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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

Modeling and Control Scheme Design of a Multi-Modular High Temperature Gas Cooled Reactor Cogeneration Unit

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Zhonghua Cheng, Zhe Dong
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A015, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135166
https://doi.org/10.1115/ICONE31-135166
View Paper titled, Modeling and Control Scheme Design of a Multi-Modular High Temperature Gas Cooled Reactor Cogeneration Unit
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Topics: Combined heat and power, Control modeling, Design, Gas cooled reactors, High temperature
Proceedings Papers

Feasibility Verification of One Operator Monitoring Two NSSS Modules in Power Plant With Six High Temperature Gas Cooled Reactors Under Accident Conditions

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Runfa Miao, Qianqian Jia, Duo Li
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A001, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-88953
https://doi.org/10.1115/ICONE29-88953
View Paper titled, Feasibility Verification of One Operator Monitoring Two NSSS Modules in Power Plant With Six High Temperature Gas Cooled Reactors Under Accident Conditions
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Topics: Accidents, Gas cooled reactors, High temperature, Power stations
Proceedings Papers

Defect Detection Method for Large Size Graphite and Carbon Components of High Temperature Gas Cooled Reactor Based on Computed Tomography

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Renjie Liu, Yuewen Sun, Tianchen Zeng, Ximing Liu, Libin Sun, Li Shi, Peng Cong
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A039, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92345
https://doi.org/10.1115/ICONE29-92345
View Paper titled, Defect Detection Method for Large Size Graphite and Carbon Components of High Temperature Gas Cooled Reactor Based on Computed Tomography
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Topics: Carbon, Computerized tomography, Flaw detection, Gas cooled reactors, Graphite, High temperature
Proceedings Papers

Numerical Analysis of Fuel Rod Rib Structure Influence on Flow And Heat Transfer of Supercritical Carbon Dioxide

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Dapeng Xi, Minyun Liu, Shenghui Liu, Jinguang Zang, Yanping Huang
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A073, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92224
https://doi.org/10.1115/ICONE29-92224
View Paper titled, Numerical Analysis of Fuel Rod Rib Structure Influence on Flow And Heat Transfer of Supercritical Carbon Dioxide
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Topics: Flow (Dynamics), Fuel rods, Heat transfer, Numerical analysis, Supercritical carbon dioxide, Annulus, Heat transfer coefficients, Heating, Nuclear power, Turbulence
Proceedings Papers

High Temperature Gas Cooled Reactor Steam Generator Research on Stress-Rupture Test of High Temperature Materials and Welded Joints

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Shimei Bao
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A039, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92956
https://doi.org/10.1115/ICONE29-92956
View Paper titled, High Temperature Gas Cooled Reactor Steam Generator Research on Stress-Rupture Test of High Temperature Materials and Welded Joints
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Topics: Boilers, Gas cooled reactors, High temperature, High temperature materials, Rupture, Stress, Very high temperature reactors, Welded joints
Proceedings Papers

Numerical Investigation on Heat Transfer Features of Gas-Cooled Open Lattice Reactor in Normal Operations

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Junlin Fang, Qian Sun, Yu Ji, Zishen Ye, Jun Sun, Zhe Sui
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A105, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92925
https://doi.org/10.1115/ICONE29-92925
View Paper titled, Numerical Investigation on Heat Transfer Features of Gas-Cooled Open Lattice Reactor in Normal Operations
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Topics: Gas flow, Heat conduction, Heat transfer, Thermal radiation, Convection, Design, Fuel rods, Pressurized water reactors, Radiation (Physics), Sodium fast reactors
Proceedings Papers

Research on In-Core Reactivity Control Method and Neutron Characteristic Analysis of a Space Gas-Cooled Reactor

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Zhiqi Chen, Jiejin Cai, Xuezhong Li
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A090, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92383
https://doi.org/10.1115/ICONE29-92383
View Paper titled, Research on In-Core Reactivity Control Method and Neutron Characteristic Analysis of a Space Gas-Cooled Reactor
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Topics: Accidents, Gas cooled reactors, Neutrons, Nuclear reactors
Proceedings Papers

Study on Dehumidification of Carbon Materials Based on Thermogravimetry

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Da Yan, Kaiyue Shen, Yicheng Guo, Huaqiang Yin, Xuedong He, Tao Ma
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A004, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63633
https://doi.org/10.1115/ICONE28-63633
View Paper titled, Study on Dehumidification of Carbon Materials Based on Thermogravimetry
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Topics: Carbon, Dehumidification, Thermogravimetry, Very high temperature reactors, Temperature, Boron, Graphite, High temperature, Corrosion, Desorption
Proceedings Papers

Study on the Transport Mechanism and Troubleshooting Analysis of Spherical Fuel in High Temperature Gas Cooled Reactor

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Jinhua Wang, Yuchen Hao, Yue Li, Bin Wu, Haitao Wang, Tao Ma
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A002, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63134
https://doi.org/10.1115/ICONE28-63134
View Paper titled, Study on the Transport Mechanism and Troubleshooting Analysis of Spherical Fuel in High Temperature Gas Cooled Reactor
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Topics: Fuels, Gas cooled reactors, High temperature, Nuclear power, Transportation systems
Proceedings Papers

Corrosion Behavior of Superalloys in High Temperature Gas Cooled Reactor in Impure Helium With Corrosion Time

