ジルコニウムターゲットより放射性イットリウム,ストロンチウムの放射化学的分離法

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In the course of the studies on fast neutron bombardment on Zr target, it was required to develop a method to separate trace amounts of radioactive Y and Sr from the matrix metal of zirconium. The separation must be performed in a short period, and the separated radioisotopes must be of high radiochemical purity and in a suitable chemical form for activity measurement. Among the various methods examined with the aid of tracers Zr-95, Y-90 or Sr-89, the procedures described below were the most successful. (a) Separation of radioactive Y from Zr target; The bombarded Zr metal sheet(1.5 g) was placed in a plastic centrifuge tube with 20 mg of Y(III) as the carrier. The Zr metal was thoroughly dissolved by adding 5 ml of 1 N HCl and 5 ml of 4 N HF dropwise. After the solution was cooled in an ice bath for 3 minutes, the resulted YF3 precipitate was separated centrifugally. The supernatant, including ZrF42-, was discarded with a pipette. The precipitate was centrifugally washed with 2 ml of 1 N HF solution and then dissolved with a mixture of 3 ml of saturated boric acid solution and 2 ml of concentrated nitric acid. The solution was transferred to a glass centrifuge tube and the whole volume of the solution was made to 10 ml. The solution was brought to slightly alkaline (pH 8) with ammonia to precipitate Y as hydroxide. The precipitate, centrifugally separated, was dissolved with 5 ml of 0.05 N HCl. Again yttrium was precipitated, by the addition of 2 ml of saturated oxalic acid solution, as oxalate, which was then separated by filtration. After being washed successively with alcohol and ether, the precipitate was mounted on a counting dish for activity measurement. The over-all radiochemical yield of Y was 70+5%. (b) Separation of radioactive Sr from Zr target; The bombarded Zr target was placed in a plastic centrifuge tube with 10 mg of Sr(II) as the carrier. Four ml of HF(46.2%) was added dropwise to completely dissolve the Zr metal. Then 10 ml of ice-cooled fuming nitric acid (d=1.52) was poured into the tube which was also cooled in an ice bath. After 5 minutes, the precipitated strontium nitrate was centrifugally separated. The supernatant containing Zr was discarded. The precipitate was washed with an aliquot of cooled nitric acid. After dissolution of the precipitate in 3 ml water, the solution was transferred to a glass centrifuge tube with 10 mg of Y(III) carrier as scavenger. The volume of the solution was then adjusted to 5 ml. With ammonia at pH 8 was precipitated yttrium hydroxide which was then centrifuged. So far at this stage, the radioactive Sr remains in the solution. The precipitate was washed with 2 ml of water. From the mixture of the supernatant and the water used for the washing, strontium carbonate was precipitated with 1 ml of 1 M ammonium carbonate solution. The precipitate was washed with an aliquot of alcohol and ether. Then it was mounted on a counting dish for activity measurement. The over-all radiochemical yield of strontium was 60±2%.
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ジルコニウムターゲットより放射性イットリウム,ストロンチウムの放射化学的分離法

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