234U content in enriched uranium as a function of the 234U concentration in the initial material

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.