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Keyword [burnup]
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21. Numerical Simulating Studies On PWR's Capability Of Producing WGPu
22. Research On The High-precision Burnup Calculation Methods And Thorium-Uranium Fuel Breeding For The Liquid-Fueled Molten Salt Reactor
23. Study On Neutronics Performance Of Pebble In Thorium-based Fluoride Salt-cooled High Temperature Reactor
24. Nuclear Data Sensitivity And Uncertainty Analysis In The Burnup Calculation Based On RMC Code
25. Research On Coupling Schemes Of Burnup Calculation And On-The-Fly Therment On Thermal Scattering Based On RMC
26. Study On Radioactive Source Term Of Liquid Fuel Molten Salt Reactor
27. Development And Application Of Neutronic And Thermal-Hydraulic Coupling Code For Long Life Chlorine-cooled Fast Reactor
28. The Effects Of Transmutation Of MA On PWR Fuel Cycle
29. The Effect Of Transmutation Minor Actinide On PWR Temperature Coefficient
30. Research On Making Continuous Energy Point Cross Section Library And Burnup Library Of Key Nuclides For Lead-based Fast Reactor
31. Burnup Of Minor Actinides Transmutation In The Lead-Cooled Fast Reactor
32. Coupled Neutronics And Thermal-Hydraulics Simulation Methods For Nuclear Reactors
33. Development of the MCNPX depletion capability: A Monte Carlo linked depletion method that automates the coupling between MCNPX and CINDER90 for high fidelity burnup calculations
34. A feasibility and optimization study to determine cooling time and burnup of advanced test reactor fuels using a nondestructive technique
35. Fuel Burnup Simulation and Analysis of the Missouri S&T Reacto
36. Development of burnup dependent fuel rod model in COBRA-TF
37. Research On Calculation Of Source Term In Spent Fuel Reprocessing Equipment
38. Phase Field Simulation Of Fracture Behavior Of Plate Dispersed Nuclear Fuel
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