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Proceedings Papers

Research on Sealing Performance and Electrical Performance of Electrical Penetration Assembly in Nuclear Reactor Containment

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Yanlu Wang, Xinli Yu, Xiaxin Cao, Yu Liu
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A015, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134800
https://doi.org/10.1115/ICONE31-134800
View Paper titled, Research on Sealing Performance and Electrical Performance of Electrical Penetration Assembly in Nuclear Reactor Containment
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Topics: Containment, Manufacturing, Nuclear reactors, Sealing (Process)
Proceedings Papers

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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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

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

Study on the Spent Fuel Management in Different Developed Countries

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Lei Shi, Jiqiang Su, Ding Chen, Yan An
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A041, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135560
https://doi.org/10.1115/ICONE31-135560
View Paper titled, Study on the Spent Fuel Management in Different Developed Countries
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Topics: Nuclear reactors, Spent nuclear fuels
Proceedings Papers

Multiple Knowledge Exploration Functions for Advanced Reactor Design and Safety in Knowledge Management System Implemented in the ARKADIA

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Akiyuki Seki, Yuki Kondo, Ryuta Hashidate, Masanori Yoshikawa, Kenji Yokoyama, Shigeru Takaya, Yasuhiro Enuma, Taira Hazama, Takashi Wakai, Tai Asayama
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A012, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131784
https://doi.org/10.1115/ICONE31-131784
View Paper titled, Multiple Knowledge Exploration Functions for Advanced Reactor Design and Safety in Knowledge Management System Implemented in the ARKADIA
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Topics: Design, Knowledge management, Safety, Computer-aided design, Information retrieval, Sodium fast reactors, Artificial intelligence, Carbon, Computer simulation, Engineering drawings
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

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

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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

Conceptual Design and Feasibility Analysis of a Modular Supercritical CO 2 Fast Reactor Core

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Guihua Lai, Tian Wang, Ding She, Hong Wang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A045, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135206
https://doi.org/10.1115/ICONE31-135206
View Paper titled, Conceptual Design and Feasibility Analysis of a Modular Supercritical CO 2 Fast Reactor Core
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Topics: Conceptual design, Fast neutron reactors, Small modular reactors, Supercritical carbon dioxide, Safety, Temperature, Design, Fuel rods, Heat, Particulate matter
Proceedings Papers

Design and Analysis of a Nuclear Hydrogen Production System by Methanol Reforming Using Light Water Reactor (LWR)

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Ruiyang Liu, Zhiyi Peng, Huaqiang Yin, Huang Zhang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A001, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-123745
https://doi.org/10.1115/ICONE31-123745
View Paper titled, Design and Analysis of a Nuclear Hydrogen Production System by Methanol Reforming Using Light Water Reactor (LWR)
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Topics: Design, Hydrogen production, Light water reactors, Methanol, Nuclear reactors, Steam reforming, Water
Proceedings Papers

Criteria for Selecting Nuclear Reactors for Merchant Shipping

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Jan Emblemsvåg, César Hueso Ordóñez, Cristian Garrido Tamm, Terje Strand, Helge Thoresen, Javier Santos Ortigosa, Alejandría Pérez, Yolanda Mugica Colilles, Alba Esteban Izquierdo
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A043, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135177
https://doi.org/10.1115/ICONE31-135177
View Paper titled, Criteria for Selecting Nuclear Reactors for Merchant Shipping
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Topics: Nuclear reactors, Ships, Small modular reactors, Emissions, Fuel oils, Fuels, Greenhouse gases, Life cycle costing, Light water reactors, Molten salt reactors
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

Effects of Mixed Inert Gases on Design of Centrifugal Compressors for Space Nuclear Reactor

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Risheng Xu, Wenkui Ma, Ping Ye, Gang Zhao, Xiaoyong Yang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A062, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135992
https://doi.org/10.1115/ICONE31-135992
View Paper titled, Effects of Mixed Inert Gases on Design of Centrifugal Compressors for Space Nuclear Reactor
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Topics: Brayton cycle, Compressors, Design, Gases, Nuclear reactors
Proceedings Papers

Inventory Control Strategy and Dynamic Modelling of a 1 MWe HeXe Brayton Cycle Reactor System

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Xinyu Li, Chaoran Guan, Xiang Chai, Xiaojing Liu
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A031, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134369
https://doi.org/10.1115/ICONE31-134369
View Paper titled, Inventory Control Strategy and Dynamic Modelling of a 1 MWe HeXe Brayton Cycle Reactor System
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Topics: Brayton cycle, Dynamic modeling, Nuclear reactors
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

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

Optimal Design of a Coupling System of Heat Pipe Cooled Reactor With Battery Energy Storage System

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Limin Liu, Ziyin Liu, Ziang Guo, Hanyang Gu
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A070, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136516
https://doi.org/10.1115/ICONE31-136516
View Paper titled, Optimal Design of a Coupling System of Heat Pipe Cooled Reactor With Battery Energy Storage System
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Topics: Batteries, Design, Energy storage, Heat pipes, Nuclear reactors
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

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

Experimental Study of Heat Transfer Characteristics During Reflooding Process Under Partially Exposed Conditions in Narrow Rectangular Channels

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Junchen Wu, Haidong Liu, Deqi Chen, Qianlong Zuo, Hanzhou Liu, Jian Deng, Dan Wu, Mingjing Chen
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A093, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136011
https://doi.org/10.1115/ICONE31-136011
View Paper titled, Experimental Study of Heat Transfer Characteristics During Reflooding Process Under Partially Exposed Conditions in Narrow Rectangular Channels
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Topics: Accidents, Boiling, Coolants, Cooling, Film boiling, Flow (Dynamics), Fuels, Heat transfer, Heat transfer coefficients, Nuclear reactors