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Scandium-47 is one of the most promising medical radioisotopes, and its production and trace separation make it an attractive candidate for theranostic application. In this study, the production of no-carrier-added (NCA) 47Sc through the natTi(n,p) reaction and subsequent purification using liquid–liquid extraction was done for the theranostic application. The comparative separation of NCA 47Sc after the dissolution of an activated Ti target using Di-2-Ethylhexyl Phosphoric Acid (HDEHP) in kerosene was evaluated. The extraction process was optimized in terms of the concentration of extractant, extraction time, pH, and reaction temperature to achieve the maximum possible separation. HDEHP is efficient and promising for rapid extraction and separation of NCA 47Sc from Ti ions at low acidity (pH 0.85) with high extraction percent (>99%), contaminated with 22.3% of Ti ions after 5 min of extraction time. Different stripping reagents were used to separate loaded 47Sc and Ti ions. Firstly, 5 M HCl was enough for stripping the loaded Ti ions. Then the loaded 47Sc was separated with a purity of 100% using 0.05 M NaOH. The obtained results find the HDEHP a promising extractant for efficient separation of 47Sc from irradiated Ti target for preparing the 47Sc radiopharmaceuticals for theranostics applications.

This work is devoted to the preparation and characterization of silver sulfide (Ag2S) nanoparticles and used as an adsorbent for the separation and purification of Zr(IV), Y(III), and Sr(II) as a simulation mode for the purification of 89Zr from its parents (Y or Sr) and separation of 90Y from its parent Sr using batch and dynamic conditions. N2 adsorption-desorption isotherm for Ag2S is of type IV with a specific surface area (222 ± 0.4 m2/g). The surface is homogeneous texture in which connected channels of diameter 8.3 µm with embedded lamellar structures and the average nanoparticle sizes of 42 ± 3 nm. Ag2S nanoparticles sorbent material shows high selectivity for Zr(IV) from 0.01 M HCl with fast kinetics while 67.2% of Y(III) was removed at pH 4.5 and Sr(II) ions are nil. The adsorption process is exothermic and the intra-particle diffusion and film diffusion were involved in the adsorption mechanism. Also, the separation process was achieved using the column technique with a purity of 100% using different concentrations of HNO3 as eluent. Silver sulfide as an adsorbent material shows a promising potential with high sensitivity for separation and purification trace of Zr, Y, and Sr ions.

47Sc can be produced from different three neutron induced nuclear reactions as 47Ti(n,p)47Sc, 50V(n,α)47Sc and 46Ca(n,γ)47Ca, 47Ca(β−)47Sc using the Egyptian Second Research Reactor. The measured neutron cross-sections (σ) are 62.12 ± 1.93, 4.51 ± 1.27 and 69.36 ± 2.01 mb from the natural targets of TiO2, V2O3 and CaO respectively. The carrier-free 47Sc from 47Ti(n,p), was purified using a composite of Alginate–Carboxymethyl cellulose/di-2-ethylhexyl phosphoric acid. The radiochemical separation of 47Sc with a recovery yield of 90 ± 1.2% was obtained. The eluted 47Sc passed quality control tests (chemical, radionuclide, and radiochemical purities) and was found to be suitable for nuclear medicine applications.

The activated carbon (AC) was modified by molecules of quinoline (Q) and the new prepared AC impregnated by Q was characterized using Fourier transform infrared (FTIR), Raman spectroscopy, surface measurements, scanning electron microscope (SEM) and transmission electron microscope (TEM). These analytical techniques demonstrated a successful preparation of AC-Q as a new material which was examined for its sorption behavior for natural uranium. The sorption results by batch mode indicated the optimum conditions for 94.5% removal of U(VI) ions at pH 4.7 and an equilibrium contact time of 90 min. The analysis of sorption data revealed that the pseudo-second-order and Langmuir were more fitted than other estimated models. The sorption capacity of U(VI) was ∼63 mg/g onto AC-Q as adsorbent martial. The thermodynamic data demonstrated that the sorption of uranium is endothermic and spontaneous. New mechanism was supposed based on the role of the abrasive material quinoline on the mechanical removal of uranium from aqueous solution.

