Search Results | ICONE | ASME Digital Collection

1-20 of 70

2 3 4

Sort by

Sort Order Select

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

DOI: https://doi.org/10.1115/ICONE29-92925

View Paper

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

DOI: https://doi.org/10.1115/ICONE29-92383

View Paper

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

DOI: https://doi.org/10.1115/ICONE29-88953

View Paper

Topics: Accidents, Gas cooled reactors, High temperature, Power stations

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

DOI: https://doi.org/10.1115/ICONE29-92956

View Paper

Topics: Boilers, Gas cooled reactors, High temperature, High temperature materials, Rupture, Stress, Very high temperature reactors, Welded joints

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

DOI: https://doi.org/10.1115/ICONE29-92345

View Paper

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

DOI: https://doi.org/10.1115/ICONE29-92224

View Paper

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

DOI: https://doi.org/10.1115/ICONE28-63633

View Paper

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

Paper No: ICONE28-63134

DOI: https://doi.org/10.1115/ICONE28-63134

View Paper

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

Paper No: ICONE28-64351

DOI: https://doi.org/10.1115/ICONE28-64351

View Paper

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

DOI: https://doi.org/10.1115/ICONE28-63388

View Paper

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

DOI: https://doi.org/10.1115/ICONE28-64455

View Paper

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

DOI: https://doi.org/10.1115/ICONE2020-16655

View Paper

Topics: Computation, Computational fluid dynamics, Coolants, Cross-flow, Flow (Dynamics), Flow control, Gas cooled reactors, Jets, Particulate matter, Statistics

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

DOI: https://doi.org/10.1115/ICONE26-82191

View Paper

Topics: Finite element analysis, Fuels, Light water reactors, Thermal conductivity, Accidents, China, Gas cooled reactors, Heat transfer, High temperature, Nuclear fuels

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

DOI: https://doi.org/10.1115/ICONE26-81132

View Paper

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

DOI: https://doi.org/10.1115/ICONE26-81166

View Paper

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

DOI: https://doi.org/10.1115/ICONE26-82631

View Paper

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

DOI: https://doi.org/10.1115/ICONE26-81427

View Paper

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

DOI: https://doi.org/10.1115/ICONE26-82220

View Paper

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

DOI: https://doi.org/10.1115/ICONE26-81481

View Paper

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

DOI: https://doi.org/10.1115/ICONE26-81618

View Paper

Topics: Thermal efficiency, Thermodynamic power cycles, Very high temperature reactors, Nuclear power stations, Helium, Cycles, Water, Combined cycles, Nitrogen, Gas turbines

2 3 4

NARROW

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

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

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

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

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

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

Study on Dehumidification of Carbon Materials Based on Thermogravimetry

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

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

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

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

Comparison of the Behavior of Different Jet Configurations in a Crossflow

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

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

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

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

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

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

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

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

Journals

Conference Proceedings

eBooks

Resources

Opportunities

Journals

Conference Proceedings

eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only