Recovery of uranium from phosphate ore of Iran mine: Part II- solvent extraction of uranium from wet-process phosphoric acid

被引:2
|
作者
Abdeshahi, A. [1 ]
Sadeghi, M. H. [1 ,2 ]
Nejad, D. Ghoddocy [2 ]
Zare, M. Habibi [2 ]
Outokesh, M. [1 ]
机构
[1] Sharif Univ Technol, Dept Energy Engn, Tehran, Iran
[2] AEOI, Nucl Sci & Technol Res Inst, Nucl Fuel Res Sch, Tehran, Iran
关键词
Di-(2-ethylhexyl) phosphoric acid (D2EHPA); Trioctylphosphine oxide (TOPO); Tributyl phosphate (TBP); Uranium recovery; Phosphate ore; Solvent -extraction process; MIXTURE; VI;
D O I
10.1016/j.nucengdes.2024.113093
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The current study in laboratory scale was aimed at developing an optimal two-stage extraction process for production of yellow cake from the phosphoric acid solution that was extracted from the Sheikh Habil phosphate rocks in central Iran. To attain an optimized extraction process, different mixtures of D2EHPA + TOPO + TBP were examined. A total extraction cycle including extraction, stripping and yellow cake precipitation was run to realistically evaluate the performances of the selected mixtures-conditions. As for optimization of the operational conditions, we exploited central composite design (CCD) method, that is a branch of the surface response methodology (RSM), and analyzed the results with standard statistical methods. The O/A (organic to aqueous ratio) = 2, 11 min extraction time, 5 wt% TOPO concentration, 10-15 wt% TBP concentration, 20 wt% D2EHPA concentration, 800 mv oxidation-reduction potential, and 25 degrees C temperature were obtained as optimum extraction parameters. The O/A = 15, 11 min stripping time, 50 wt% phosphoric acid concentration, 250 mv oxidation-reduction potential, and 40 degrees C temperature were obtained as optimum stripping parameters. Finally on the last uranium extraction from the H3PO4 strippant on the optimum conditions, the concentration of uranium was more than 4500 ppm with extraction efficiency near to 90 %. Scrubbing of organic phase was done by 2 wt% of sulfuric acid solution at 40 degrees C and precipitation of ammonium uranyl carbonate (AUC, (NH4)4UO2(CO3)3) was done with 2 M ammonium carbonate solution at an O/A ratio of 1/2 with efficiency more than 95 % in the uranium precipitation process.
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页数:14
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