1-20 of 70
Gas cooled reactors
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
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
Open the PDF for Feasibility Verification of One Operator Monitoring Two NSSS Modules in Power Plant With Six High Temperature Gas Cooled Reactors Under Accident Conditions in another window
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
Open the PDF for Defect Detection Method for Large Size Graphite and Carbon Components of High Temperature Gas Cooled Reactor Based on Computed Tomography in another window
Topics: Carbon, Computerized tomography, Flaw detection, Gas cooled reactors, Graphite, High temperature
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
Open the PDF for High Temperature Gas Cooled Reactor Steam Generator Research on Stress-Rupture Test of High Temperature Materials and Welded Joints in another window
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
Open the PDF for Numerical Investigation on Heat Transfer Features of Gas-Cooled Open Lattice Reactor in Normal Operations in another window
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
Open the PDF for Research on In-Core Reactivity Control Method and Neutron Characteristic Analysis of a Space Gas-Cooled Reactor in another window
Topics: Accidents, Gas cooled reactors, Neutrons, Nuclear reactors
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
Open the PDF for Numerical Analysis of Fuel Rod Rib Structure Influence on Flow And Heat Transfer of Supercritical Carbon Dioxide in another window
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
Open the PDF for Study on Dehumidification of Carbon Materials Based on Thermogravimetry in another window
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
Open the PDF for Study on the Transport Mechanism and Troubleshooting Analysis of Spherical Fuel in High Temperature Gas Cooled Reactor in another window
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
Open the PDF for Corrosion Behavior of Superalloys in High Temperature Gas Cooled Reactor in Impure Helium With Corrosion Time in another window
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
Open the PDF for Investigation and Design of Energy-Absorbing Structure in Nuclear Fuel Cask in another window
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
Open the PDF for Study on the Dynamic Modeling of the Micro-High Temperature Gas Cooled Reactor for Control System Design in another window
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
Open the PDF for Comparison of the Behavior of Different Jet Configurations in a Crossflow in another window
Topics: Computation, Computational fluid dynamics, Coolants, Cross-flow, Flow (Dynamics), Flow control, Gas cooled reactors, Jets, Particulate matter, Statistics
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
Open the PDF for Neutronic Methodological Benchmarks With Simplified Geometries for the Gas Cooled Reactor Group Constant Generating Tools in another window
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
Open the PDF for The Characteristics Study of Helium-Xenon Mixture in Closed Brayton Cycle for Space Nuclear Reactor Power in another window
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
Open the PDF for First-Principles Studies of Diffusion Behaviors of Tritium in HTR-PM Materials: From Framework to Preliminary Result in another window
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
Open the PDF for Research on Thermal Efficiencies of Various Power Cycles for GFRs and VHTRs in another window
Topics: Thermal efficiency, Thermodynamic power cycles, Very high temperature reactors, Nuclear power stations, Helium, Cycles, Water, Combined cycles, Nitrogen, Gas turbines
Proceedings Papers

Preliminary Development of a TRISO Fuel Performance Analysis Code: FFAT

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
Paper No: ICONE26-82242
https://doi.org/10.1115/ICONE26-82242
View Paper titled, Preliminary Development of a TRISO Fuel Performance Analysis Code: FFAT
Open the PDF for Preliminary Development of a TRISO Fuel Performance Analysis Code: FFAT in another window
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

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
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
Open the PDF for Preliminary Study on Thermal Performance of Inert Matrix Disperse Pellet Using FEA Method in another window
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

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
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
Open the PDF for Study on the Turbulent Mixed Convection Phenomena Inside the Air-Cooled RCCS Riser in another window
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

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
Open the PDF for Filtration Technology Research of Graphite Dust Produced in Spent Fuel Transportation Process in HTR-PM in another window
Topics: Dust, Filtration, Graphite, Spent nuclear fuels, Transportation systems, Fuels, Gas cooled reactors, High temperature, Nuclear power, Pipelines