Global ETD Search
Search theses and dissertations gathered from participating repositories worldwide. Every result links back to the library that holds it. No account is needed.
Results
Showing 1 to 8 of 8 for “"uranium dioxide (UO2)"”.
-
Thermodynamic and Thermochemical Investigation of Advanced Triso Coated Particle Fuels
… performed in this research utilized samples of Uranium Dioxide (UO2) and Uranium Dioxide (UO2) coated in a carbon seal coat followed by a zirconium carbide layer as an oxygen getter which would be representative of the advanced TRISO fuel kernel. For this research, techniques were developed …
-
Design and development of an automated pellet inspection system for nuclear fuel pellets
… for inline, non-destructive inspection of uranium dioxide (UO2) fuel pellets at production speeds of two pellets per second is presented. The system tests the surface of each cylindrical ceramic pellet using three different methods: laser 2D profile, laser surface roughness, and machine …
-
Fission gas transport and its interactions with irradiation-induced defects in lanthanum doped ceria
… (CeO2) was selected as a surrogate material for Uranium Dioxide (UO2) due to its many similar properties. Lanthanum (La) was chosen as a dopant in CeO2 to investigate the effect of impurities in a controlled manner. The presence of La in the CeO2 lattice introduces a predictable initial …
-
Design Space Exploration for Salt Cooled Reactor Systems
… FLiNaK and 3) NaF-ZrF4, and three fuel forms: 1) Uranium Dioxide (UO2), Uranium Carbide (UC), and Fully Ceramic Microencapsulated (FCM) fuel. A package of thermal-hydraulic operating domain search and design optimisation codes was created that can identify the optimum primary and secondary loop …
-
Molecular Dynamics Studies of Grain Boundary Mobilities in Metallic and Oxide Fuels
… light water reactors, the most common fuel is uranium dioxide (UO2), an oxide ceramic. There is also ongoing research examining uranium-based based metallic fuels, such as uranium-molybdenum (U-Mo) fuels with low uranium (U) enrichment for research reactors as part of a broader effort to combat …
-
Ion Beam Synthesis and Irradiation for Si-Based Photonic Materials and Nuclear Waste Management
This thesis describes investigations of material synthesis and interactions of radiation with materials using ion beam techniques, with applications in Si photonics and in nuclear waste management. Advances in electronics and telecommunications drive the need for Si-based optical materials (group …
-
Thermal conductivity of UO2 and U3O8 epitaxial layers damaged by ion irradiation
… measurements on both irradiated and unirradiated uranium oxides between 90 K and 658 K. The irradiation doses range from 5x10^13 argon ions/cm² to 2x10^16 Ar+/cm² at 2 MeV and room temperature. The main focus lies on 360 – 500 nm single crystal UO2 and U3O8 thin films grown on YSZ substrates. The …
-
DEVELOPMENT AND APPLICATIONS OF SCANNING ELECTROCHEMICAL MICROSCOPY (SECM)
… The corrosion behavior of non-stoichiometric UO2.002, spent nuclear waste, were investigated using SECM. Different corrosion rates on the surfaces their materials were discovered, and the mechanism was discussed. This information is very useful in determining the UO2 chemical dissolution …