The incorporation of marble particles into the framework of composite material through the polymerization of acrylic acid (AA) and acrylamide acid (AM) using induced gamma irradiation was performed. The novel poly[AA-AM]-marble composite was characterized by multiple analytical instruments such as: energy dispersive X-ray analysis (EDX), X-ray diffraction (XRD) analysis, differential thermal analysis-thermogravimetric analysis (DTA-TGA), Fourier transformer infrared (FTIR), surface area measurements using Brunauer–Emmett–Teller (BET) method and scanning electron microscope (SEM). Radioisotopes of fission (152+154Eu) and activation products (60Co) are the major environmental threats. Sorption of stable isotopes of cobalt and europium onto the synthesized composite material as the sorbent is applied. Sorption kinetics of Eu3+ and Co2+ were computed. The obtained results were analyzed by pseudo-first- and second-order, intraparticle diffusion, and Elovich kinetic models. It is deduced that the pseudo-second-order was more fitted and a chemisorption mechanism was suggested. The sorption capacity for Eu3+ and Co2+ on the prepared composite material was measured at the contact time (2 h) and pH = 4 (for Eu3+), pH = 6 (for Co2+) and it was found to be 91.2 and 13.1 mg/g, respectively. A promising result for the decontamination of both Eu and Co ions was obtained in various aquatic ecosystem applications such as: river water, tap water and groundwater.

The goal of this research is to separate and purify

This work spotlights on the rapid and effective separation method for the no-carrier-added (NCA) 47Sc from natural irradiated Ti target using an anionic exchanger resin; AN-31 impregnated with 4-(2-Pyridylazo) resorcinol (PAR). The newly prepared resin (An-PAR) was characterized by FTIR and SEM. The Influence of pH on the distribution coefficients (Kd) of Sc(III) and Ti(IV) ions was investigated by batch technique and the results revealed that Ti(IV) ions are strongly adsorbed by AN-PAR rather than AN-31, while Sc(III) ions are weakly adsorbed on the both resin materials. The radiochemical separation of 47Sc(III) from irradiated natural Ti target was successfully carried out, where the elution efficiency for 47Sc reached 89 ± 1.5% with high radiochemical, radionuclidic and chemical purities. Our findings thus hold a great promise for the use of 47Sc radioisotope in the preparation of radiopharmaceuticals for theranostics applications.

The present study describes enrichment and purification of zirconium the Egyptian zircon ore, by selective successive precipitations and two analytical tools. The obtained main results indicated that three grades of Zr-concentrates were produced (PPt-A, PPt-B and PPt-C) by selective precipitation. In PPt-B grade, Zr exists with actinides (U and Th), so, purified by anion exchange chromatography and fractional precipitation. However, the purity of Zr obtained by the both methods reached 99%. Meanwhile, recoveries were varied between 64% of fraction precipitation and 95% by extraction chromatography. As a result, the Zr/Hf ratio in zircon ore was 40.3 in zircon ore, then, increased to 463 (11.5-folds) in PPt-B concentrate obtained by selective precipitation at pH 5, and increased again to 116-folds by extraction chromatography. Due to the some industrial and the nuclear significance of Zr, the zircon exists around the long Egyptian beaches can be explored to produce high grades of Zr-concentrates.

Production of no carrier-added (NCA) 199Au through natPt(n, γ) reaction and subsequent purification using liquid-liquid extraction from other radioisotopes is studied in the context of theranostic application. Comparative separation of NCA 199Au after dissolution of activated Pt target using three Cyanex compounds (Cyanex-272, Cyanex-302 and Cyanex-923) is evaluated. The extraction process is optimized in terms of the type of extractant, the concentration of extractant, extraction time and aqueous media (HNO3, NH4OH). Among these extractants, the Cynaex-923 is efficient and promising for rapid separation and production of NCA 199Au from HNO3 by high extraction %. Selective extraction of 199Au from other Pt and Ir radioisotopes is observed. High recovery of 199Au was obtained in the case of Cyanex-923 using 0.05 M thiourea dissolved in HCl or 2 M NaOH. Our results find the Cyanex-923 as a promising extractant for efficient separation of 199Au from irradiated Pt target with high yield (99%).

