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Keyword [Fast Reactor]
Result: 121 - 140 | Page: 7 of 8
121. Flow-characteristics Investigation On Core-assembly Abnormal Structure Of Sodium-cooled Fast Reactor
122. Research On System Design And Characteristics Of Supercritical CO2 Power Cycle Based On Lead-cooled Fast Reactor
123. Research On Structural Design For Cladding For Central Measuring Shroud Against Thermal Shock In A Fast Reactor
124. Small Lead-Cooled Fast Reactor Core Thermal-Hydraulics And Neutronics Coupling Research And Application
125. Study On The Flow Characteristics Of Wire-wrapped Fuel Bundle Channel In A Lead-cooled Fast Reactor
126. Research On Uncertainty Analysis Of Fast Reactor Based On High-precision Random Number Sampling Of Correlated Variables
127. Research On Reconstruction And Linearization Of Resonance Cross Section And Fabrication Method Of Ultrafine Energy Group Cross Section Of Fast Reactor
128. Core Thermal Calculation Of Fast Reactor Refueling Process Based On Subchannel Program
129. Effect Of Minor Actinide Transmutation On Safe Operation Of The Lead-cooled Fast Reactor
130. Experimental Research And Numerical Simulation On Flow Distribution Characteristics Of Seven-Box Assembly In Small Grid Plate Of Fast Reactor
131. Numerical Simulation And Experimental Verification Of Coolant Temperature Oscillation At Core Outlet Of Fast Reactor
132. Research On Subchannel Analysis Method Of Lead-based Fast Reactor Fuel Assembly With Wire Spacers For CiADS
133. Investigation On Flow And Heat Transfer Models Of A LBE Cooled Fast Reactor Helical Coiled Tube Once Through Steam Generator Based On Two-fluid Model
134. Numerical Simulation And Analysis Of Sodium-cooled Fast Reactor Fuel Assembly
135. Development And Verification Of Sub-channel Analysis Code For Sodium-cooled Fast Reactor Under Nature Cycle
136. Research On Core Flow Distribution Of Natural Circulation Sodium-cooled Fast Reactor
137. Research On Brayton Cycle Properties Of Helium-Xenon Mixed Working Fluid Based On Space Nuclear Power System
138. Development Of Hydraulic Design Code For Fast Reactor Hydraulically Suspended Passive Shutdown Subassembly
139. Experimental Study On The Surface Reaction Characteristics Of Liquid Sodium-water Vapor In Sodium-cooled Fast Reactor
140. Study On Particle(ISPH)-Grid(FVM) Coupling Method Based On FCI In Lead Fast Reactor
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