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Preparation of Americium Dioxide by Thermal Decomposition of Americium Oxalate in Air
One hundred and seventy five grams of americium in a hydrochloric acid solution varying from 1 to 7 N was converted to americium dioxide. Americium oxalate was precipitated from 0.1 N HCI with 100% excess oxalic acid and was converted to the dioxide by calcination at 800 ts C in air. The solubility losses in the oxalate precipitation filtrate averaged approximately 7 mg/liter of solution, with a total loss of 0.09%. (auth
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THE ABSORPTION SPECTRUM OF Es3+ IN HYDROCHLORIC ACID SOLUTIONS
Separation of Transplutonium and Rare-Earth Elements by Extraction with Di-isodecyl Phosphoric Acid from DTPA Solution
Recovery of Np-237 by an oxidation-reduction fluoride precipitation method /
Several hundred grams of Np/sup 237/ in nitric acid solution was approximately 95% recovered as NpO/sub 2/ of>99.5% purity. The remaining 5% was recovered as a nitric acid solution of 99.95% purity. The neptunium was oxidized to the soluble +6 state with sodium bromate, and Pu(IV), thorium, and other impurities in the solution were precipitated as fluorides. The neptuninum was then reduced to Np(IV)) with sulfur dioxide and precipitated as KH/sub p/F/sub 5/, dissolved in nitric acid, precipitated as neptunium oxalate, and calcined to the oxide. The recovered material balance was 99.91% with a process loss of 0.09%. (auth)."Date issued Apr 4 1961.""UC-4 - Chemistry.Includes bibliographical references (page 9)Several hundred grams of Np/sup 237/ in nitric acid solution was approximately 95% recovered as NpO/sub 2/ of>99.5% purity. The remaining 5% was recovered as a nitric acid solution of 99.95% purity. The neptunium was oxidized to the soluble +6 state with sodium bromate, and Pu(IV), thorium, and other impurities in the solution were precipitated as fluorides. The neptuninum was then reduced to Np(IV)) with sulfur dioxide and precipitated as KH/sub p/F/sub 5/, dissolved in nitric acid, precipitated as neptunium oxalate, and calcined to the oxide. The recovered material balance was 99.91% with a process loss of 0.09%. (auth).Operated by Union Carbide Corporation for the U.S. Atomic Energy Commission :Mode of access: Internet