[en] A comparison of the distribution coefficients (K_d) of tellurium and iodine-131 (¹³¹I) between hydrochloric acid of various concentrations (without and in presence of 0.1 M thiourea) and the cation exchange resin (Dowex50WX8) was studied. The K_d of tellurium and ¹³¹I at different concentrations of thiourea in 0.1 M HCl on the Dowex50WX8 was also studied. The results clarified that the maximum uptake of tellurium was 98% on the Dowex50WX8, while the uptakes of ¹³¹I and thiourea are 1.96% and 70%, respectively. To purify ¹³¹I from thiourea (30%), which is not retained on Dowex50WX8, the remaining solution was shaken with different types of anion exchangers (Dowex21 K, Dowex1X8, and Dowex1X2) within 60 min. The most suitable anion exchanger, which gave the maximum uptake of ¹³¹I (80%) was Dowex21 K. Finally, ¹³¹I was re-extracted from Dowex21 K into 5 mM TBAB with a separation yield of 98%. Quality control on the separated product of tetra-butyl ammonium iodide (¹³¹I) was carried out

[en] The separation of ⁶⁷Ga from zinc and copper target materials using an anion-exchanger (Dowex21K) and 0.1 M citrate buffer at pH 6 is described. The gallium-67 was separated in citrate solution and can be directly used for medical applications

[en] A rapid method and high radiochemical yield were investigated for labelling etoposide with the radioactive iodide (Na¹²⁵I) in presence of chloramine-T (CAT) as oxidizing agent. The factors, which affect the radiochemical yield such as oxidizing agent (CAT, hydrogen peroxide), ph, reaction temperature, reaction time and organic solvents (acetic acid, dimethyl formamide, ethanol and methanol) were studied. The optimum condensed in one reaction to obtain the maximum radiochemical yield of diiodo-etoposide (65%) when the reaction was carried out in presence of CAT (1 m M), in buffer solution at ph 11, within 5 min at 60±1 degree

[en] A preparation of ¹²⁵I-celecoxib is carried out via an electrophilic substitution reaction. The reaction parameters studied were celecoxib concentration, reaction temperature, pH of the reaction mixture and kinds of oxidizing agents in order to obtain a high radiochemical yield of the ¹²⁵I-celecoxib. Using 3.7 MBq of Na¹²⁵I, 150 μg (3.9 mM (mmol/L)) of celecoxib, and 1.6 mM (mmol/L) of chloramine-T (CAT) as oxidant at pH 4 and 60 deg C for 15 min a maximum radiochemical yield of ¹²⁵I-celecoxib (65%) was obtained. The labeled compound was separated and purified by means of high pressure liquid chromatography (HPLC). The biological distribution in infected mice indicates the suitability of radioiodinated celecoxib as imaging of tumor. (author)

[en] A separation procedure of ^64,67Cu(II) from ⁶⁵Zn(II) was studied for serving ⁶²Zn/⁶²Cu generator preparation. The distribution coefficients of ⁶⁵Zn(II) and ^64,67Cu(II) ions from homogeneous medium of hydrochloric acid and acetone onto De-Acidite FF anion exchanger were investigated. Both hydrochloric acid and acetone concentrations are important factors that affect the separation process. Effects of decreasing the HCl concentration from 0.2 to 0.04 M, increasing the acetone concentration from 5% to 80% and different acetone concentrations (5-97%) in 0.2 M HCl were also studied on the separation of ^64,67Cu(II) from ⁶⁵Zn(II). The exchange capacity of Zn(II) on the De-Acidite FF matrix was obtained as 3.8 meq/g and the^64,67Cu(II) elution efficiency was 92.5% using 20 ml of 0.2 M HCl-60% acetone with flow rate of 2 ml/min.The radionuclidic purity and radiochemical purity of the eluted ^64,67Cu(II) were examined.

