首页> 美国政府科技报告 >FABRICATION DEVELOPMENT OF U-Mo-UO2 AND U-Mo-UO2 DISPERSION FUELS FOR THE ENRICO FERMI FAST-BREEDER REACTOR
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FABRICATION DEVELOPMENT OF U-Mo-UO2 AND U-Mo-UO2 DISPERSION FUELS FOR THE ENRICO FERMI FAST-BREEDER REACTOR

机译:富里费米快速反应器U-mo-UO2和U-mo-UO2分散燃料的制备研究

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The fabricability of dispersion fuels using UO2 or UC as the dispersoid and uranium combined with 10 to 15 wt % Mo as the matrix was investigated. Cores containing 17.8 wt (25 vol) % UO2 dispersed in U—15 wt % Mo were successfully fabricated to about 80% of theoretical density by cold pressing at 50tsi, sintering at 1100°C, and cold coining at 50 tsi. Comparable results were obtained with UC as the dispersoid.nCore fabrication results varied greatly with the type of matrix powder used. Occluded gases pour density, and surface cleanliness bore important relations to the fabrication behav¬ior of powders. Suitable pressing and sintering results were obtained with prealloyed, calcium-reduced U-Mo powder and with molybdenum and calcium-reduced uranium as elemental powders. Shotted prealloyed powders were difficult to press and sinter, as were elemental and prealloyed powders prepared by hydriding.

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