Quarterly Report for Period 8/10-11/10/51, ORNL RaLa and MTR RaLa Process Development
barium, MTR RaLa Process; ion exchange, ORNL; purification process; solubility, hydrogen; uranium, radiation
Steahly, F.L.; Steahly, F.L.
DOE INFORMATION CENTER 1 Science.gov Way, Oak Ridge, TN 37831; Eva Butler; Phone: 865-241-4780; Toll-Free: 800-382-6938, Option 6; FAX: 865-574-3521; Email: firstname.lastname@example.org
Specific Material\Uranium; Specific Material\Uranium
1951 Nov 05
1997 Nov 26
CF-51-11-161; Copy 11, Series A; Copy11SeriesA
Originating Research Org.:
Oak Ridge National Laboratory
OpenNet Entry Date:
1998 Jun 16
This report concerns the ORNL RaLa and MTR RaLa Process Development. The ORNL RaLa ion exchange purification process was revised to permit the production of the larger batches now required (30 - 40 kilo-curies). Changes designed to minimize the radiation damage to the system and decrease the sensitivity of the feed solution to radiation damage were to (1) substitute sodium acetate for Versene as the first feed solution, and (2) increase the flow rates and column size. A full chemical scale tracer level demonstration run showed that the barium yield will be 96 percent and that the product will meet purity specifications. In the MTR RaLa Process, the solubility of uranium in the caustic dissolver solution and the volume of hydrogen evolved during the dissolution were studied as a function of aluminum, sodium nitrate, sodium hydroxide, sodium carbonate and calcium nitrate concentrations. Using the recommended conditions of 5.OM A1, 2.5M NaNO-3 and 5.0M NaOH, the uranium solubility was approximately 7 mg/liter ~~0.15 percent uranium loss, and the volume of hydrogen evolved was 9/liters/MTR-assembly. The separation of barium from uranium and soluble fission products by precipitation of barium nitrate from 85 percent nitric acid was selected for a process step because of its solubility in water. The nitric acid precipitation gives a quantitative precipitation of barium nitrate with less than 0.04 percent uranium loss. The MTR RaLa ion exchange flowsheet was revised as follows: (1) a step was added for the selective elution of aluminum with sodium hydroxide; and (2) the flow rates and column size were increased. The radiation stability of acetate and Versene feed solutions were studied using the 3,000 curie CO-60 source, and the acetate was apparently more stable than the Versene. The Dowex 50 resin capacity loss was determined after the full scale RaLa Run #45 (12,500 curies of Ba-140). The results showed that 0.232 K.W.H. of beta radiation/Kg. of oven-dry resin was equivalent to a 20 percent loss in capacity. Elution of barium from Dowex 50 was shown to be more efficient with 9M HNO-3 than with 6M or 12M.