Sodium-cooled - Globe Thesis

Keyword [Sodium-cooled] Result: 21 - 40 \| Page: 2 of 3
21.	Modeling Of Fouling On Heat Transfer Tube In Steam Generators For Sodium-cooled Fast Reactor
22.	Simulating Method And Analysis Of The Sodium-Water Reaction Accident In The Sodium-Cooled Fast Reactor
23.	Simulation Of 600MW Sodium-cooled Fast Reactor Steam Generator
24.	Design And Experimental Study Of Magnetorheological Fluid Seal Structure
25.	Research On Nuclear Core Thermal Performance Of Fast Reactor Under Typical Accident Conditions
26.	Experimental Study On Sodium Droplet Combustion Rate And The Spatial Temperature Distribution Characteristics
27.	Research On FCI Characteristics Of Sodium Cooled Fast Reactor Under Severe Accident
28.	Numerical Investigation Of Thermal-Hydraulic Characteristics Of Sodium Cooled Fast Reactor Once-through Steam Generator With Coupled Heat Transfer From Primary To Secondary Side
29.	Research On Anti-interference Of Core Measurement System Of Pool-type Sodium-cooled Fast Reactor
30.	Modeling And Simulation Of The Moisture Separator And Reheater System In Soda-cooled Fast Reactor
31.	Effects of fuel type on the safety characteristics of a sodium cooled fast reactor
32.	Design and Analysis of Sodium-cooled Fast Reactor Systems for Nuclear Waste Minimizatio
33.	Used nuclear fuel actinide management in a sodium-cooled heterogeneous innovative burner reactor
34.	Research On The Fragmentation Characteristics And Mechanisms Of Molten Core Material-liquid Sodium Interaction In Sodium-cooled Fast Reactor
35.	Flow-characteristics Investigation On Core-assembly Abnormal Structure Of Sodium-cooled Fast Reactor
36.	Research On Uncertainty Analysis Of Fast Reactor Based On High-precision Random Number Sampling Of Correlated Variables
37.	Core Thermal Calculation Of Fast Reactor Refueling Process Based On Subchannel Program
38.	Experimental Research And Numerical Simulation On Flow Distribution Characteristics Of Seven-Box Assembly In Small Grid Plate Of Fast Reactor
39.	Numerical Simulation On Asymmetrical Three-Dimensional Thermal Characteristics Of Sodium Pool Under A Primary Pump Stuck Accident In CEFR
40.	Numerical Simulation And Analysis Of Sodium-cooled Fast Reactor Fuel Assembly
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