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Proceedings Papers

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

Shimei Bao
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A039, August 8–12, 2022
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

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
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

Zhiqi Chen, Jiejin Cai, Xuezhong Li
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A090, August 8–12, 2022
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

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

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
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

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
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

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
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

Study on Dehumidification of Carbon Materials Based on Thermogravimetry

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
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

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
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

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
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

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

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
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

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

Leilei Qiu, Xinyu Wei, Peiwei Sun, Shengyong Liao
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A040, August 4–6, 2021
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

Comparison of the Behavior of Different Jet Configurations in a Crossflow

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
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

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

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
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

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
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

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
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
Proceedings Papers

The International Experimental Thermal Hydraulic Systems Database (TIETHYS): A New NEA Validation Tool

Upendra Rohatgi, James Dyrda, Nicolas Soppera
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A022, July 22–26, 2018
Paper No: ICONE26-82631
https://doi.org/10.1115/ICONE26-82631
View Paper titled, The International Experimental Thermal Hydraulic Systems Database (TIETHYS): A New NEA Validation Tool
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Topics: Databases, Hydraulic drive systems, Nuclear reactors, Relational databases, Boiling water reactors, Computational fluid dynamics, Gas cooled reactors, High temperature, Instrumentation, Liquid metals
Proceedings Papers

Neutronic Methodological Benchmarks With Simplified Geometries for the Gas Cooled Reactor Group Constant Generating Tools

E. Temesvari, B. Batki, M. Gren
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A009, July 22–26, 2018
Paper No: ICONE26-81427
https://doi.org/10.1115/ICONE26-81427
View Paper titled, Neutronic Methodological Benchmarks With Simplified Geometries for the Gas Cooled Reactor Group Constant Generating Tools
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Topics: Approximation, Doppler effect, Gas cooled reactors, Geometry, Leakage, Manufacturing, Modeling, Optical mirrors, Physics, Safety
Proceedings Papers

The Characteristics Study of Helium-Xenon Mixture in Closed Brayton Cycle for Space Nuclear Reactor Power

Xie Yang, Lei Shi
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A025, July 22–26, 2018
Paper No: ICONE26-82220
https://doi.org/10.1115/ICONE26-82220
View Paper titled, The Characteristics Study of Helium-Xenon Mixture in Closed Brayton Cycle for Space Nuclear Reactor Power
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Topics: Brayton cycle, Helium, Nuclear reactors, System efficiency, Fluids, Weight (Mass), Pressure, Turbines, Compressors, Cycles
Proceedings Papers

First-Principles Studies of Diffusion Behaviors of Tritium in HTR-PM Materials: From Framework to Preliminary Result

Chao Fang, WenYi Wang, HongYu Chen, Chuan Li
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A010, July 22–26, 2018
Paper No: ICONE26-81481
https://doi.org/10.1115/ICONE26-81481
View Paper titled, First-Principles Studies of Diffusion Behaviors of Tritium in HTR-PM Materials: From Framework to Preliminary Result
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Topics: Diffusion (Physics), Circuits, High temperature, Alloys, Boilers, Gas cooled reactors, Half-life, Particulate matter, Radiation (Physics), Radioisotopes
Proceedings Papers

Research on Thermal Efficiencies of Various Power Cycles for GFRs and VHTRs

Mohammed Mahdi, Roman Popov, Igor Pioro
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A039, July 22–26, 2018
Paper No: ICONE26-81618
https://doi.org/10.1115/ICONE26-81618
View Paper titled, Research on Thermal Efficiencies of Various Power Cycles for GFRs and VHTRs
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Topics: Thermal efficiency, Thermodynamic power cycles, Very high temperature reactors, Nuclear power stations, Helium, Cycles, Water, Combined cycles, Nitrogen, Gas turbines