sodium-cooled fast reactor - Globe Thesis

Keyword [sodium-cooled fast reactor] Result: 41 - 57 \| Page: 3 of 3
41.	Experimental Study On The Surface Reaction Characteristics Of Liquid Sodium-water Vapor In Sodium-cooled Fast Reactor
42.	Calculation Of Flow And Hfat Transfer Of Steam Generator In Sodium-cooled Fast Reactor
43.	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
44.	Numerical-simulation Optimization Of Wire-wrapped Fuel Bundle Of Sodium-cold Fast Reactor And Its Application In Blockage Accidents
45.	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
46.	Numerical Analysis Of Flow And Heat Transfer In The Natural Cycle Experiment Section Of A Sodium Cold Fast Reactor(SFR)
47.	Numerical Analysis Of Natural Circulation Flow And Heat Transfer Of 37 Rods Sodium Cooled Fast Reactor Experimental Components
48.	Numerical Investigation On Heat Transfer Of Spent Fuel Assembly Of Sodium Cooled Fast Reactor In Argon Atmosphere
49.	Verification And Validation Of System Analysis Code FASYS For Sodium-cooled Fast Reactor
50.	The Research On Automatic Start-up Control Technology Of Reactor System
51.	Analysis Of Internal And External Characteristics Of Sodium Pump In The Primary Circuit Of The Fourth Generation Nuclear Fast Reactor During Coasting-down Transition Process
52.	Numerical Simulation Of Shaft Jamming Of One Primary Pump In Fast Reactor
53.	Study On Comparation Of Different Arrangement Schemes For The Residual Heat Removal System In Sodium-cooled Fast Reactors Based On The FRTAC System Code
54.	Three-dimensional Numerical Simulation On Thermal Characteristics In Pool-type Sodium-cooled Fast Reactor Under Reactivity Insertion Accident
55.	Research On Simplified Method For Calculating Thermal Deformation Of The Pump Support In The Sodium-cooled Fast Reactor
56.	Joint Cross-Scale Simulation Study Of The Main Cooling System Of A Sodium-Cooled Fast Reactor
57.	Numerical Analysis Of Hydraulic Characteristic Of Wire-wrapped Rod Bundle Assembly Under Low Reynolds Number
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