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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.
Consists of AECD 1-2023 (no. 1-1779 called MDDC).