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CFD analysis of spent fuel dry cask storage system for High burnup nuclear fuel
Yogesh Fulpagare, Tao Yao, Chao Jen Li,
Chi Chuan Wang
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機械工程學系
研究成果
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引文 斯高帕斯(Scopus)
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Keyphrases
Nuclear Fuel
100%
Canister
100%
Computational Fluid Dynamics Analysis
100%
Spent Fuel
100%
Dry Cask Storage System
100%
High Burnup
100%
Heat Dissipation Performance
66%
Maximum Temperature
66%
Thermal Fluid
66%
Fuel Assembly
66%
Ideal Gas Model
66%
Sensitivity Analysis
33%
High Temperature
33%
Temperature Distribution
33%
2D Model
33%
Reactor
33%
Thermal Conditions
33%
Thermal Power
33%
3D Model
33%
Natural Convection
33%
Engineering Technology
33%
Nuclear Safety
33%
Cylindrical Structure
33%
Computational Fluid Dynamics
33%
Storage Container
33%
Outer Diameter
33%
Internal Temperature
33%
Flow Field Characteristics
33%
Internal Flow
33%
Nuclear Waste
33%
Decay Heat
33%
Spent nuclear Fuel
33%
Computational Fluid Dynamics Simulation
33%
Actual Situation
33%
Heat Ratio
33%
Abnormal Results
33%
Westinghouse
33%
Three-dimensional Computational Fluid Dynamics
33%
Fluid Phenomena
33%
Dry Cask Storage
33%
Dry Storage Cask
33%
Boussinesq Approximation
33%
Stochastic Optical Reconstruction Microscopy (STORM)
33%
Pressurized Water Reactor Fuel Assembly
33%
Shear Stress Transport Turbulence Model
33%
Air Outlet Temperature
33%
Porous Medium Assumption
33%
Welded Stainless Steel
33%
Fuel Components
33%
Distribution Fields
33%
Engineering
Computational Fluid Dynamics
100%
Storage System
100%
Fuel Assembly
100%
Spent Fuels
100%
Burnup
100%
Nuclear Fuel
100%
Heat Losses
66%
Maximum Temperature
66%
Gas Model
66%
Ideal Gas
66%
Stainless Steel
33%
Flowrates
33%
Boussinesq's Hypothesis
33%
Natural Convection
33%
Nuclear Safety
33%
Cylindrical Structure
33%
Outer Diameter
33%
Outlet Temperature
33%
Internal Flow
33%
Thermal Fluid
33%
Sensitive Factor
33%
Pressurized Water Reactor
33%
Spent Nuclear Fuel
33%
Flow Distribution
33%
Temperature Distribution
33%
Decay Heat
33%