Fast Reactor - Globe Thesis

Keyword [Fast Reactor] Result: 161 - 180 \| Page: 9 of 10
161.	Research On Structure And Mechanical Properties Of Fuel Assembly For CiADS Lead Bismuth Fast Reactor
162.	Research On Hexagonal Nodal Space-Time Neutron Kinetics Computational Method And Application In Neutronics/Thermal-Hydraulics Coupling
163.	The Research On Simulation Program Development And Control Strategy Of Small Lead-bismuth Fast Reactor
164.	The Study Of Hexagonal Assembly Pin Power Reconstruction For Fast Reactor
165.	Research And Optimization Design Of Turbo-generator For Small Lead-bismuth Fast Reactor
166.	The Research On Automatic Start-up Control Technology Of Reactor System
167.	Research On Thermal-hydraulic Parameter Prediction Method Of The Small Lead–bismuth Fast Reactor Core Based On Adaptive RBF Neural Network
168.	Analysis Of Internal And External Characteristics Of Sodium Pump In The Primary Circuit Of The Fourth Generation Nuclear Fast Reactor During Coasting-down Transition Process
169.	Study On Bubble Distribution And Movement Behavior Of Lead Based Reactor Under SGTR Accident
170.	Numerical Simulation Of Shaft Jamming Of One Primary Pump In Fast Reactor
171.	Study On Comparation Of Different Arrangement Schemes For The Residual Heat Removal System In Sodium-cooled Fast Reactors Based On The FRTAC System Code
172.	Study On The Effect Of Positioning Mode On Thermal And Hydraulic Characteristics Of Lead Cooled Fast Reactor Fuel Assembly
173.	Experimental Study On Flow-induced Vibration Characteristics Of Control Rod Assemblies In Fast Reactors
174.	Three-dimensional Numerical Simulation On Thermal Characteristics In Pool-type Sodium-cooled Fast Reactor Under Reactivity Insertion Accident
175.	Design And Analysis Of Multi-purpose High Efficiency Energy Conversion System Matched With Offshore Floating Small Lead Cooled Fast Reactor
176.	Research On The Mechanism Of Argon Space For Flow The Heat Transfer Characteristics In The Main Vessel Of Fast Reactor And Optimization Of Thermal Design
177.	Research On Simulation And Phenomena Identification Ranking Table(PIRT) Quantification Of The EBR-Ⅱ Fast Reactor Loss Of Flow Accident Based On System Code FRTAC
178.	Theoretical Study On The Fluid-Structure Interaction Characteristics Of Coaxial Cylindrical Shells Under Free-Clamped Conditions And Its Application
179.	Study On Fluid-Structure Interaction Characteristics Of Primary Pump Support Cylinder And Thermal Shield
180.	Research On Simplified Method For Calculating Thermal Deformation Of The Pump Support In The Sodium-cooled Fast Reactor
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