Fast Reactor - Globe Thesis

Keyword [Fast Reactor] Result: 141 - 158 \| Page: 8 of 8
141.	Flow And Heat Transfer Calculation Of A Compact Heat Exchanger In Lead Cooled Fast Reactor
142.	Calculation Of Flow And Hfat Transfer Of Steam Generator In Sodium-cooled Fast Reactor
143.	Experimental Study On Flow-induced Vibration Characteristics Of Fast Reactor Fuel Assembly
144.	Numerical Verification On Similarity Theory Of Fluid-Structure Coupled Dynamics For Fast Reactor Vessel And Internals
145.	3D Simulation On Transient Characteristics Of Fluid In The Cold And Hot Pools Of Pool-typed Sodium-cooled Fast Reactor Under Loss Of Steam Generator Feedwater Accident
146.	Study On Fluid-Solid Thermal Coupling Characteristics Of Center Measuring Column In Fast Reactor Under Thermal Shock
147.	Thermal Fatigue Analysis And Study On Thermal-Fluid-structure Interaction Characteristic Of Central Measurement Column In Fast Reactor Under Thermal Striping
148.	Molecular Dynamics Study On The Related Problems Of Pb-Fe-O System In Solid Phase Oxygen Control Of Lead-Cooled Fast Reactor
149.	Research On Flow Charateristics Of Wire-wrapped Rod Bundles Fuel Assemblies In Fast Reactor
150.	Numerical-simulation Optimization Of Wire-wrapped Fuel Bundle Of Sodium-cold Fast Reactor And Its Application In Blockage Accidents
151.	Research On Three Dimensional Transient Thermal And Hydraulic Characteristics Of Pool-type Sodium-cooled Fast Reactor Under Asymmetric Conditions Of One Primary Pump Trip Superimposing Loss Of Off-site Power
152.	Numerical Analysis Of Flow And Heat Transfer In The Natural Cycle Experiment Section Of A Sodium Cold Fast Reactor(SFR)
153.	Numerical Analysis Of Natural Circulation Flow And Heat Transfer Of 37 Rods Sodium Cooled Fast Reactor Experimental Components
154.	Numerical Investigation On Heat Transfer Of Spent Fuel Assembly Of Sodium Cooled Fast Reactor In Argon Atmosphere
155.	Investigation On The Operation Characterustics Of 100kWe Brayton Cycle System Coupled With Lithium Cooled Space Fast Reactor
156.	Experimental Study On Heat Dissipation Of Sodium Fast Reactor Spent Fuel Assembly During In-containment Transfer
157.	Verification And Validation Of System Analysis Code FASYS For Sodium-cooled Fast Reactor
158.	Study On Core Layout Schemes And Control Methods Of A Lead Cooled Fast Reactor Based On Thorium And Plutonium Mixed Fuel
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