The present study is conducted for developing separation of some elements of nuclear interest from zirconium-concentrate explored from Egyptian zircon mineral, using certain cationic exchangers. Th...

Nuclear techniques are applied for exploration and efficient tapping of natural resources in finding promising resources of mining and mineral processing industries. The rare earth elements (REEs) in four fluorite samples, collected from Nuba Mountains are determined using neutron activation analysis (NAA) technique. The concentration of 11 REEs (Sc, La, Ce, Nd, Sm, Eu, Gd, Dy, Tb, Yb, Lu) was measured and found within ranges between 685 and 1747 ppm. The Ca is a major element in the four samples. The Fe, Al, Na, Ba and Sr are found as minor elements in the investigated samples. In addition, tracer levels of U, Th, Cs, V and Sc are also detected. The signature of Ce, La and Nd as light REEs is characterized in all samples under this study. The enrichment types of light-REEs (L-type), medium-REEs (M-type) and several distinct features of some REEs e.g., Ce and Eu anomalies are identified and described as the signature of REEs in the geochemical samples. These results have demonstrated promising materials that could be used for hydrometallurgy processing to get significant amounts of REEs.

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 $$ \overset{\kern1em {\beta}^{-}\kern1em }{\to } $$ 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.

In the present work, poly(acrylamide-acrylic acid)-SiO2, p(AM-AA)-SiO2, was made with a template polymerization technique induced by gamma irradiation as an initiator under an irradiation dose of 60.00 kGy. The produced hybrid polymer was investigated using different techniques such as scanning electron microscope (SEM), Fourier-transform infrared (FT-IR), thermogravimetric analysis (TGA), and X-ray fluorescence (XRF) and was applied for the separation of Y(III) and Sr(II) using column chromatography resulting in an acceptable separation. The results exhibited that the percentage of adsorption of Y(III) in the binary system increased with increasing pH value with a slight uptake percentage of Sr(II) ions in the batch technique. The highest removal percentage of Y(III) was about 90.00% with a low amount of Sr(II) and was achieved at pH 4.00 in batch technique with specific values of the distribution coefficient (Kd) and separation factor (SF). The loaded percentages of Y(III) and Sr(II) on the packed column were 95.50 and 40%, respectively, at the best conditions. The results illustrated that the recovery Y(III) and Sr(III) from the packed column were 98.97 and 96.65%, respectively, using 25% ethanol followed by 0.001 M HNO3. The hybrid polymer could be regenerated and achieved, and the results are relevant that there is no change in adsorption ability of p(AM-AA)-SiO2 after three times of use. The results recommended that the p(AM-AA)-SiO2 is effective for the separation and purification of Y(III) from Sr(II) ions.

This work describes the purification and separation of some radionuclides of 210Pb and/or 210Bi that might be used in calibration of nuclear spectroscopic instruments for forensic purposes and environmental studies. The retention and desorption investigations have been done by Dowex HCR-S/S resin as the cationic exchanger by batch mode. Full retention of metal ions was achieved in 0.1 M HNO3 solution after an equilibration period of 2 h at room temperature. The uptake of Pb and Bi is reached to more than 95 and 85%, respectively. Desorption studies by several reagents indicated that 1 M citric acid and ammonium acetate are efficient to elute and separate Bi and Pb. Taking into consideration all the above obtained results, column applications packed by the Dowex HCR-S/S resin were carried out to separate 214,210Pb and 214Bi radionuclides either in TENORM-concentrate or old certified reference of 226Ra solution. The column application results revealed that the recovery of Pb and Bi radionuclides was ∼93%. In the radiochemical part, the eluted Bi was impure due to presence of 23% Pb. In contrast, 70% of pure Pb was obtained. Thus, the radionuclides 210Pb can be recovered from several waste resources by this method. It can be concluded that the Dowex HCR resin can be an alternative economic material that could be used to produce 210Pb from the TENORM wastes generated from some strategic industries.

