neutronics - Globe Thesis

Keyword [neutronics] Result: 21 - 40 \| Page: 2 of 5
21.	Radiological Analyzation Of Spallation Target Production For An Accelerator-driven System
22.	A Preliminary Study On The Neutronics And The Heat Releasing Rate Characteristics Of ~99(Tc) Transmutation Target
23.	Study Of The IMF Fuelâ€™s Neutronics Characteristic Which Is Used For Pressurized Water Reactor To Transmute MA
24.	Research On Neutronics/Thermal-hydraulics Coupling Of The Thorium Molten Salt Reactor Based On MCNPX And Fluent
25.	Preliminary Calculation And Analysis Of Activation For CFETR Blanket
26.	The Design And Neutronics Analysis Of CFETR WCCB Experimental Mock-up
27.	Research Of GPU-accelerated Core Transient Analysis Method For Pebble-bed Fluoride Salt Cooled High Temperature Reactor
28.	Research On Neutronics And Thermal Hydraulic And Preliminary Study On Safety Characteristics Of Molten Salt Reactor
29.	Experimental Neutronics Study On The Zero-power Coupling Device Of The Spallation Target And Reactor
30.	Research On Neutronics/Thermal-coupled Systematic Analysis Technology For Liquid Metal Cooled Fast Breeder Reactor
31.	Research On Reactor Noise In A Molten Salt Reactor
32.	Development Of Interfaces For Fusion Neutronics Codes And Their Application
33.	Neutronics Study On Subcritical Travelling Wave Reactor Driven By Gas Dynamic Trap Fusion Facility
34.	Study On Neutronics/Thermal Hydraulics Coupling In Typical Channel Of Subcooled Boiling Flow Under Rolling Condition
35.	A Study On Neutronics Characteristics For The Core Of Thorium Molten Salt Reactor
36.	Coupled Neutronic And Thermal-hydraulic Analysis Of TMSR-SF1 At Steady State
37.	Preliminary Physical Design And Optimization Of Burnup For Small Natural Circulation Lead Cooled Fast Reactor(SNCLFR-100)
38.	Development And Application Of Neutronics-thermal Hydraulics Coupling Interface For CFETR Integration Design Platform
39.	Neutronic Calculation And Analysis Of CFETR Helium Cooled Ceramic Breeder Blanket
40.	The Development Of A Thermal Hydraulic Analysis Code Of Nuclear Reactor Under Ocean Conditions
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