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Proceedings Papers

Stress Intensity Factor Solutions for Circumferential Through-Wall Cracks Applicable to Pool Type Sodium Cooled Fast Reactors

Hiroki Yada, Shigeru Takaya, Hideo Machida
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A010, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134552
https://doi.org/10.1115/ICONE31-134552
View Paper titled, Stress Intensity Factor Solutions for Circumferential Through-Wall Cracks Applicable to Pool Type Sodium Cooled Fast Reactors
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Topics: Cylinders, Fast neutron reactors, Finite element analysis, Fracture (Materials), Sodium, Stress
Proceedings Papers

Investigation About Classification of Stresses due to Radial Deformation Induced by Design Pressure Applied to the Tubes of Square Pitch Multi-Perforated Portion of Thick Plates

Pascal Duranton, Marie Bernion, Aboubakr Amzil, Divjot Jolly, Abdelhak Benrabia, Tony Da Silva
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A009, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134544
https://doi.org/10.1115/ICONE31-134544
View Paper titled, Investigation About Classification of Stresses due to Radial Deformation Induced by Design Pressure Applied to the Tubes of Square Pitch Multi-Perforated Portion of Thick Plates
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Topics: Deformation, Design, Plates (structures), Pressure, Stress, Finite element methods, Welding, Heat exchangers, Mechanical behavior, Nuclear industry
Proceedings Papers

Load-Following Control of Nuclear Reactor Using Variable-Order Fuzzy Fractional PID Controller Based on the Fractional-Space Neutron Point Kinetics Model

Hetao Sun, Hailemichael Guadie Mengsitu, Xiuchun Luan, Jie Zhou, Junling Wang, Zhida Yang
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A027, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135371
https://doi.org/10.1115/ICONE31-135371
View Paper titled, Load-Following Control of Nuclear Reactor Using Variable-Order Fuzzy Fractional PID Controller Based on the Fractional-Space Neutron Point Kinetics Model
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Topics: Control equipment, Neutrons, Nuclear reactors, Stress
Proceedings Papers

Investigation in Design Technology of Load Follow Without Changing Soluble Boron of Hualong One

Cui Huaiming, Ning Zhonghao, Liu TongXian, Wang ChenLin, Li Tian Ya, Cai Yun
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A024, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135183
https://doi.org/10.1115/ICONE31-135183
View Paper titled, Investigation in Design Technology of Load Follow Without Changing Soluble Boron of Hualong One
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Topics: Boron, Design, Stress, Water
Proceedings Papers

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

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

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

Structural Design and Analysis of Plate-Type Fuel Assembly of Research Reactor

Hyun-Jung Kim, Young-Wook Tahk, Dong-Hyun Kim
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A008, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132740
https://doi.org/10.1115/ICONE31-132740
View Paper titled, Structural Design and Analysis of Plate-Type Fuel Assembly of Research Reactor
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Topics: Fuels, Manufacturing, Stress, Structural analysis, Structural design, Vibration
Proceedings Papers

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

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

A Fuzzy Control Method for Adjusting the Peak Value of Power Axial Distribution Based on Distributed Parameter Model

Airan Dang, Bowen Tu, Xiuchun Luan
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A013, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135044
https://doi.org/10.1115/ICONE31-135044
View Paper titled, A Fuzzy Control Method for Adjusting the Peak Value of Power Axial Distribution Based on Distributed Parameter Model
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Topics: Distributed parameter models, Fuzzy control, Steady state, Control equipment, Diffusion (Physics), Neutrons, Stress, Distributed parameter systems, Simulation results, Spacetime
Proceedings Papers

A Coordinated Control Strategy for NHR200-II Under Load Rejection Condition

Canxing Huang, Huasheng Xiong, Zhe Dong, Boyuan Li, Shuqiao Zhou
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A022, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136013
https://doi.org/10.1115/ICONE31-136013
View Paper titled, A Coordinated Control Strategy for NHR200-II Under Load Rejection Condition
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Topics: Stress
Proceedings Papers

Constrained Nonlinear Model Predictive Control for High Temperature Gas-Cooled Reactor in Load Following

Yunlong Zhu, Zhe Dong, Xiaojin Huang
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A023, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136137
https://doi.org/10.1115/ICONE31-136137
View Paper titled, Constrained Nonlinear Model Predictive Control for High Temperature Gas-Cooled Reactor in Load Following
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Topics: Predictive control, Stress, Very high temperature reactors
Proceedings Papers

Study on Parameters Design Methodology for Rolling and Pitching Test of Control Rod Hydraulic Drive System

Yanlin Li, Benke Qin, Hanliang Bo
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A008, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-130895
https://doi.org/10.1115/ICONE31-130895
View Paper titled, Study on Parameters Design Methodology for Rolling and Pitching Test of Control Rod Hydraulic Drive System
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Topics: Design methodology, Hydraulic drive systems, Rods, Stress, Accidents, Design, Fluids, Heating, Marine engineering, Naval architecture
Proceedings Papers

Optimization of Inventory Control Strategy for Part Load Operation in a sCO 2 Recuperated Brayton Cycle for a 5 MW th Heat Pipe Micro Modular Reactor

Matthias Peiretti, Markus Hofer, Michael Buck, Ruggero Meucci, Jörg Starflinger
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A025, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133703
https://doi.org/10.1115/ICONE31-133703
View Paper titled, Optimization of Inventory Control Strategy for Part Load Operation in a sCO 2 Recuperated Brayton Cycle for a 5 MW th Heat Pipe Micro Modular Reactor
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Topics: Brayton cycle, Heat pipes, Optimization, Stress
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

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

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

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

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
Proceedings Papers

Effect of Pressure Acting on the Flaw Surface on Plastic Collapse Strength for Pipes With the Circumferential Surface Flaw

Hideo Machida
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T06A001, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-126112
https://doi.org/10.1115/ICONE31-126112
View Paper titled, Effect of Pressure Acting on the Flaw Surface on Plastic Collapse Strength for Pipes With the Circumferential Surface Flaw
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Topics: Collapse, Fitness-for-service, Pipes, Pressure, Stress
Proceedings Papers

Study on the Dynamic Characteristics of the Supercritical CO2 Recompression Brayton Cycle for a Lead-Bismuth Generator Set

Yifan Zhang, Hongzhi Li, Yujia Zhou
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A057, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135095
https://doi.org/10.1115/ICONE31-135095
View Paper titled, Study on the Dynamic Characteristics of the Supercritical CO2 Recompression Brayton Cycle for a Lead-Bismuth Generator Set
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Topics: Brayton cycle, Fast neutron reactors, Generators, Stress, Supercritical carbon dioxide
Proceedings Papers

Design and Performance Verification of Passive Core Cooling System Strainer in Advanced Nuclear Power Plants of China

Ruolin Huang
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A051, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134892
https://doi.org/10.1115/ICONE31-134892
View Paper titled, Design and Performance Verification of Passive Core Cooling System Strainer in Advanced Nuclear Power Plants of China
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Topics: China, Cooling, Cooling systems, Design, Emergency core cooling systems, Nuclear power stations, Loss of coolant accidents, Filters, Aluminum, Coating processes
Proceedings Papers

Prediction of Thermal-Hydraulic Parameters for Autonomous Load Following LFR Core Using Surrogate Model

Kefan Zhang, Wenshun Duan, Junjia Zhang, Hongli Chen
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A052, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134988
https://doi.org/10.1115/ICONE31-134988
View Paper titled, Prediction of Thermal-Hydraulic Parameters for Autonomous Load Following LFR Core Using Surrogate Model
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Topics: Fast neutron reactors, Stress