Patent Number: 042017386
Section: claims

1. The method of directly preparing U.sub.3 O.sub.8 nuclear fuel material having a controlled particle size distribution from an aqueous solution of uranyl nitrate which comprises (a) contacting said uranyl nitrate solution with sufficient formic acid to effect a denitration of said solution and to form an unsaturated solution of uranyl formate;  (b) further contacting said unsaturated uranyl formate solution with additional formic acid in sufficient stoichiometric excess of formic acid to precipitate uranyl formate monohydrate from said solution;  (c) removing and drying said precipitate to provide a crystalline uranyl formate monohydrate; and  (d) calcining said crystalline uranyl formate monohydrate to produce U.sub.3 O.sub.8 nuclear fuel material having a controlled particle size distribution. 2. The method of claim 1 wherein the temperature of said denitration is maintained at about 90.degree. C. 3. The method of claim 1 wherein the concentration of said formic acid is in excess of about 19 M. 4. The method of claim 1 wherein the rate of addition of formic acid to said unsaturated uranyl formate solution is controlled to provide a substantial portion of said U.sub.3 O.sub.8 nuclear fuel material with a particle size that does not exceed about 150 .mu.m. 5. The method of claim 1 wherein the amount of and rate of addition of formic acid to said uranyl nitrate solution in step (a) is controlled to effect complete denitration and to prevent precipitation of uranyl formate during said denitration. 6. The method of claim 1 wherein said calcining is conducted in air by heating said crystalline uranyl formate monohydrate at a rate of about 10.degree. C. per minute to a temperature of about 800.degree. C. 7. The method of claim 4 wherein the formic acid is added at a rate of between about 0.40 and 1.27 moles/(min)(liter of uranyl nitrate solution).