Font Size: a A A
Keyword [Sodium-Cooled Fast Reactor]
Result: 1 - 20 | Page: 1 of 3
1. A Study On Core System Of New Type Nuclear Powered Propulsion Installation
2. The Preliminary Analysis Of Transmutation Characteristics Of Long-life High Level Radioactive Waste In Sodium-Cooled Fast Reactor
3. Preliminary Study Of Transient Safety Analysis Method In Sodium-cooled Fast Reactor
4. Practical Development Of Sodium Cooled Fast Reactor System Analysis Program
5. Research On Simulation Of Primary Coolant System Of Sodium Cooled Fast Reactor
6. Numerical And Experimental Study On Sodium Columnar Fire In Fast Reactor
7. Experimental Study On Sodium Fire In A Columnar Flow Of Sodium-cooled Fast Reactor
8. Real-time Simulation Model And Program Research Of Primary Coolant System Of Pool-type Sodium Cooled Fast Reactor
9. R&D On An Analytical Code For Flow Induced Vibration Of Heat Exchange Tube In Steam Generator Of Fast Reactor
10. Experimental Research On Sodium Columnar Fire Combustion And Suppression In Sodium-cooled Fast Reactor
11. Real-time Simulation Program Research Of Decay Heat Removal System In Pool-type Sodium Cooled Fast Reactor
12. Experiment Study On The Oxidation And Combustion Characteristics Of Sodium Droplets
13. Research On Simulation Model Of Sodium Fire In A Columnar Flow Of Sodium-cooled Fast Reactor
14. The Effects Of Number Of Blades And Pressure Chamber Parameters On The Performance Of The Secondary Circuit Coolant Pump For Sodium-Cooled Fast Reactor
15. Research And Promotion Of Cavitation Performance Of The Secondary Circuit Coolant Pump For Sodium-cooled Fast Reactor
16. Study On Magnetic Fluid Seal Under Radial Fretting Condition Of Sodium Cooled Fast Reactor
17. R&D On An Analytical Code For Flow Induced Vibration And Fretting Wear Of Heat Exchange Tube In Steam Generator Of Fast Reactor
18. Effects Of Zr And/or Ti Addition On The Nano-scale Particles In ODS Steels As The Fuel Cladding Materials Of Generation Iv Nuclear Fission Reactors
19. Modeling Of Fouling On Heat Transfer Tube In Steam Generators For Sodium-cooled Fast Reactor
20. Simulating Method And Analysis Of The Sodium-Water Reaction Accident In The Sodium-Cooled Fast Reactor
  <<First  <Prev  Next>  Last>>  Jump to