Sodium-Cooled Fast Reactor - Globe Thesis

Keyword [Sodium-Cooled Fast Reactor] Result: 21 - 40 \| Page: 2 of 3
21.	Simulation Of 600MW Sodium-cooled Fast Reactor Steam Generator
22.	Design And Experimental Study Of Magnetorheological Fluid Seal Structure
23.	Research On Nuclear Core Thermal Performance Of Fast Reactor Under Typical Accident Conditions
24.	Experimental Study On Sodium Droplet Combustion Rate And The Spatial Temperature Distribution Characteristics
25.	Research On FCI Characteristics Of Sodium Cooled Fast Reactor Under Severe Accident
26.	Numerical Investigation Of Thermal-Hydraulic Characteristics Of Sodium Cooled Fast Reactor Once-through Steam Generator With Coupled Heat Transfer From Primary To Secondary Side
27.	Research On Anti-interference Of Core Measurement System Of Pool-type Sodium-cooled Fast Reactor
28.	Modeling And Simulation Of The Moisture Separator And Reheater System In Soda-cooled Fast Reactor
29.	Effects of fuel type on the safety characteristics of a sodium cooled fast reactor
30.	Design and Analysis of Sodium-cooled Fast Reactor Systems for Nuclear Waste Minimizatio
31.	Research On The Fragmentation Characteristics And Mechanisms Of Molten Core Material-liquid Sodium Interaction In Sodium-cooled Fast Reactor
32.	Flow-characteristics Investigation On Core-assembly Abnormal Structure Of Sodium-cooled Fast Reactor
33.	Research On Uncertainty Analysis Of Fast Reactor Based On High-precision Random Number Sampling Of Correlated Variables
34.	Core Thermal Calculation Of Fast Reactor Refueling Process Based On Subchannel Program
35.	Experimental Research And Numerical Simulation On Flow Distribution Characteristics Of Seven-Box Assembly In Small Grid Plate Of Fast Reactor
36.	Numerical Simulation And Analysis Of Sodium-cooled Fast Reactor Fuel Assembly
37.	Development And Verification Of Sub-channel Analysis Code For Sodium-cooled Fast Reactor Under Nature Cycle
38.	Research On Core Flow Distribution Of Natural Circulation Sodium-cooled Fast Reactor
39.	Research On Brayton Cycle Properties Of Helium-Xenon Mixed Working Fluid Based On Space Nuclear Power System
40.	Development Of Hydraulic Design Code For Fast Reactor Hydraulically Suspended Passive Shutdown Subassembly
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