[en] A comparison of the distribution coefficients (K d) of tellurium and iodine -131 between hydrochloric acid of various concentrations (without and in presence 0.1 M thiourea) and the cation exchanger resin (Dowex 50 W X 8) was studied . the results clarified that the maximum uptake (%) of the tellurium is 98% on the dowex 50 W X 8. while the uptakes (%) of iodine -131 and thiourea are 1.96 and 70% . respectively. to purify iodine -131 from thiourea (30%) , which is not retained on dowex 50 W X 8. the remaining solution was shaken with different types of anion exchangers (Dowex 21 K.Dowex 1 X 8.and dowex 1 X 2). within 60 minutes dowex 21 K was to be the most suitable anion exchanger could be used and gave the maximum uptake (%) of iodine-131(80%). finally. iodine-131 is re-extracted from dowex 21 K by 5 m M TBAB with separation yield 98% . the quality control on the separated product of tetra-butyl ammonium iodide (¹³¹ I) was carried out

[en] A simple radiochemical method is described for separating indium-114 from cadmium and copper. The separation is carried out by the difference in the sorption of indium, cadmium and copper on an organic or an inorganic cation exchanger (Dowex 50 X 8 or potassium zinc hexacyanoferrate, respectively) from 0.05 or 10^-5^M HCl, respectively. The distribution coefficients of the three elements on two types of cation exchangers were evaluated in HCl (0.05 or 10^5M), acetate buffer (1M) at Ph 4 and EDTA (10^3M) in order to find the best conditions for separation of 114^Indium from Cd and Cu. A comparison of the separation by these cation exchangers shows one suitable cation exchanger (Dowex 50 X 8) with radiochemical separation yield of radio indium more than 98% within 50 min by using column chromatograph

[en] Triton X-100 cerium(IV) phosphate (TX-100CeP) was synthesized and characterized by using IR, X-ray, TGA/DT and the elemental analysis. The chemical stability of TX-100CeP versus the different concentrations of HCl acid was studied before and after its exposure to the radiation dose (30 K Gray). The effect of HCl concentration on separation of Cr(III) from Cr(VI) by using TX-100CeP as surface active ion exchanger was also studied. A novel method was achieved for the quantifying of Cr(III) and Cr(VI) ions by using the high-performance liquid chromatography (HPLC) at wavelength 650 nm, a stationary phase consists of reversed phase column (Nucleosil phenyl column; 250 x 4.6 mm, 5 μm), and a mobile phase consists of 0.001 M di-(2-ethylhexyl) phosphoric acid (DEHPA) in methanol:water (70:30 v/v). The retention times were 7.0 and 8.5 min, for the Cr(III) and Cr(VI), respectively. The exchange capacity of Cr(III) was quantified (2.1 meq/g) onto the TX-100CeP. (author)

[en] The zirconium silicotungstate (ZrSiW) was studied as an effective sorbent material to be used in the ¹¹³Sn/^113mIn generator. The results elucidated that the distribution coefficient of ¹¹³Sn (3700 mL/g) is greater than ^113mIn (275 mL/g) from 0.1 M HCl acid solution to the ZrSiW material. The maximum sorption capacity of Sn (IV) was found to be 33 mg per gram ZrSiW (∼ 0.3 mmol/g). The elution yield of ^113mIn was found to be > 78 ± 6.4% with an acceptable purity of radionuclidic and radiochemical (≥99.99 and 96.8%, respectively). The rigorous separation of ^113mIn from the ¹²⁵Sb was carried out due to its long half-life (2.758 years) and beta emission that causes tissue damage. Zr, W and Si levels are below the permitted limit in the ^113mIn eluate. (author)

[en] The activated carbon was prepared by using corncobs and characterized by sorpatometer for using as an exchanger material to separate the generated ^113mIn from ¹¹³Sn and ^124,125Sb. To optimize the separation process, the different parameters like acetone percentage, HCl concentration were studied. The exchange capacity of Sn(IV) is 7.6 meq/g onto the activated carbon and the elution efficiency of ¹¹³mIn > 80% by using 10 mL of 0.2 M HCl-80% acetone with flow rate 1 mL/min. The radionuclidic purity and radiochemical purity of the eluted ^113mIn were examined and clarified the presence of ^124,125Sb with relatively high level as radio impurities, so further separation was carried out by using Dowex 1 x 8 as an anion exchanger below the activated carbon matrix on the same separation column to adsorb the ¹¹³Sn and ^124,125Sb, which escape from the activated carbon matrix. (author)