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.
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Showing 1 to 9 of 9 for “"Mixed oxide fuel"”.
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Fuel performance modeling of high burnup mixed oxide fuel for hard spectrum LWRs
According to the future of the nuclear fuel cycle study at MIT, a reactor with a conversion ratio around one can achieve desired objectives in the long-term sustainability of uranium and reduction of transuranic wastes. This finding relaxes the need for sodium fast reactors (SFR) in a closed-loop …
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Thorium-based mixed oxide fuel in a pressurized water reactor: A feasibility analysis with MCNP
… dissertation investigates techniques for spent fuel monitoring, and assesses the feasibility of using a thorium-based mixed oxide fuel in a conventional pressurized water reactor for plutonium disposition. Both non-paralyzing and paralyzing dead-time calculations were performed for the Portable …
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Modelling of thermo-mechanical and irradiation behavior of metallic and oxide fuels for sodium fast reactors
… to model the irradiation behavior of metal and oxide fuels in sodium cooled fast reactors is developed. Modeling capability was enhanced by adopting a non-empirical mechanistic approach to the extent possible, so that to increase the ability to extrapolate the existing database with a reasonable …
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Sensitivity analysis of nuclear fuel cycle transitions
The present United States nuclear fuel cycle faces challenges that hinder the expansion of nuclear energy technology. The U.S. Department of Energy identified four classes of nuclear fuel cycle options the U.S could transition to, which would overcome these challenges and make nuclear energy …
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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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Thermomechanical analysis of innovative nuclear fuel pin designs
… reactor is to change the solid cylindrical fuel to Internally and Externally Cooled (I&EC) annular fuel, and adjust the flow and the core inlet coolant temperature. The switch to annular fuel allows for a 20% increase in core power density without changing the assembly size or the control …
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Plutoniumfingerabdrücke und Brennstoffzyklusstudien für thermische Reaktorkonzepte
… for thermal reactor concepts and different fuel cycles are investigated by using the reactor simulation code VSOP. The fuel cycles of LEU (Low-Enriched Uranium), MOX (Mixed Oxide Fuel), ThHEU (Thorium High-Enriched Uranium) and ThPu (Thorium-Plutonium) as well as the reactor concepts of LWR, …
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Advanced nodal methods for MOX fuel analysis
… grade plutonium is to bum the plutonium as mixed oxide fuel (MOX) in commercial light water reactors (LWR's). The introduction of MOX fuel into LWR's poses several challenges for the reactor analyst. The spectrum difference between MOX and U02 assemblies creates a large thermal flux gradient …
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Monitoring under the Plutonium Management and Disposition Agreement : the prospects of antineutrino detection as an IAEA verification metric for the disposition of weapons-grade plutonium in the United States
… MT of excess military plutonium in the form of mixed oxide fuel (MOX) in nuclear power reactors. One of the major issues of concern associated with this agreement relates to the verification measures that will be implemented to ensure actual WGPu disposition. Additionally, despite a commitment …