Removal of Eu3+ from simulated aqueous solutions by synthesis of a new composite adsorbent material.

The goal of this research is to separate and purify 152+154Eu generated from nuclear waste and/or research laboratories using synthesized composite material. Fourier infrared (FTIR), thermal gravimetric analysis (TGA), differential thermal analysis (DTA), scanning electron microscopy (SEM), and Brunauer-Emmett-Teller (BET) surface area measurements were used to characterize the composite material. On the 152+154Eu sorption process, the impacts of pH, contact time, and initial feed concentration were also examined. The best 152+154Eu removal efficiency was 86.4% achieved at pH 4.5 and 180 min. The sorption data of 152+154Eu ions were investigated using kinetic modeling and sorption isotherm models, and it was clear that the pseudo second-order kinetics and the Langmuir isotherm are the best matches for the sorption process. The produced adsorbent capacity was 11.48 mg g-1. Application study demonstrated that the removal efficiency (%) reached 92.4, 92.2 and 95.2% of 152+154Eu (carrier free) from river, tab and groundwater, respectively. According to the findings of this investigation, the proposed polymer composite is a strong candidate for recovering radioactive 152+154Eu ions from liquid waste.

Novel nano network trigonal prismatic Ba2CoO4-deficient BaCoO3 for high-affinity sorption of radiolanthanide elements of biomedical applications: synthesis and sorption studies.

Nano trigonal prismatic Ba2CoO4 with hierarchical structure and deficient BaCoO3 with columnar structure have been prepared at low temperatures (400 [BC4] and 500 [BC5]) °C/3h using green method. X-ray diffraction (XRD) results demonstrate the presence of enriched Ba2CoO4 phase at 400 °C and multiphase structures: BaCoO3, BaCoO3-δ, and Co3O4 with a decrease in the amount of Ba2CoO4 at 500 °C. The prepared powders are characterized by a high specific surface area (SSA) values which are reflected to the mode of synthesis that leads to produce materials with massive active sites. The SSA of BC4 is higher than that of BC5 which can be correlated to the difference in the microstructure analysis of BC4 and BC5 as given from scanning electron microscope (SEM) and high-resolution transmission electron microscope (HRTEM) studies. Electron spin resonance (ESR) spectroscopy as an effective method for the characterization of vacancy-rich nanostructures indicates that the presence of oxygen vacancies is related mainly to BaCoO3, BaCoO3-δ, and Co3O4 phases while the effective oxygen vacancies is in BaCoO3 and BaCoO3-δ. The nanocrystalline structures of BC4 and BC5 as novel nano-adsorbents are the first time to be tested. Production of Gd radioisotopes through natGd(n,γ)153,159,161Gd and carrier-free 161Tb through 160Gd(n,γ,) 161Gd [Formula: see text] 161Tb are achieved at 2nd Egyptian nuclear research reactor (ETRR-2). Preliminary sorption study of Gd radioisotopes (represent the lanthanide elements) shows a promising material for the application in the separation and removal of lanthanide elements. The results demonstrated that the fast interaction and efficient sorption of lanthanides ions are based on the novel synthesized nanomaterial that can be considered for the upscale application in this field.

Biosynthetic new composite material containing CuO nanoparticles produced by Aspergillus terreus for 47Sc separation of cancer theranostics application from irradiated Ca target.

Copper oxide nanoparticles (CuO NPs) are needed in various fields, especially in the biomedical field. CuO NPs was obtained from Aspergillus terreus filtrate. CuO NPs structure was confirmed by UV-Vis spectrophotometry, as well as Fourier transform infrared (FT-IR), X-ray diffraction (XRD), scanning electron microscopy (SEM) and transmission electron microscopy (TEM). XRD offers the nanoparticles purity of CuO biosynthesis. CuO NPs are spherical when examined with TEM. The average size of CuO NPs from TEM was 15.75 ± 3.95 nm. New composite of P (AA-AN)-NPs CuO was synthesized by biotechnology and the induced γ-radiation. The distribution coefficient value (Kd) of 47Sc(III) as well as 47Ca(II) ions for the synthetic new composite was determined by batch technique. Radiochemical separation of 47Sc(III) from irradiated calcium target was studied using chromatographic column packed with the new composite material. The recovery yield of 78 ± 1.2% for 47Sc(III) was obtained using 1 M HCl. The quality control tests (chemical, radionuclide and radiochemical purities) of the eluted 47Sc confirmed that it's adequate for nuclear medicine applications.