papers

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

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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

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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

Steam-Water Two-Phase Flow Testing Under Nominal Pressure and Temperature Conditions for Natural Circulation Performance of Chimney in BWRX-300 SMR

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Hajime Furuichi, Antonin Povolny, Kenichi Katono, Kenichi Yasuda, Kazuaki Kito, Charles Heck
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A030, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134289
https://doi.org/10.1115/ICONE31-134289
View Paper titled, Steam-Water Two-Phase Flow Testing Under Nominal Pressure and Temperature Conditions for Natural Circulation Performance of Chimney in BWRX-300 SMR
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Topics: Porosity, Pressure, Sensors, Steam, Temperature, Testing, Two-phase flow, Water, Wire mesh, Boiling water reactors
Proceedings Papers

Effect of the Heat Transfer Correlation Choice on the Coupled Assessment of Energy Release and Stress-Strain State of an Elementary Supercritical Fuel Rod Under Nuclear Heating Conditions

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Vladislav Filonov, Oleksandr Kovalenko, Yaroslav Dubyk, Yuliia Filonova, Dmitriy Fedorov
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A069, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136275
https://doi.org/10.1115/ICONE31-136275
View Paper titled, Effect of the Heat Transfer Correlation Choice on the Coupled Assessment of Energy Release and Stress-Strain State of an Elementary Supercritical Fuel Rod Under Nuclear Heating Conditions
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Topics: Approximation, Diffusion (Physics), Fuel rods, Heat transfer, Heating, Stress, Temperature, Design, Fuels, Computational fluid dynamics
Proceedings Papers

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

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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

Research on a Space Reactor Scheme for the Lunar Research Station

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Zhipeng Wang, Qiang Sheng, Zijing Liu, Ke Wang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A003, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-125424
https://doi.org/10.1115/ICONE31-125424
View Paper titled, Research on a Space Reactor Scheme for the Lunar Research Station
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Topics: Cycles, Design, Energy / power systems, Energy generation, Flow (Dynamics), Fuel rods, Heat transfer, Magnetohydrodynamics, Modeling, NASA
Proceedings Papers

Thermo-Neutronics Coupled Simulation of a Heat Pipe Reactor Based on OpenMC/COMSOL

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Jingyu Nie, Binqian Li, Yingwei Wu, Jing Zhang, Guoliang Zhang, Qisen Ren, Yanan He, Guanghui Su
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A047, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135246
https://doi.org/10.1115/ICONE31-135246
View Paper titled, Thermo-Neutronics Coupled Simulation of a Heat Pipe Reactor Based on OpenMC/COMSOL
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Topics: Heat pipes, Simulation, Neutrons, Physics, Cross section (Physics), Databases, Density, Design, Modeling, Nuclear reactors
Proceedings Papers

Dynamic Event Tree Analysis of SGTR Accidents Considering HRA

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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

Model Evaluation and Parallelization of Subchannel Analysis Code for Full-Core Pin-by-Pin Analysis

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Zhonghao Yu, Jinbiao Xiong
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T06A002, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133784
https://doi.org/10.1115/ICONE31-133784
View Paper titled, Model Evaluation and Parallelization of Subchannel Analysis Code for Full-Core Pin-by-Pin Analysis
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Topics: Databases, Errors, Flow (Dynamics), Friction, Modeling, Nuclear power plant operations, Nuclear reactors, Optimization, Pressurized water reactors, Resolution (Optics)
Proceedings Papers

Comparison of Different Methods to Parameterize Errors in Inverse Modeling of Atmospheric Emissions

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Xinwen Dong, Yuhan Xu, Shuhan Zhuang, Hao Hu, Sheng Fang
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A013, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134601
https://doi.org/10.1115/ICONE31-134601
View Paper titled, Comparison of Different Methods to Parameterize Errors in Inverse Modeling of Atmospheric Emissions
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Topics: Emissions, Errors, Modeling
Proceedings Papers

Three-Dimensional Numerical Simulation on DRACS and PRACS Heat Removal Ways of Natural Circulation Based on the PLANDTL-DHX Experimental Device

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Haijie Song, Xiangfeng Ma, Haiqi Zhao, Yuhao Zhang, Daogang Lu, Xueyuan Zhang
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A108, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136974
https://doi.org/10.1115/ICONE31-136974
View Paper titled, Three-Dimensional Numerical Simulation on DRACS and PRACS Heat Removal Ways of Natural Circulation Based on the PLANDTL-DHX Experimental Device
Open the PDF for Three-Dimensional Numerical Simulation on DRACS and PRACS Heat Removal Ways of Natural Circulation Based on the PLANDTL-DHX Experimental Device in another window
Topics: Computer simulation, Heat, Sodium fast reactors, Flow (Dynamics), Cooling systems, Modeling, Computational methods, Design, Temperature
Proceedings Papers

Modelling Mass Transfer and Mixing of Corium with Concrete during Molten Corium-Concrete Interaction: Impact of Concrete Thermal Conductivity

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Ilyas Khurshid, Yacine Addad, Imran Afgan
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A097, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136086
https://doi.org/10.1115/ICONE31-136086
View Paper titled, Modelling Mass Transfer and Mixing of Corium with Concrete during Molten Corium-Concrete Interaction: Impact of Concrete Thermal Conductivity
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Topics: Ablation (Vaporization technology), Concretes, Heat transfer, Mass transfer, Modeling, Thermal conductivity
Proceedings Papers

Preliminary Assessment of CATHARE-MODELICA Codes Coupling for Safety Analyses in Nuclear Cogeneration

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Alessandro De Angelis, Paolo Olita, Walter Ambrosini
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A094, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136017
https://doi.org/10.1115/ICONE31-136017
View Paper titled, Preliminary Assessment of CATHARE-MODELICA Codes Coupling for Safety Analyses in Nuclear Cogeneration
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Topics: Combined heat and power, Safety, Small modular reactors, Energy / power systems, Carbon, Transients (Dynamics), Dynamic modeling, Economics , Hydraulic drive systems, Mass production
Proceedings Papers

Inquiry on the Effect of Heating Structures in the Prediction of Flow Stability at Supercritical Pressures

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Alessio Betti, Andrea Pucciarelli, Walter Ambrosini
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A067, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135176
https://doi.org/10.1115/ICONE31-135176
View Paper titled, Inquiry on the Effect of Heating Structures in the Prediction of Flow Stability at Supercritical Pressures
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Topics: Computational fluid dynamics, Flow (Dynamics), Heating, Stability, Supercritical water reactors, Design, Modeling, Oscillations, Flow instability, Fluid density