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This document is a correction notice for a publication on water retreatment in shale reservoirs. The correction updates certain references in the original publication with new citations, while stating that the scientific conclusions remain unchanged. The updated references cover topics such as saline wastewater, shale oil production, water scarcity, wastewater reuse, and treatment technologies. The document also includes a compilation of research articles on wastewater management in the oil and gas industry, covering topics such as water contamination, membrane technology, oil and gas produced water treatment, hydraulic fracturing fluids, and optimization of hydraulic fracturing processes. These articles provide valuable insights into current practices and challenges in wastewater management in the industry. [Extracted from the article]

Herein, SnO2-NiO nanocomposite was prepared via a hydrothermal method and characterized by various techniques consisting X-ray diffraction (XRD), field emission scanning electron microscopy (FESEM) and energy-dispersive X-ray spectroscopy (EDS). The FESEM image showed particles with the size at about 20-130 nm in diameters. The electrochemical oxidation of hydrochlorothiazide (HCTZ) at a carbon paste electrode modified with SnO2-NiO nanocomposite and an ionic liquid (1-butyl-3-methylimidazolium hexafluorophosphate (BMIM-PF6)) (SnO2-NiO/IL/CPE) was evaluated in phosphate buffer (PB) pH 8, by using cyclic voltammetry, linear sweep voltammetry, differential pulse voltammetry and chronoamperometry. The SnO2- NiO/IL/CPE indicated good electrocatalytic behaviour towards to oxidation of hydrochlorothiazide. The anodic peak currents were increased with the HCTZ concentration and indicated two linear dynamic range from 0.01 to 0.1 µM and 0.1 to 100 µM and a detection limit of 0.002 µM (S/N = 5) under the optimized conditions. The introduced electrochemical sensor was successfully utilized for the determination of HCTZ in the pharmaceutical formulations and biological sample. [ABSTRACT FROM AUTHOR]

The purpose of this study was to investigate the effect of different solutions on the optical behavior of two types of 3D-printed resin (Detax and Asiga). The samples were randomly divided into 4 groups of cola, orange juice, tea and artificial saliva (control group) in the form of 14 x 10 mm blocks with a thickness of 1.5 ± 0.3 mm (10 samples in each group). By spectrophotometric device, the color of the examined samples was recorded in the CIE system and in three parameters *L (brightness), a* (red-green) and b* (blue-yellow) as the initial record. The color difference of the samples was recorded on 7 and 30 days after immersion as a secondary record. After that, using the formula, the color difference (Î"E) were calculated. T-test also was used to analyze the data. There was no significant difference between the amount of Î"E on 7th and 30th days after exposure to artificial saliva and cola and on 7th days after exposure to orange juice and tea. But on the 30th day, a significant difference was found in orange juice and tea drinks (p<0.05), so that the value of Î"E in Asiga printer was lower than Detax. Î"E changes in orange juice solution were more than other drinks. On the 30th day of immersion in tea drinks and orange juice, Asiga printer had significantly less color difference than Detax printer. [ABSTRACT FROM AUTHOR]

Introduction: Radioactive iodine finds widespread application in both diagnostic and therapeutic contexts. I - 123 and I - 125 serve diagnostic purposes, whereas I - 125 and I - 131 are employed for treating conditions such as hyperthyroidism and thyroid tumors, either through targeted radionuclide therapy or brachytherapy. The deterministic impact of the dose received by cells, especially within the cell nucleus, plays a crucial role in predicting radiation complications. This study aims to compare the received dose in cellular human thyroid models resulting from exposure to I - 123, I - 125, and I - 131 radionuclides. Methods: The Gate Monte Carlo software (version 9.3) was used for simulation and dosimetric calculations. The energies of electrons resulting from decay were chosen based on the corresponding decay spectrum of each radionuclide, as provided by MIRD (medical internal radiation dose). The cells were simulated considering cubic geometries with the dimensions of 6, 10, and 17.5 micrometers, and the nucleus was modeled as a spherical shape with diameters of 5, 7, and 9 micrometers. The s - value (dose per decay) values were calculated for different source - target configurations, including nucleus (as source) - nucleus (as target volume), cell membrane - nucleus, and cytoplasm - nucleus. In all cases, the S - values in the extracellular medium, were also calculated. Results: Across all scenarios, the highest S - value was related to the nuclear self - absorption (nucleus - nucleus configuration). I131 had the highest S - value in the nucleus - nucleus situation and the lowest value was for I123. In the case of cytoplasm - nucleus and cellmembrane - nucleus, the highest S value was related to I131. In all cases, the contribution of internal radiation electrons in S - value was higher than Auger and beta electrons. S - value decreased with the increase of cell size and nucleus. This difference was greater in the cytoplasm - nucleus and cell - nucleus membrane than in the nucleus - nucleus situation. It is worth mentioning that I123 delivered a lower dose to the extracellular environment compared to other radionuclides. Conclusions: Distinct radiations of radioactive iodine demonstrated significant differences in their contributions to S - values. The dimensions of the cell exerted a more substantial effect than the source - nucleus location on the delivered dose to the cell nucleus. I123, notably, resulted in a lower dose to the cell nucleus and the extracellular environment, suggesting potentially reduced damage to the thyroid cell DNA. [ABSTRACT FROM AUTHOR]