The characterization and radiological study of sludge technically enhanced naturally occurring radioactive materials (TENORM) waste samples collected from the production of oil and gas at Gabal EL Zeit eastern desert in Egypt were carried out using different analytical and radiological spectrometry. The sludge TENORM waste sample was fractionated to 3 different particle sizes (

The quantity of liquid organic radioactive wastes produced by the use of radioactive materials in nuclear research facilities is small compared to aqueous radioactive waste, but a special and low-cost treatment method is needed. Here we investigated the adsorption performance of five materials, namely: KU-2 resin, bentonite, charcoal (M&S) and clay adsorbents for the successful removal of 90Sr/90Y from liquid scintillation cocktail waste. The batch adsorption technique (influence of pH, contact time, and temperature), sequential, and column technique were investigated. The efficiency of these adsorbents for the removal of 90Sr/90Y is in this order, resin > bentonite > clay with removal efficiency 90 ± 5.2, 68 ± 3.25, and 65 ± 5.3%, respectively. While charcoal has lower affinity for the sorption processes. Purification of liquid scintillation (LS) cocktail by separation of 90Sr/90Y was successfully carried out by packed column with KU-2 resin. The exhausted loaded column with 90Sr/90Y is successfully regenerated by 25 mL, 1 M HNO3. Characterizations of the original and the purified LS cocktail were carried out using FTIR analysis. The efficiency of the purified liquid scintillation waste (LSW) for the determination of radionuclide is about 62.67 ± 4.8.

Feasibility of 199Au production from neutron activated platinum and gold targets at the Egyptian Second Research Reactor was studied. A comparison between theoretical calculations and experimental measurements for the two targets was carried out. A radiochemical separation of 199Au from irradiated Pt target was achieved using chromatographic column packed with modified chabazite material with elution efficiency of 90 ± 0.54% based on the high separation factor between Au and other produced undesired radionuclides. Three quality control tests; radionuclidic, radiochemical and chemical purities were carried out on the eluted 199Au to ensure its safe application in nuclear medicine.

This study is concerned with the sorption behavior of natural radionuclides (226Ra, 210Po, 228Th—originated from TENORM waste associated with petroleum industry) onto silica/olive pomace nanocomposite. Initially, nanocomposites of extracted silica and olive pomace are prepared and characterized by physicochemical techniques. In the batch technique, 60% SiO2 40% olive pomace (AM3) nanocomposite showed a considerable group sorption for 226Ra and 210Po larger than 228Th in 1M HNO3 and HClO4 solutions. In case of sorption by the compacted disc, sorption of 226Ra was similar to batch method, sorption of 228Th increased slightly to ~ 17%, while sorption of 210Po was decreased to 77%. Thus, AM3 nanocomposite can be considered as an efficient nano-adsorbent for sorption and separation of Ra-isotopes and 210Po-radionuclides from 226Ra–210Po–228Th admixture associated with nuclear and non-nuclear industries.

The mobility of several radionuclides in a soil sample from a potential site in Egypt is examined. The retention of 152,154Eu (as homologs of 241Am), 60Co, 137Cs, and 99Mo in the presence of chelating ligands in the soil sample and without them is studied. Four chelating agents, namely, ethylenediaminetetraacetic acid (EDTA), citric and oxalic acids (as the major degradation products of EDTA), and humic acid are chosen for this purpose. The radionuclide retention on the soil without chelating ligands decreases in the order Co(II) > Eu(III) > Cs(I) > Mo(VI), with Kd equal to 11.38 mL/g for 99Mo and 1088 mL/g for 152,154Eu. The chelating ligands had little influence on the sorption of 60Co and 137Cs, but significantly decreased the retention of 152,154Eu owing to complexation. The soil sample on the potential nuclear site can act as a material for trapping the released radionuclides.

The expanded perlite and base activated perlite (Zeolite-NaA) results from treating perlite has a SiO2:Al2O3 ratio ~2 were used as an adsorbents for the removal of 144Ce and 152+154Eu. The two adsorbents were fully characterized. The factors affecting the sorption of radionuclides onto expanded and modified perlite including contact time, pH, ion concentration were investigated. The modification process of expanded perlite enhanced the removal of 152+154Eu from 17.0 to 97.0 %, while for 144Ce from 22.0 to 91.0 %. Both 144Ce and 152+154Eu obey Langmiur isotherm model in case of using modified perlite (Zeolite-NaA) and expanded perlite.

