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An annotated bibliography is presented of the work reported in the literature in the English language (1957-1973) on fabrication, mechanical and physical properties, physical metallurgy, and corrosion behavior of depleted uranium-base alloys. Also included are testing and preparation techniques and other studies for unalloyed uranium which are applicable to uranium alloys.
Unclassified reports on processing of enriched UF6 into U metal, U-base alloys, UO2, and UO2SO4 for use a reactor fuels are annotated. Recovery of enriched U scrap, methods of isotopic analysis, health physics, criticality problems, and materials management are emphasized. A few references to papers presented at the Geneva Conference, 1955, and other recent nonreport literature are included. 254 references.
'Feed materials' refers to U metal, fabricated into fuel elements but not clad, and UF6, both normal isotopic content, suitable for introduction into Pu-production reactors or gaseous diffusion cascades.