Sodium-cooled - Globe Thesis

Keyword [Sodium-cooled] 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.	Applicability Research And Application Of The System Safety Analysis Code On Supercritical Water-cooled Reactors And Sodium-cooled Fast Reactors
8.	Applicability Assessment For SuperMC Code In Neutronic Analysis Of Advanced Sodium-cooled Reactors
9.	Experimental Study On Sodium Fire In A Columnar Flow Of Sodium-cooled Fast Reactor
10.	Real-time Simulation Model And Program Research Of Primary Coolant System Of Pool-type Sodium Cooled Fast Reactor
11.	R&D On An Analytical Code For Flow Induced Vibration Of Heat Exchange Tube In Steam Generator Of Fast Reactor
12.	Experimental Research On Sodium Columnar Fire Combustion And Suppression In Sodium-cooled Fast Reactor
13.	Real-time Simulation Program Research Of Decay Heat Removal System In Pool-type Sodium Cooled Fast Reactor
14.	Experiment Study On The Oxidation And Combustion Characteristics Of Sodium Droplets
15.	Research On Simulation Model Of Sodium Fire In A Columnar Flow Of Sodium-cooled Fast Reactor
16.	The Effects Of Number Of Blades And Pressure Chamber Parameters On The Performance Of The Secondary Circuit Coolant Pump For Sodium-Cooled Fast Reactor
17.	Research And Promotion Of Cavitation Performance Of The Secondary Circuit Coolant Pump For Sodium-cooled Fast Reactor
18.	Study On Magnetic Fluid Seal Under Radial Fretting Condition Of Sodium Cooled Fast Reactor
19.	R&D On An Analytical Code For Flow Induced Vibration And Fretting Wear Of Heat Exchange Tube In Steam Generator Of Fast Reactor
20.	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
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