Incorporation of fulvic acid (FA) into the framework of hydroxyapatite particle to synthesis NHAP functionalized with FA (NHAP-FA) as a new smart nanocomposite is achieved. Some analytical methods such as EDX, FTIR, XRD, and TEM defined it. Preliminary study on the possible radiolabeling of NHAP-FA with 141,143Ce, 152,154Eu, 159,161Gd as represented radio-lanthanides that are gaining more attention in the last decades is carried out. The obtained results were revealed that a significant sorption affinity of radio-lanthanides (~ 98%). Application on the environmental remediation towards the removal of some radionuclides (152,154Eu, 60Co, 99Mo, 63Ni and 137Cs) has been evaluated.

Rice husk was converted into activated carbon (AC) as a byproduct of agricultural waste in an electric furnace at 700 °C and chemically activated using three distinct processes: NaOH AC(C), acetic acid AC(C-1), phosphoric acid AC(C-2), and carbonization AC(C-3) without any chemical activation. To characterize the activated carbon and the removal efficiencies of Fe(III) and Mn(II) from aqueous solutions, various analytical tools were used. The results revealed that the capacities of the four adsorbents to adsorb Fe(III) or Mn(II) from an aqueous solution differ significantly. AC(C-3) was chosen for additional research. The impact of different operational factors, including pH, contact time, adsorbent dosage, starting metal ion concentration, interfering ions, and temperature, were investigated. The optimum pH values for Fe(III) and Mn(II) adsorption were found to be pH 3 and pH 6, respectively. The results obtained were utilized to assess the kinetics and thermodynamics of the adsorption process. The sorption of Fe(III) and Mn(II) ions was found to be a pseudo-second-order kinetic process, and the equilibrium data were fitted with the Langmuir isotherm. Additionally, the evidence suggests that an endothermic mechanism governs the adsorption process. The maximum adsorption capacities of Fe(III) and Mn(II) were 28.9 and 73.47 mg/g, respectively.

This study aims to identify the analytical and radiological characterization of scale TENORM waste produced from oil and natural gas productions in the western desert in Egypt and evaluates their radiological impacts. The mean activity concentration of 238U, 226Ra, 210Pb, 228Ra, 224Ra, and 40K measured in scale TENORM samples is 660 ± 63, 1979 ± 435, 1399 ± 211, 645 ± 104, 794 ± 116, and 556 ± 86 Bq/kg, respectively. Radiological hazard parameters (Raeq, Hex, Hin, etc.) were estimated form the scale TENORM waste sample. All the calculated hazard parameters were found greater than the permissible and recommended safe levels. So the exposure to radiations released from the accumulation of the petroleum scale TENORM waste may cause health risks to the operators and who inhale radioactive radon gases and/or ingest contaminants by radiotoxic nuclides of U, Th, Ra, and Pb. Also, the risks may be extended to the near and/or the general environment.

Adsorption features onto clay and modified surface clay with humic acid (clay-HA) is investigated. Natural clay material and clay-HA composite were characterized using FTIR, TGA, and DTA. Performan...

A new approach for extraction of 99Mo tracer as a lighter homolog of Seaborgium (Sg) by three different the ionic liquids are studied. Aliquat-336 [Aliq-336.Cl-] as anion exchange has been used for the preparation of three ionic liquid, namely: ([Aliq-336]+ [SCN]-), ([Aliq-336]+ [S]- ) and ([Aliq-336]+ [Fe(CN)6]-). Their potential extraction of carrier free 99Mo from HNO3 solutions has been evaluated. The obtained results demonstrated that successful extraction of carrier free 99Mo from HNO3 solutions is achieved. The ([Aliq-336]+ [Fe(CN)6]-) is found to give the highest extraction affinity for 99Mo than the others ionic liquids investigated. The preliminary results could be useful for the upcoming aqueous experiments of Seaborgium.

