Radiochemistry Analysis of 93Nbm and 94Nb
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Graphical Abstract
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Abstract
A radiochemical procedure for separation of 93Nbm, 94Nb from dissolution of spent fuel based on extraction using BPHA, back-extraction using ammonia, and extraction twice by α-benzoin oxime to remove 93Mo is developed. The procedure has decontamination factors of 2.4×106, 1×103 to 137Cs, 93Mo respectively and better than 104 to 144Ce and 103Ru. The efficiency curve at low energy region of broad energy Ge detector was calibrated using standard source of 241Am, 137Cs and 57Co. So the efficiency of 93Nbm can be known from the curve. Finally, using this detection method and the procedure described before, the 93Nbm radioactivity in one kind of spent fuel dissolution is determined to be (126.87±4.86) Bq/g, and the specific activity of 94Nb is less than 0.05 Bq/g.
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