1-20 of 80
Transportation systems
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

Economical Research on Hydrogen Production of Sodium-Cooled Fast Reactor

Zhiwen Dai
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A004, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132454
https://doi.org/10.1115/ICONE31-132454
View Paper titled, Economical Research on Hydrogen Production of Sodium-Cooled Fast Reactor
Open the PDF for Economical Research on Hydrogen Production of Sodium-Cooled Fast Reactor in another window
Topics: Hydrogen, Hydrogen production, Nuclear power stations, Sodium fast reactors, Transportation systems
Proceedings Papers

Assessment of CFD Methods in Simulating Flowfield in a Vane-Type Separator

Xiaobo Zeng, Yifan Xu, Guangming Fan, Changqi Yan
Proc. ASME. ICONE31, Volume 7: Computational Fluid Dynamics (CFD) and Applications, V007T08A001, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132562
https://doi.org/10.1115/ICONE31-132562
View Paper titled, Assessment of CFD Methods in Simulating Flowfield in a Vane-Type Separator
Open the PDF for Assessment of CFD Methods in Simulating Flowfield in a Vane-Type Separator in another window
Topics: Computational fluid dynamics, Large eddy simulation, Centrifugal force, Flow (Dynamics), Fuels, Interface phenomena, Interface structure, Molten salt reactors, Nuclear fission, Simulation
Proceedings Papers

Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies

Jian Li, Ruihan Li, Ding She, Jin'gang Liang, Lei Shi
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A008, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89241
https://doi.org/10.1115/ICONE29-89241
View Paper titled, Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies
Open the PDF for Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies in another window
Topics: Heat, Pressurized water reactors, Spent nuclear fuels, Fuels, Neutrons, Boiling water reactors, Collapse, Cooling, Cross section (Physics), Density
Proceedings Papers

Drop Analyses and Verification of the Spent Nuclear Fuel Transportation Cask Under Hypothetical Accident Conditions

Guangdong Liu, Weiliang Wu, He Zhu, Qingjun Ma, Qipeng Li
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A042, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91927
https://doi.org/10.1115/ICONE29-91927
View Paper titled, Drop Analyses and Verification of the Spent Nuclear Fuel Transportation Cask Under Hypothetical Accident Conditions
Open the PDF for Drop Analyses and Verification of the Spent Nuclear Fuel Transportation Cask Under Hypothetical Accident Conditions in another window
Topics: Accidents, Spent nuclear fuels, Stress, Transportation systems
Proceedings Papers

Research on Establishing Efficient Scheduling System of Spent Fuel From Chinese Nuclear Power Plants

Jiqiang Su, Qun Liu, Honglin Zhang, Lei Shi, Hongjun Liu, Yanrui Li, Jian Hu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A062, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92757
https://doi.org/10.1115/ICONE29-92757
View Paper titled, Research on Establishing Efficient Scheduling System of Spent Fuel From Chinese Nuclear Power Plants
Open the PDF for Research on Establishing Efficient Scheduling System of Spent Fuel From Chinese Nuclear Power Plants in another window
Topics: Nuclear power stations, Spent nuclear fuels, Transportation systems
Proceedings Papers

Study of the Regular Pattern Between the Geometric Characteristics of Radioactive Package and Its External Radiation Dose Rate

Zhipeng Wang, Changwu Wang, Qian Sun, Yuhang Zhang, Lei Chen
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A066, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93641
https://doi.org/10.1115/ICONE29-93641
View Paper titled, Study of the Regular Pattern Between the Geometric Characteristics of Radioactive Package and Its External Radiation Dose Rate
Open the PDF for Study of the Regular Pattern Between the Geometric Characteristics of Radioactive Package and Its External Radiation Dose Rate in another window
Topics: Radiation (Physics), Radioactive substances, Safety, Transportation systems, Regulations, Containers, Accidents, Biomedicine, China, Pollution
Proceedings Papers

Safety Analysis for Transportation of Activated Secondary Neutron Source Assembly

Nanfeng Cao, Shouhai Yang, Enfei Xie, Shunping Jing
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A077, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93332
https://doi.org/10.1115/ICONE29-93332
View Paper titled, Safety Analysis for Transportation of Activated Secondary Neutron Source Assembly
Open the PDF for Safety Analysis for Transportation of Activated Secondary Neutron Source Assembly in another window
Topics: Manufacturing, Neutron sources, Safety, Storage, Transportation systems
Proceedings Papers

Analysis and Simulation in Rotating Rectifier in Brushless Excitation of Nuclear Power Plant

Zhang Xingzhen, Sun Hui, Zhao Yanjun, Shi Xianzuo
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A056, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92834
https://doi.org/10.1115/ICONE29-92834
View Paper titled, Analysis and Simulation in Rotating Rectifier in Brushless Excitation of Nuclear Power Plant
Open the PDF for Analysis and Simulation in Rotating Rectifier in Brushless Excitation of Nuclear Power Plant in another window
Topics: Excitation, Excitation systems, Nuclear power stations, Simulation, Bridges (Structures), Maintenance, Failure, Nuclear power, Accidents, Construction
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
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
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 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
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
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

A Sodium-Cooled Thermal-Spectrum Fission Battery

Patrick J. McDaniel, Charles Forsberg
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, V001T04A015, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65765
https://doi.org/10.1115/ICONE28-65765
View Paper titled, A Sodium-Cooled Thermal-Spectrum Fission Battery
Open the PDF for A Sodium-Cooled Thermal-Spectrum Fission Battery in another window
Topics: Batteries, Nuclear fission, Sodium, Heat, Neutrons, Uranium, Carbon, Data centers, Design, Economics
Proceedings Papers

