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Showing 1 to 20 of 30 for “"Uranium Dioxide"”.
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Reduction of Solid Uranium Dioxide in Calcium Salts
… cooperation, 2014) has pointed out is to utilize uranium resources to the maximum and recycle spent nuclear fuel through burn-up in the Generation IV reactor designs, one of which is the molten salt reactor (MSR). Therefore, the MSR can use the spent nuclear fuel as a fresh fuel when the actinides …
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Dry process fluorination of uranium dioxide using ammonium bifluoride
… of various unit operations for fluorination of uranium dioxide. The objective was to prepare ammonium uranium fluoride double salts from uranium dioxide and ammonium bifluoride, then decompose these salts to uranium tetrafluoride through heating to temperatures near 425 °C in either a fluidized …
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Uranium-Dioxide Sintering Kinetics and Mechanisms Under Controlled Oxygen Potentials
Made available in DSpace on 2014-12-14T15:24:02Z (GMT). No. of bitstreams: 1 7913424.pdf: 9172220 bytes, checksum: 1e497a69c1f365c6aa0b36ea5ff827e4 (MD5) Previous issue date: 1978
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Radiation-enhanced diffusion of oxygen-18 in uranium dioxide thin films
Anion radiation enhanced diffusion (RED) and thermal diffusion of a buried 18O tracer layer in thin film UO2 was measured using Secondary-Ion Mass Spectroscopy (SIMS). Thin films were grown using a dedicated magnetron sputtering chamber. Samples were irradiated with 1.8 MeV Kr+ over a temperature …
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Molecular dynamic simulation of xenon bubble re-solution in uranium dioxide
This is a comprehensive study of two mechanisms of fission gas bubble re-solution in UO2 by molecular dynamics (MD) simulations: homogeneous re-solution and heterogeneous re-solution. For the homogeneous mechanism, a hybrid approach is employed whereby Monte Carlo (MC) simulations are used to …
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Equilibrium studies of the uranium dioxide - carbon and neodymium sesquioxide - carbon systems
Thesis (M.S.)--Michigan State University. Dept. of Chemistry, 1963
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Elastic and Anelastic Response in a Polycrystalline System Uranium-Dioxide - Plutonium-Dioxide
Made available in DSpace on 2014-12-10T17:32:38Z (GMT). No. of bitstreams: 1 7000941.pdf: 4902619 bytes, checksum: 490cb54ed80a6e963193f7cdacdce814 (MD5) Previous issue date: 1969
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Uranium dioxide and urania-thoria fuel cores for the UTR-10 reactor
… transient behavior have been made for proposed uranium dioxide and urania-thoria fuel cores for the Virginia Polytechnic Institute UTR-10 Reactor.
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Computer simulation of defect evolution in lanthanum doped cerium dioxide under irradiation
Uranium dioxide is the most common choice for fuel material in fission reactors. However, the radioactivity of uranium limits the experimental approaches on the oxide fuel material. Fortunately, cerium dioxide has been shown to be a good surrogate of uranium dioxide in many aspects. To better …
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Alteration mechanisms of spent nuclear fuel and characterization of potential uranium secondary phases.
… of said alteration. The relative abundance of uranium as an energy resource, coupled with the high costs of spent nuclear fuel reprocessing and the associated risks of nuclear proliferation make a strong case for direct disposal of SNF in deep underground geological disposal facilities. The …
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Dissolution of mixed uranium thorium oxides under geological disposal conditions
Uranium dioxide alone offers enough complexity to provide the subject matter for 50 years of dissolution studies, not least due to uranium’s redox sensitivity and the orders of magnitudes between the solubility of U(IV) and U(VI). The addition of plutonium dioxide as a solid solution opens up a …
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A new age of fuel performance code criteria studied through advanced atomistic simulation techniques
… the effects of irradiation on metallic uranium and uranium dioxide ceramic fuels, or any material, must start with the nature of radiation damage on the atomic level. The atomic damage displacement results in a multitude of defects that influence the fuel performance. Nuclear reactions …
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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 …
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The effect of radiation damage by fission fragments on the structural stability and dissolution of the UO2 fuel matrix
… structural integrity and matrix dissolution of uranium dioxide in water. Radiation damage similar to fission damage was created by irradiating bulk undoped and doped ‘SIMFUEL’ disks of UO2, undoped bulk CeO2 and thin films of UO2 and CeO2 with high energy Xe and U ions. The UO2 thin films, with …
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Molecular Dynamics Studies of Anisotropy in Grain Boundary Energy and Mobility in UO₂
… is examined for the light water reactor fuel uranium dioxide (UO₂) by molecular dynamics simulations. The dependence of these properties on both misorientation angle and rotation axis is studied. The anisotropy in grain boundary energy is found to be insignificant in UO₂. However, grain …
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Magnetic surface relaxation and reconstruction phenomena in frustrated magnetic systems
… state configuration of a semi-infinite system of uranium dioxide, an FCC triple-q magnet, show a solitonic solution corresponding to this relaxation. Fluctuations of this domain wall are considered in order to explain the unusual disordering observed experimentally in the near-surface region at a …
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Thermal hydraulic analysis of hydride fuels in BWR's
… nuclear reactors. All results hold equally for uranium dioxide as well as hydride fuel since the design limits imposed, critical heat flux, maximum flow velocity and pressure drop constrain only pin array geometry and diameter. It is shown that applicable uranium oxide and hydride fuel limits …
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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 …
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Increasing Cermet Fuel Thermal Margin with Thoria for Nuclear Thermal Propulsion
… the fuel margin to melting point. A thorium-dioxide stabilized, high-assay low enriched uranium (HALEU) tungsten-uranium dioxide (W-UO2) CERMET fueled nuclear thermal propulsion (NTP) concept was produced based on the Space Capable Cryogenic Thermal Engine (SCCTE) reactor1. Axial fuel thoria …
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