Volume 110, Issue 4

Appropriately functionalized dendrimers are exotic ligands and are expected to give rise to better extraction/transport results than the corresponding monofunctional ones. Diglycolamide- (DGA) based dendrimers and their transport studies are rarely reported. Transport of Am(III) and Eu(III) was studied across a PTFE- (polytetrafluoroethylene) based flat sheet supported liquid membrane containing a tris(2-aminoethyl)amine (TREN) dendrimer ligand containing six DGA pendent arms (termed as TREN-G1-DGA) in 5% isodecanol modified n -dodecane. The transport results were compared with those of the monofunctional ligand TODGA ( N,N,N′,N′ -tetra- n -octyl diglycolamide). In case of a 5.75 × 10 −4  M TREN-G1-DGA solution, Am(III) transport was slower than that of Eu(III) under identical conditions. In case of TREN-G1-DGA the role of acid on the metal ion transport was less important than that while using TODGA as a carrier. However, a nitric acid medium is much more suitable for metal ion transport than a mixture containing sodium nitrate as the major component. Insight into the extraction and transport of the Eu(III) complexes was obtained from luminescence spectroscopic studies.

A novel cloud point extraction (CPE) procedure was developed to preenrich Th 4+ and UO 2 2+ by oil-in-water (O/W) microemulsion. Coupling CPE to ICP-MS, the separation and analysis were achieved at a trace level, in which the low detection limits were 0.019 and 0.042 ng mL −1 for Th(IV) and U(VI), respectively. N , N ′-diethyl- N , N ′-ditolyl-2,9-diamide-1,10-phenanthroline (Et-Tol-DAPhen), as an extremely hydrophobic extractant, was failed to dissolve in single or mixed micelles, but was successfully solubilized to CPE system owing to O/W microemulsion. The extraction efficiency and selectivity for Th 4+ and UO 2 2+ were excellent under acidic condition of 1.0 mol L −1 HNO 3 , and the recovery of ultra-trace Th 4+ and UO 2 2+ was almost 100% even at the presence of large amounts of lanthanides, exhibiting high tolerance limits for lanthanides. The solubilization, extraction and coordination behaviours were studied systematically via DLS, UV–vis, 1 H NMR and FT-IR. Moreover, the solubilization of N , N ′-dioctyl- N , N ′-dioctyl-2,9-diamide-1,10-phenanthroline (Oct-Oct-DAPhen) and efficient extraction for UO 2 2+ were also realized by O/W microemulsion, which further proved the feasibility of the method.

Palladium-103 is one of the most attractive radionuclides for internal radiotherapy. It is not only used as a brachytherapy seed but is also a feasible candidate for Auger electron therapy and gold-nanoparticle therapy. In this study, we propose a new method for the separation of 103 Pd from a rhodium target to obtain no-carrier-added 103 Pd. Rhodium powder target was irradiated under the following conditions: proton, 50 MeV, 1–3 μA, 1–4 h for the separation study; and H 2 + , 24 MeV, 5 μA, 1 h to produce 103 Pd. The irradiated target was pretreated using an alloying reaction between Rh and Bi on a hotplate at 500 °C. Rhodium in the chemical form of a Bi–Rh compound could then be dissolved with nitric acid and 103 Pd was extracted using dimethylglyoxime as an extractant. The target rhodium was recycled using sodium tetrahydroborate (NaBH 4 ). We obtained 103 Pd with a yield of 87%. The activity of the product was 26 ± 2 MBq at the end of bombardment (EOB), and the radionuclidic purity of 103 Pd was greater than 99%. The decontamination factors of rhodium and bismuth in the 103 Pd product were estimated to be greater than 10 4 and 10 5 , respectively. The target rhodium was recycled with a yield of 91% with a trace of bismuth (9 μg/50 mg Rh). The total separation time for 103 Pd was within 3.5 h.

The current study is an attempt to confirm the possibility of using rafoxanide (Raf) for diagnostic or radiotherapeutic purpose based on the radioiodine used in the labeling process. The isotopic exchange reaction was performed to radiolabel Raf. The maximum radiochemical yield of [ 125 I]Raf (90%) was obtained when 20 μL of Na[ 125 I]I (7.4 MBq (200 μCi)) in the reaction flask was added to 100 μg of Raf (0.799 mM) within 20 min at 140 °C. High pressure liquid chromatography was used to purify the labeled product of [ 125 I]Raf. The activation energy was calculated experimentally in both ethyl acetate and methanol as reaction medium and found to be 22.82 kJ/mol and 24.43 kJ/mol, respectively. Furthermore, Gaussian 09 used the density function theory (DFT) to calculate the activation energy of the reaction in the two solvents.

This study focuses on the synthesis and preliminary bio-evaluation of [ 99m Tc]-technetium tricarbonyl procainamide ([ 99m Tc]-technetium tricarbony PA) as a viable cardiac imaging agent. The compound, [ 99m Tc]-technetium tricarbony PA, was synthesized by labelling procainamide with a [ 99m Tc]-technetium tricarbonyl core, yielding a high radiochemical yield and radiochemical purity of 98%. Under optimal circumstances, high radiochemical yield and purity were obtained utilizing [ 99m Tc]-technetium tricarbonyl core within 30 min of incubation at pH 9, 200 µg substrate concentration, and 100 °C reaction temperature. The heart showed a high absorption of 32.39 ± 0.88% of the injected dose/g organ (ID/g), confirming the suitability of [ 99m Tc]-technetium tricarbonyl PA as a viable complex for heart imaging.

To improve a radiation shielding performance of the polymer composite, poly (vinyl alcohol) (PVA) was composited with cadmium nitrate. Its radiation shielding capabilities of PVA/Cd(NO 3 ) 2 composite films were investigated at three different Cd(NO 3 ) 2 concentration levels: 5, 10, and 15% wt. The structural, thermal, and optical properties of the synthesized composite films were examined. The addition of cadmium nitrate to the polymer worsened its thermal stability and improved its optical energy band gap by lowering its direct bandgap energy from 4.56 to 3.25 eV for PVA and PVA/15 wt% Cd(NO 3 ) 2 films, respectively. The gamma-ray shielding capacity of the composite was examined using radioactive sources including 241 Am (59.5 keV), 57 Co (122 keV), 192 Ir (346 keV) and 137 Cs (662 keV). The Micro-Shielding program was used to compare the experimental results of gamma transmittance with theoretical calculations, and the results were found to be in good agreement. Radiation shielding performance of PVA/Cd(NO 3 ) 2 composite films was examined by the determination of the linear attenuation coefficient ( µ ), mass attenuation coefficient ( µ m ), half value layer (HVL) and exposure buildup factor (EBF). The reinforcement of PVA matrix with 15 wt% Cd(NO 3 ) 2 supported to increase the radiation shielding capacity by 13.7% for gamma photons of 57 Co radioisotope.