Abstract
The results of calculations of the 234U content in enriched uranium are presented. These results substantiate the need to change the ASTM C 996 specification for the maximum 234U content in enriched uranium to 11000 μg/g 235U and the ASTM C 787 specification for the maximum 234U content in the initial material to 60 μg/g U in connection with the possibility of bringing into enrichment production uranium ores with 234U content higher than 58 μg/g U. These changes will permit using initial uranium with 234U content up to 60 μg/g U when enriching the 235U content to 4.95% with 0.36% 235U in the waste.
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