Introduction: Gamma cameras are proposed for online range verification and treatment monitoring in proton therapy. An Analytical formula was derived and validated for sensitivity of a slit collimator based on the photon fluence concept. Methods: Fluence formulation was generalized for photons distribution function and solved for high-energy point sources. The effect of the collimator slit size and source off-axis position on the sensitivity of the collimator were included in the formula. Results: The analytically calculated sensitivities of the slit collimator were in good agreement with Monte Carlo results according to the Bland-Altman agreement test and Pearson correlation (r =0.998) statistical analysis with p < 0.05. The mean relative error between calculated sensitivities with the derived formula and Monte Carlo was up to 0.8%. Moreover, we found that under certain conditions, the established formula is converted to the Anger equation for the pinhole collimator. Conclusion: The analytical formula developed in this research can estimate the slit collimator sensitivity with an acceptable accuracy. The derived closed-form sensitivity formula can be applied in KE collimator design and optimization studies. [ABSTRACT FROM AUTHOR]

Single photon emission tomography is widely used to detect photons emitted from the patient. Some of these emitted photons suffer from scattering and absorption because of the attenuation occurred through their path in patient's body. Therefore, the attenuation is the most important problem in single-photon emission computed tomography (SPECT) imaging. Some of the radioisotopes emit gamma rays in different energy levels, and consequently, they have different counts and attenuation coefficients. Calculation of the parameters used in the attenuation equation Nout=αNin= e−μl Nin by mathematical methods is useful for the attenuation correction. Nurbs-based cardiac-torso (NCAT) phantom with an adequate attenuation coefficient and activity distribution is used in this study. Simulations were done using SimSET in 20–70 and 20–167 keV. A total of 128 projections were acquired over 360°. The corrected and reference images were compared using a universal image quality index (UIQI). The simulation repeated using NCAT phantom by SimSET. In the first group, no attenuation correction was used, but the Zubal coefficients were used for attenuation correction in the second image group. After the image reconstruction, a comparison between image groups was done using optimized UIQI to determine the quality of used reconstruction methods. Similarities of images were investigated by considering the average sinogram for every block size. The results showed that the proposed method improved the image quality. This study showed that simulation studies are useful tools in the investigation of nuclear medicine researches. We produced a nonattenuated model using Monte Carlo simulation method and compared it with an attenuated model. The proposed reconstruction method improved image resolution and contrast. Regional and general similarities of images could be determined, respectively, from acquired UIQI of small and large block sizes. Resulted curves from both small and large block sizes showed a good similarity between reconstructed and ideal images. [ABSTRACT FROM AUTHOR]

Introduction: The choice of optimal radionuclides for radioimmunotherapy depends on several factors, especially the radionuclide and antibody. The dosimetric characteristics of a non-internalizing and an internalizing monoclonal antibody (MAb) labeled with beta emitting radionuclides were investigated. Methods: Using Geant4-DNA Monte Carlo simulation, we carry out dosimetric calculations for different subcellular distributions of beta-emitting radionuclides; 131I, 177Lu, 64Cu, 186Re and 153Sm. Results: The dependency of the radial dose profiles on the energy spectra of electrons (beta particles and Auger and internal conversion electrons) and also their relative yield of emission is clear. The highest difference between the radionuclides tested was observed when the activity was localized in the nucleus. There was not considerable difference in the nucleus dose when radionuclides were localized in cytoplasm and over the cell membrane. Conclusion: There is a very significant increase in the dose deposited to the nucleus if 153Sm localized at the nucleus. Although subcellular localization of activity isn't a critical factor for beta emitting radionuclides, but the use of internalizing MAbs leads to an increase in nucleus dose and to the killing of single cells in addition to the tumors. [ABSTRACT FROM AUTHOR]

Nanoparticles are generally cleared by the reticuloendothelial system, taken up by Kupffer cells in liver. This principle can be used for liver imaging. Chitosan is an excellent biocompatible and biodegradable polymer. In this study, the authors synthesized99mTc-chitosan nanoparticles and evaluated its potential for liver imaging. Chitosan nanoparticles were synthesized and radiolabeled with99mTc. The labeling efficiency, stability, biodistribution, and imaging study in the normal mice was performed. Biodistribution and imaging studies demonstrated an efficient accumulation of the radiolabeled nanoparticles in the mice liver and indicated the99mTc-chitosan nanoparticles may be considered as a promising radiopharmaceutical for liver imaging. [ABSTRACT FROM AUTHOR]