Study on the Structural Evaluation and Optimization of Spent Nuclear Fuel Cask

Yuchen Hao, Jinhua Wang, Yue Li, Bin Wu, Haitao Wang, Tao Ma
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, V003T11A006, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63369
https://doi.org/10.1115/ICONE28-63369
View Paper titled, Study on the Structural Evaluation and Optimization of Spent Nuclear Fuel Cask
Open the PDF for Study on the Structural Evaluation and Optimization of Spent Nuclear Fuel Cask in another window
Topics: Nuclear power, Optimization, Spent nuclear fuels, Transportation systems
Proceedings Papers

Study on Radiation Dose Calculation of PWR Spent Fuel Storage and Transportation

Wen Yang, Xing Li, Jinrong Qiu, Lun Zhou
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A042, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64457
https://doi.org/10.1115/ICONE28-64457
View Paper titled, Study on Radiation Dose Calculation of PWR Spent Fuel Storage and Transportation
Open the PDF for Study on Radiation Dose Calculation of PWR Spent Fuel Storage and Transportation in another window
Topics: Containers, Pressurized water reactors, Radiation (Physics), Spent fuel storage, Spent nuclear fuels, Transportation systems
Proceedings Papers

Determining Airborne Release Fraction From DOT 7A Drums Exposed to a Thermal Insult

Hector Mendoza, Victor G. Figueroa, Walter Gill, Scott Sanborn
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A054, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16755
https://doi.org/10.1115/ICONE2020-16755
View Paper titled, Determining Airborne Release Fraction From DOT 7A Drums Exposed to a Thermal Insult
Open the PDF for Determining Airborne Release Fraction From DOT 7A Drums Exposed to a Thermal Insult in another window
Topics: Accidents, Filters, Fire, Liquid pool fires, Radiant heat, Radioactive substances, Safety, Stress, Testing, Thermogravimetry
Proceedings Papers

Uncertainty Quantification for the Development of Mechanistic Hydride Behavior Model for Spent Fuel Cladding Storage and Transportation

Edward M. Duchnowski, Seokbin Seo, Nicholas R. Brown
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A046, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16812
https://doi.org/10.1115/ICONE2020-16812
View Paper titled, Uncertainty Quantification for the Development of Mechanistic Hydride Behavior Model for Spent Fuel Cladding Storage and Transportation
Open the PDF for Uncertainty Quantification for the Development of Mechanistic Hydride Behavior Model for Spent Fuel Cladding Storage and Transportation in another window
Topics: Cladding systems (Building), Spent nuclear fuels, Storage, Transportation systems, Uncertainty quantification, Hydrogen, Diffusion (Physics), Fuels, Temperature profiles, Uncertainty
Proceedings Papers

Finite Element Analysis for Fuel Assembly Structural Behavior

Youngik Yoo, Kyounghong Kim, Kyongbo Eom, Seongki Lee, Jongsung Yoo
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A030, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81621
https://doi.org/10.1115/ICONE26-81621
View Paper titled, Finite Element Analysis for Fuel Assembly Structural Behavior
Open the PDF for Finite Element Analysis for Fuel Assembly Structural Behavior in another window
Topics: Finite element analysis, Fuels, Manufacturing, Accidents, Computer software, Failure mechanisms, Finite element model, Mechanical behavior, Mechanical testing, Radioactive substances
Proceedings Papers

Modular Boiling Water Reactor Concept

Liao Yi, Wang Cong, Chen Lei
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A009, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81196
https://doi.org/10.1115/ICONE26-81196
View Paper titled, Modular Boiling Water Reactor Concept
Open the PDF for Modular Boiling Water Reactor Concept in another window
Topics: Boiling water reactors, Cycles, Equilibrium (Physics), Blades, Fuels, Manufacturing, Nuclear fuel cycle, Safety, Computer software, Construction
Proceedings Papers

Research on the Effect of Grid Clamping Failure on Flow Elastic Stability and Vortex Shedding of Fuel Rod

Qi Huan-huan, Feng Zhi-peng, Jiang Nai-bin, Huang Qian, Huang Xuan
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A023, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81509
https://doi.org/10.1115/ICONE26-81509
View Paper titled, Research on the Effect of Grid Clamping Failure on Flow Elastic Stability and Vortex Shedding of Fuel Rod
Open the PDF for Research on the Effect of Grid Clamping Failure on Flow Elastic Stability and Vortex Shedding of Fuel Rod in another window
Topics: Failure, Flow (Dynamics), Fuel rods, Stability, Vortex shedding, Mode shapes, Flow-induced vibrations, Fuels, Irradiation (Radiation exposure), Manufacturing
Proceedings Papers

Design and Distortion Analysis of Thermal-Hydraulics Test Facility for the Fuel Transfer Tube

Mao Xi-dao, Liu Yang, Jia Hai-jun, Guo Qiang
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A007, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81834
https://doi.org/10.1115/ICONE26-81834
View Paper titled, Design and Distortion Analysis of Thermal-Hydraulics Test Facility for the Fuel Transfer Tube
Open the PDF for Design and Distortion Analysis of Thermal-Hydraulics Test Facility for the Fuel Transfer Tube in another window
Topics: Design, Fuels, Test facilities, Thermal hydraulics, Manufacturing, Flow (Dynamics), Safety, Cooling, Heat transfer, High temperature
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
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
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