fast reactor - Globe Thesis

Keyword [fast reactor] Result: 61 - 80 \| Page: 4 of 10
61.	Preliminary Physical Design And Optimization Of Burnup For Small Natural Circulation Lead Cooled Fast Reactor(SNCLFR-100)
62.	Experimental Study On Sodium Fire In A Columnar Flow Of Sodium-cooled Fast Reactor
63.	Transmutation Characteristics Of MA In Lead-cooled Fast Reactor
64.	Shielding Research On Main Container Of Lead Cooled Fast Reactor
65.	Real-time Simulation Model And Program Research Of Primary Coolant System Of Pool-type Sodium Cooled Fast Reactor
66.	Real-Time Simulation Research On Experimental Fast Reactor Core Physics
67.	R&D On An Analytical Code For Flow Induced Vibration Of Heat Exchange Tube In Steam Generator Of Fast Reactor
68.	Simulation Of Chinese Experimental Fast Reactor Core Systems
69.	Development Of Subchannel Analysis Code For Lead Cooled Fast Reactor Subassembly
70.	Experimental Research On Sodium Columnar Fire Combustion And Suppression In Sodium-cooled Fast Reactor
71.	Real-time Simulation Program Research Of Decay Heat Removal System In Pool-type Sodium Cooled Fast Reactor
72.	Analysis Of Burnup Performance For A Molten Chloride Salt Fast Reactor Based On Thorium Fuel
73.	Experiment Study On The Oxidation And Combustion Characteristics Of Sodium Droplets
74.	Research On Simulation Model Of Sodium Fire In A Columnar Flow Of Sodium-cooled Fast Reactor
75.	Study And Application Of SPH On FCI Resulting From Fast Reactor Core Disruptive Accident
76.	The Effects Of Number Of Blades And Pressure Chamber Parameters On The Performance Of The Secondary Circuit Coolant Pump For Sodium-Cooled Fast Reactor
77.	Research And Promotion Of Cavitation Performance Of The Secondary Circuit Coolant Pump For Sodium-cooled Fast Reactor
78.	Physical Performance Study For A Small Modular Breed And Burn Fast Reactor Based On Th-U Fuel Cycle
79.	Optimization Design And Reliability Analysis Of LBE-cooled Fast Reactor Main Coolant Pump
80.	Conceptual Design And Efficiency Optimization Of Power Generation System For Lead-based Nuclear Energy System
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