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Haoxiang Li, Bin Du, Wei Zheng, Qiuhao Wang, Huaqiang Yin, Xuedong He, Hua Fan, Tao Ma
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A011, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64351
https://doi.org/10.1115/ICONE28-64351
View Paper titled, Corrosion Behavior of Superalloys in High Temperature Gas Cooled Reactor in Impure Helium With Corrosion Time
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Topics: Corrosion, Gas cooled reactors, Helium, High temperature, Oxidation, Superalloys
Proceedings Papers

Study on the Dynamic Modeling of the Micro-High Temperature Gas Cooled Reactor for Control System Design

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Leilei Qiu, Xinyu Wei, Peiwei Sun, Shengyong Liao
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A040, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64455
https://doi.org/10.1115/ICONE28-64455
View Paper titled, Study on the Dynamic Modeling of the Micro-High Temperature Gas Cooled Reactor for Control System Design
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Topics: Control systems, Design, Dynamic modeling, Dynamic models, Gas cooled reactors, Temperature, Transfer functions
Proceedings Papers

Investigation and Design of Energy-Absorbing Structure in Nuclear Fuel Cask

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Yuchen Hao, Yue Li, Jinhua Wang, Bin Wu, Tao Ma, Haitao Wang
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T11A007, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63388
https://doi.org/10.1115/ICONE28-63388
View Paper titled, Investigation and Design of Energy-Absorbing Structure in Nuclear Fuel Cask
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Topics: Design, Nuclear fuels, Transportation systems, Fuels, Metals, Safety, High temperature, Construction, Containers, Economics
Proceedings Papers

Comparison of the Behavior of Different Jet Configurations in a Crossflow

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Michael Lewandowski, Paul Kristo, Abdullah Weiss, Mark Kimber
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A005, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16655
https://doi.org/10.1115/ICONE2020-16655
View Paper titled, Comparison of the Behavior of Different Jet Configurations in a Crossflow
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Topics: Computation, Computational fluid dynamics, Coolants, Cross-flow, Flow (Dynamics), Flow control, Gas cooled reactors, Jets, Particulate matter, Statistics
Proceedings Papers

Preliminary Development of a TRISO Fuel Performance Analysis Code: FFAT

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Jian Li, Ding She, Lei Shi, Jing Zhao
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A046, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82242
https://doi.org/10.1115/ICONE26-82242
View Paper titled, Preliminary Development of a TRISO Fuel Performance Analysis Code: FFAT
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Topics: Fuels, Particulate matter, Failure, Very high temperature reactors, Accidents, Equipment performance, Gas cooled reactors, High temperature, Pressure vessels, Probability
Proceedings Papers

Preliminary Study on Thermal Performance of Inert Matrix Disperse Pellet Using FEA Method

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Lu Zhiwei, Li Yun, Zhang Yongdong, Li Lei, Ma Zhaodandan, Liu Tong
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A044, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82191
https://doi.org/10.1115/ICONE26-82191
View Paper titled, Preliminary Study on Thermal Performance of Inert Matrix Disperse Pellet Using FEA Method
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Topics: Finite element analysis, Fuels, Light water reactors, Thermal conductivity, Accidents, China, Gas cooled reactors, Heat transfer, High temperature, Nuclear fuels
Proceedings Papers

Study on the Turbulent Mixed Convection Phenomena Inside the Air-Cooled RCCS Riser

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Dong-Ho Shin, Sin-Yeob Kim, Chan Soo Kim, Goon-Cherl Park, Hyoung Kyu Cho
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A029, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82071
https://doi.org/10.1115/ICONE26-82071
View Paper titled, Study on the Turbulent Mixed Convection Phenomena Inside the Air-Cooled RCCS Riser
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Topics: Mixed convection, Pipeline risers, Risers (Casting), Turbulence, Ducts, Heat transfer, Cooling systems, Flow (Dynamics), Reactor vessels, Cavities
Proceedings Papers

Filtration Technology Research of Graphite Dust Produced in Spent Fuel Transportation Process in HTR-PM

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Jinhua Wang, Bing Wang, Bin Wu, Yue Li, Haitao Wang
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A001, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81022
https://doi.org/10.1115/ICONE26-81022
View Paper titled, Filtration Technology Research of Graphite Dust Produced in Spent Fuel Transportation Process in HTR-PM
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Topics: Dust, Filtration, Graphite, Spent nuclear fuels, Transportation systems, Fuels, Gas cooled reactors, High temperature, Nuclear power, Pipelines
Proceedings Papers

The Influence of Thermal Deformation on the Dynamic Characteristics of AMB Rotor of HTR-PM Helium Blower

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Guowei Du, Jinpeng Yu, Hong Wang, Lei Zhao
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A004, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81132
https://doi.org/10.1115/ICONE26-81132
View Paper titled, The Influence of Thermal Deformation on the Dynamic Characteristics of AMB Rotor of HTR-PM Helium Blower
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Topics: Helium, Rotors, Thermal deformation, Temperature, Bearings, Computer simulation, Damping, Displacement, Electromagnetic force, Engines
Proceedings Papers

Study on Offsite Emergency Preparedness for the Industry Application of HTR-PM

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Hongchun Ding, Jiejuan Tong, Liguo Zhang
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A007, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81166
https://doi.org/10.1115/ICONE26-81166
View Paper titled, Study on Offsite Emergency Preparedness for the Industry Application of HTR-PM
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Topics: Emergency preparedness, Risk, Nuclear power stations, Emergency management, Gas cooled reactors, High temperature, Plumes (Fluid dynamics), Safety