Graduate Thesis Or Dissertation
 

High uranium density dispersion fuel for the reduced enrichment of research and test reactors program

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https://ir.library.oregonstate.edu/concern/graduate_thesis_or_dissertations/pg15bk48v

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  • This work describes the fabrication of a high uranium density fuel for the Reduced Enrichment of Research and Test Reactors Program. In an effort to decrease the use of high enriched uranium in research and test reactors around the world, new fuels with high uranium densities must be developed such that low enrichment fuel may be used in its place. Preliminary studies on uranium molybdenum alloys have shown promising results. A uranium molybdenum fuel phase dispersed in a zirconium matrix is proposed and examined in this thesis. Work described herein includes the successful fabrication of materials, preparation of samples, diffusion testing, fuel fabrication, and analysis of the resulting product. The fabrication results appear to be very good and all data collected indicates that this fuel type is fabricable and justifies irradiation testing.
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  • Text: File scanned at 300 ppi (Monochrome) using Capture Perfect 3.0.82 on a Canon DR-9080C in PDF format. CVista PdfCompressor 4.0 was used for pdf compression and textual OCR.Color images: File scanned at 300 ppi (24-bit Color) using Capture Perfect 3.0.82 on a Canon DR-9080C in PDF format. CVista PdfCompressor 3.1 was used for pdf compression and textual OCR.Gray images: File scanned at 300 ppi (256 Grayscale) using Capture Perfect 3.0.82 on a Canon DR-9080C in PDF format. CVista PdfCompressor 4.0 was used for pdf compression and textual OCR.
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