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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

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
Proceedings Papers

Implementation of Domain Decomposition Parallel and gCMFD in MOCP: Method of Characteristics for Pebble-Bed

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Chen Hao, Yu Chen Wen, Yi Zhen Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A033, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134979
https://doi.org/10.1115/ICONE31-134979
View Paper titled, Implementation of Domain Decomposition Parallel and gCMFD in MOCP: Method of Characteristics for Pebble-Bed
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Topics: Geometry, Neutrons, Simulation, Stress, Very high temperature reactors
Proceedings Papers

Neutronics–Mechanics Coupling for Fast Transient Simulation in Molten Salt Reactors

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Théo Vidril, Stanislas de Lambert, Nicolas Lelong, Florence Drui, Cyril Patricot, Elsa Merle
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133060
https://doi.org/10.1115/ICONE31-133060
View Paper titled, Neutronics–Mechanics Coupling for Fast Transient Simulation in Molten Salt Reactors
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Topics: Molten salt reactors, Simulation, Transients (Dynamics)
Proceedings Papers

Simulation Calculation of the Utilization Rate of Uranium Resources on the ADANES Fuel Cycle

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Xuesong Yan, Yucui Gao, Yaling Zhang, Lei Yang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A001, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-130623
https://doi.org/10.1115/ICONE31-130623
View Paper titled, Simulation Calculation of the Utilization Rate of Uranium Resources on the ADANES Fuel Cycle
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Topics: Fuels, Nuclear fuel cycle, Nuclear power, Simulation, Uranium
Proceedings Papers

Weight Window Generation Based on Pre-Calculated Response Matrix

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Yingzhe Hu, Pengfei Shen, Shihang Jiang, Shanfang Huang, Kan Wang, Zeguang Li, Zhaoyuan Liu
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A023, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134556
https://doi.org/10.1115/ICONE31-134556
View Paper titled, Weight Window Generation Based on Pre-Calculated Response Matrix
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Topics: Weight (Mass), Generators, Simulation
Proceedings Papers

High-Fidelity Depletion-Pebble-Flow Coupling Simulation of Pebble Bed Reactor HTR-PM

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Ruihan Li, Jingang Liang, Ding She, Weijian Zhang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A024, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134641
https://doi.org/10.1115/ICONE31-134641
View Paper titled, High-Fidelity Depletion-Pebble-Flow Coupling Simulation of Pebble Bed Reactor HTR-PM
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Topics: Discrete element methods, Flow (Dynamics), Simulation
Proceedings Papers

Molten Salt Reactor Simulation by a MOOSE-Based Application Suanni

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Ao Zhang, Ming Dai, Shaopeng Xia, Jingen Chen, Xiangzhou Cai
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A065, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136944
https://doi.org/10.1115/ICONE31-136944
View Paper titled, Molten Salt Reactor Simulation by a MOOSE-Based Application Suanni
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Topics: Cross section (Physics), Molten salt reactors, Simulation, Errors, Diffusion (Physics), Finite element methods, Fuels, Light water reactors, Thermal reactors
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

Kriging Surrogate Modelling of Multiplication Factor With Random Effect

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Yizhen Wang, Chen Hao
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A063, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136647
https://doi.org/10.1115/ICONE31-136647
View Paper titled, Kriging Surrogate Modelling of Multiplication Factor With Random Effect
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Topics: Metamodeling, Simulation
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

Simulation Study of Turbine Trips Without Scram for CPR1000 Nuclear Power Plant Employing MSHIM Control

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Shifa Wu, Yunzhi Chai, Jiashuang Wan
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A006, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134523
https://doi.org/10.1115/ICONE31-134523
View Paper titled, Simulation Study of Turbine Trips Without Scram for CPR1000 Nuclear Power Plant Employing MSHIM Control
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Topics: Nuclear power stations, Scram, Simulation, Turbines
Proceedings Papers

CFD-DEM Simulation on Gas-Solid Separation and Sphere Packing Behaviors in a Storage Bin of the Small Absorber Sphere System

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Tianjin Li, Haitao Hu, He Yan, Xingzhong Diao
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A054, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135598
https://doi.org/10.1115/ICONE31-135598
View Paper titled, CFD-DEM Simulation on Gas-Solid Separation and Sphere Packing Behaviors in a Storage Bin of the Small Absorber Sphere System
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Topics: Computational fluid dynamics, Discrete element methods, Flow (Dynamics), Packing (Shipments), Packings (Cushioning), Separation (Technology), Simulation, Storage, Very high temperature reactors
Proceedings Papers

Analysis of SMR Reactor Coolant System in APROS

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Zhu Ye, Wang Xinbo, Liao Xianwei, Cai Zhiyun, Liu Minghao
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A010, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131299
https://doi.org/10.1115/ICONE31-131299
View Paper titled, Analysis of SMR Reactor Coolant System in APROS
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Topics: Nuclear reactor coolants, Simulation
Proceedings Papers

Multiphysics Coupling Analysis of an FCM-Fueled Gas-Cooled Microreactor

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Jipu Hu, Yuyang Shen, Ruixiang Wang, Kuaiyuan Feng, Lei Lou, Hui Guo
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A002, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-124442
https://doi.org/10.1115/ICONE31-124442
View Paper titled, Multiphysics Coupling Analysis of an FCM-Fueled Gas-Cooled Microreactor
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Topics: Accidents, Ceramics, Computer software, Coolants, Design, Engineering simulation, Flow (Dynamics), Fluids, Fuels, Graphite
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

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

Hydrogen Production by High Temperature Steam Electrolysis Coupled With a Small Modular Reactor: Cross-Comparison Between Various Thermal Architectures

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Nicolas Tauveron, David Haubensack, Pierre Dumoulin, Nicolas Alpy
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A052, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135501
https://doi.org/10.1115/ICONE31-135501
View Paper titled, Hydrogen Production by High Temperature Steam Electrolysis Coupled With a Small Modular Reactor: Cross-Comparison Between Various Thermal Architectures
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Topics: Architecture, Electrolysis, High temperature steam, Hydrogen production, Small modular reactors, Simulation, Heat, Atmospheric pressure, Experimental design, Heat pumps
Proceedings Papers

Preliminary Design and Transient Simulation of a Nuclear-Solar Hybrid System Using an Open-Air Brayton Cycle

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Jiaolong Deng, Chaoran Guan, Xiaojing Liu, Hui He, Xiang Chai
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A041, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135136
https://doi.org/10.1115/ICONE31-135136
View Paper titled, Preliminary Design and Transient Simulation of a Nuclear-Solar Hybrid System Using an Open-Air Brayton Cycle
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Topics: Brayton cycle, Concentrating solar power, Design, Heat, Nuclear reactors, Pipes, Simulation, Solar energy, Thermal energy storage, Transients (Dynamics)
Proceedings Papers

Dynamic Simulation of a Small Modular Sodium-Cooled Fast Reactor Coupled With Molten Salt Energy Storage System

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Jinrong Jin, Jiashuang Wan, Shifa Wu, Areai Nuerlan
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A071, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136749
https://doi.org/10.1115/ICONE31-136749
View Paper titled, Dynamic Simulation of a Small Modular Sodium-Cooled Fast Reactor Coupled With Molten Salt Energy Storage System
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Topics: Energy storage, Heat storage, Simulation, Sodium fast reactors, Stress