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Jinhua Wang
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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
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Topics: Fuels, Gas cooled reactors, High temperature, Nuclear power, Transportation systems
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
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Topics: Design, Nuclear fuels, Transportation systems, Fuels, Metals, Safety, High temperature, Construction, Containers, 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
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Topics: Nuclear power, Optimization, Spent nuclear fuels, Transportation systems
Proceedings Papers

Study on the Impact Limiter Design in Spent Fuel Transfer Cask in Nuclear Power Plants

Yuchen Hao, Yue Li, Jinhua Wang, Bin Wu, Haitao Wang
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T05A006, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16157
https://doi.org/10.1115/ICONE2020-16157
View Paper titled, Study on the Impact Limiter Design in Spent Fuel Transfer Cask in Nuclear Power Plants
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Topics: Cushioning materials, Design, Nuclear power stations, Spent nuclear fuels
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
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Topics: Dust, Filtration, Graphite, Spent nuclear fuels, Transportation systems, Fuels, Gas cooled reactors, High temperature, Nuclear power, Pipelines
Proceedings Papers

Design of the Spent Fuel Storage Well of HTR-PM

Jinhua Wang, Bing Wang, Bin Wu, Yue Li
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T03A003, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60051
https://doi.org/10.1115/ICONE24-60051
View Paper titled, Design of the Spent Fuel Storage Well of HTR-PM
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Topics: Design, Spent fuel storage, Spent nuclear fuels, Storage, Fuels, Safety, Wells, Heat, Accidents, High temperature
Proceedings Papers

CFD Simulation of Natural Ventilation Performance of the Interim Region in Spent Fuel Dry-Storage System of HTR-PM

Bing Wang, Jinhua Wang, Haijun Jia
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T10A010, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60238
https://doi.org/10.1115/ICONE24-60238
View Paper titled, CFD Simulation of Natural Ventilation Performance of the Interim Region in Spent Fuel Dry-Storage System of HTR-PM
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Topics: Computational fluid dynamics, Simulation, Spent nuclear fuels, Storage, Ventilation, Heat, Wells, Accidents, Bifurcation, Flow (Dynamics)
Proceedings Papers

Numerical Analysis of the Residual Heat Removal for the Spent Fuel Canister of HTR-PM in Fuel Loading Process

Jinhua Wang, Bing Wang, Bin Wu
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T10A006, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30284
https://doi.org/10.1115/ICONE22-30284
View Paper titled, Numerical Analysis of the Residual Heat Removal for the Spent Fuel Canister of HTR-PM in Fuel Loading Process
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Topics: Fuels, Heat, Numerical analysis, Spent nuclear fuels, Temperature, Ventilation, Accidents, Safety, Boron, Failure
Proceedings Papers

Stress Concentration Factor Calculation for the Hooks in Lifting Appliance of Spent Fuel Well Cover

Xiang Liu, Yue Li, Jinhua Wang, Bin Wu
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A002, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30272
https://doi.org/10.1115/ICONE22-30272
View Paper titled, Stress Concentration Factor Calculation for the Hooks in Lifting Appliance of Spent Fuel Well Cover
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Topics: Spent nuclear fuels, Stress concentration, Corners (Structural elements), Fatigue life, Finite element methods, High temperature, Numerical analysis, Saint-Venant's principle, Wells
Proceedings Papers

Electromagnetic Self-Locking Device for Air Cylinders in Spent Fuel Storage System of Pebble-Bed High Temperature Gas-Cooled Reactor

Bin Wu, Jinhua Wang, Yue Li, Jiguo Liu
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A047, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16342
https://doi.org/10.1115/ICONE21-16342
View Paper titled, Electromagnetic Self-Locking Device for Air Cylinders in Spent Fuel Storage System of Pebble-Bed High Temperature Gas-Cooled Reactor
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Topics: Pneumatic cylinders, Spent fuel storage, Very high temperature reactors, Locks (Waterways), Compressed air, Cylinders, Machinery, Spent nuclear fuels, Temperature, Accidents
Proceedings Papers

Numerical Analysis of the Residual Heat Removal for the Spent Fuel Storage Tank of HTR-10

Jinhua Wang, Bing Wang, Bin Wu, Jiguo Lui
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A005, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15053
https://doi.org/10.1115/ICONE21-15053
View Paper titled, Numerical Analysis of the Residual Heat Removal for the Spent Fuel Storage Tank of HTR-10
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Topics: Heat, Numerical analysis, Spent fuel storage, Spent nuclear fuels, Temperature, Ventilation, Storage, Fuels, Gas cooled reactors, High temperature