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In this study, graphene oxide (GO) adsorbent was prepared by modified Hummer’s method and functionalized with aminomethylphosphonic acid. Its application to the adsorption of Sr ions from aqueous solutions in a batch sorption process was investigated. Adsorbents were characterized by TEM and FT-IR. The TEM images of functionalized graphene oxide showed that graphene sheets are formed in wavy sheets. The FTIR spectrum revealed that graphene oxide was highly functionalized with aminomethylphosphonic acid and oxygenated functional groups were reduced. Response surface methodology investigates pH, adsorbent dosage, and temperature parameters. The quadratic model corresponds well with the experimental data. The results illustrated that there is no systematic error in the experiments. The verification of the model with random experiments showed a low error in the values predicted by the model. The kinetic data were analyzed by Pseudo-first-order, Pseudo-second-order, and Double- exponential kinetic models, and experimental data were well modeled by the pseudo-second-order kinetic model. The research results showed that graphene oxide functionalized with aminomethylphosphonic acid has a good ability to strontium adsorption from aqueous solutions.

Neutron radiography (NRG) is a non-destructive imaging technique for image generation using neutron radiation. In this paper, feasibility studies of neutron radiography for IECF were performed by Geant4 Monte Carlo code. The effects of the different thicknesses of lead on the image and the detection possibility of cavities with different sizes inside a thick lead have been investigated to understand the performance of the device for neutron radiography purposes. The quality of the images was evaluated in terms of contrast. The simulation results showed the efficiency and limitations of NRG for IECF devices and the potential areas where NRG can be performed.

161Tb is a promising radionuclide, which is a suitable radionuclide with favorable properties for small treatment size of cancer. NCA 161Tb can be produced by the indirect method through 160Gd(n,γ) 161Gd→161Tb nuclear reaction. To obtain the NCA radionuclides, the existence of an effective Gd/Tb separation method is critical. In this study, isolation of Tb from Gd/Tb matrix using Ln resin column based on extraction chromatography method has been carried out. Fractions eluted from the column containing Gd/Tb matrix were identified and quantified using ICP. The optimization of different experimental parameters for the effective separation of Gd/Tb, such as concentration of eluting solutions and flow rate of load and elution, was investigated. The results showed that optimum Gd/Tb isolation condition was obtained using HNO3 solution with a concentration of 0.8 and 3 N to separate gadolinium and terbium isotopes, respectively. The separation yield of Tb and Gd was obtained at 83.51 % and 81.8%, respectively.

The Holmium-166 radionuclide is one of the most effective radionuclides used to treat bone marrow cancer and rheumatoid arthritis. Among the recommended radionuclides used in radiation synovectomy, 166Ho has got much attention due to suitable decay properties such as short half-life, its high beta energy, gamma-ray emission with suitable energy for nuclear imaging, and the possibility of large-scale production in medium flux reactor. One method to deliver 166Ho to the target tissue is via the 166Dy/166Ho-Chitosan in vivo generator. Compared with other similar radiopharmaceuticals, using the in vivo generator to deliver 166Ho, causes minimal non-target tissue exposure and increased absorbed dose in the target tissue. In this work, the absorbed dose of 166Dy/166Ho-Chitosan radio-complex for radio-synovectomy purposes was calculated by GEANT4 and MCNPX. The obtained results were compared with each other. In addition, the dosimetry results of the mentioned radio-complex have been compared with the common radio complexes used for radio-synovectomy.

The peptides radiolabeled with 177Lu are including a wide range of promising radiopharmaceuticals. The NCA form of 177Lu provides a high specific activity that is required in targeted receptor therapy in order to avoid saturation of the targeted receptors. In this study, the outstanding quality of NCA radionuclides especially in the case of 177Lu was evaluated by comparing with CA radionuclide for radiolabeling of DOTATATE peptide and. The NCA 177Lu and CA 177Lu were obtained by chromatography separation of irradiated 176Yb (enrichment: 96.4%) and irradiation of 176Lu (enrichment: 95%) respectively. Radiolabeling of DOTATE with CA and NCA 177Lu was carried out in the same conditions and time. Then, radiolabeling yield was calculated as a function of some parameters like the Ligand: metal ratio and stability of compound after production. The results showed the superiority of NCA 177Lu with respect to CA 177Lu. Not only the particle ratio showed the advantages of the NCA radionuclide, but also the long-term comparison over a period of 14 days revealed the inferior character of CA.177Lu with regard to the high requirements regarding the specific activity set by radio-immunotherapy.