照射ウラン中137Csの定量
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概要
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<SUP>137</SUP>Cs in irradiated uranium sample was separated from the other fission products with 10 mg isotopic carrier by using connected columns of silica gel and Ionite C (zirconium phosphate), and was determined by γ-counting whereby the chemical yield was measured by precipitating and weighing of cesium tetraphenyl borate.<BR>Pass 10 m<I>l</I> of 2 <I>N</I> nitric acid solution of the sample with 10 mg Cs carrier through silica gel-Ionite C columns (volume: 3 m<I>l</I> each), and wash the column with 6 m<I>l</I> of 2 <I>N</I> HNO<SUB>3</SUB>. Disconnect the Ionite C column from the silica gel column, wash the Ionite C column with 15 m<I>l</I> of 2 <I>N</I> HNO<SUB>3</SUB>, and with 5m<I>l</I> of 6<I>N</I> HNO<SUB>3</SUB>. Elute Cs adsorbed on the Ionite C column with 10 <I>N</I> HNO<SUB>3</SUB>, evaporate the eluate and take up the residue with 1 <I>N</I> HNO<SUB>3</SUB>. Precipitate Cs three times as tetraphenyl borate. Weigh, and measure the γ-activity.<BR>The recovery test proved that the error was within ±3% and the decontamination factor of Cs from the other fission products at the column separation step alone was >2×10<SUP>4</SUP>.
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