The aim of this work is directed to prepare nanoparticles of egg shell hydroxyapatite-humic acid (ESHAP-HA) as a novel composite material. FTIR, EDX, TEM, XRD, and SEM identified it. Sorption characteristic studies on ESHAP-HA at different pH of solutions, shaking time, initial ion concentration and complexing agent were performed at 152,154Eu, 99Mo and 63Ni. The results were demonstrated that selectivity removal of 152,154Eu (~96 %) rather than 99Mo (8.5 %) and 63Ni (26.7 %). The sorption capacity of 152,154Eu(III), 63Ni(II) and 99Mo(VI) are 80.1, 12.5 and 2.3 mg/g, respectively, onto the ESHAP-HA nanoparticles. Application on the eclectic removal of 152,154Eu from mixed radionuclides (152,154Eu, 60Co, and 137Cs) solution has been evaluated. It concluded that the prepared ESHAP-HA composite material is a promising and recommended for separation of radio lanthanides and/or actinides (such as Am) from nuclear liquid waste and/or contaminated aquatic environmental.

Increasing in the use of various radioactive elements in many applications over the past few decades has accompanied with an increase radioactive waste. Therefore, preparation of Al2O3 ZrO2 CeO2 nanocomposite material by sol-gel polymeric method is carried out. The nanocomposite material was characterized by some analytical techniques such as Fourier transform infrared (FTIR), Thermograviemtric & differential thermal analysis (TGA & DTA), X-ray diffraction (XRD) and scanning electron microscopy (SEM). Separation of 134Cs and 90Sr/90Y as a fission product present in radioactive waste effluents using the prepared nanocomposite was investigated. The result showed that removal of 94%, 44% and 8.5% for 134Cs, 90Sr and 90Y, respectively. The experimental results are fitted with pseudo-second-order kinetic model. Isotherm models of sorption process are calculated and it can be concluded that the Langmuir model more fitted than Freundlich model. The calculated thermodynamic functions exhibited that sorption behavior of 134Cs and 90Sr ions are spontaneous in nature and the positive value of ΔHo value indicates that the sorption is endothermic. The results demonstrated that the % sorption of 134Cs(I) and 90Sr(II) is sharply decreased in the presence of coexisting ions (Na, Mg and Cr) using nanoparticles of Al2O3 ZrO2 CeO2.

The radiological and elemental hazards indices of phosphate fertilizers and phosphogypsum waste were investigated by determination of their components concentration using Instrumental Neutron Activation Analysis (INAA) then comparing the resultant concentrations with the acceptable limit. The radioactivity of 40K, 232Th and 238U within the samples were determined using passive gamma ray spectroscopy. The environmental impact risk resulting from the utilization of these materials was evaluated by the computation of some parameters including; absorbed dose rate, annual effective dose equivalent, radium equivalent activity, hazard index for γ-rays, excess lifetime cancer risk, alpha index and annual gonadal dose equivalent. The results illustrated that these materials pose a radiological threat to the creature health. For non-carcinogenic risks, the data was fed into human health risk models to evaluate the potential health risk of heavy metals by computing the average daily intake of each pollutant via variant exposure pathways and subsequent determination of the hazard quotient, hazard index and total exposure hazard index. For carcinogenic risks, the incremental lifetime cancer risk was calculated. The outcomes give rise to that some parameters values are above the acceptable limit, this increases the probability of adverse health effects.

We aim to investigate the separation of carrier free 99Mo as a homolog of Sg (element-106) from HCl, HNO3, H2SO4 and HF solutions using Bio-resin impregnated by trioctylamine (TOA), (BR-TOA). Distribution coefficient (Kd) of carrier free 99Mo has been investigated under various conditions by batch mode. To get knowledge towards the chemical behavior of Sg(IV) and Sg(VI), set of different chemical system, including mixed reducing agent with an acid solution for possible reduction and/or subsequent separation of 99Mo species was tested. The preliminary results are demonstrated that possible separation of different species of 99Mo as a homolog of Sg using BR-TOA.

We aim to recycle and utilization of eggshell as a biomass waste of human foodstuff. Pure hydroxyapatite nano-particles were prepared using waste eggshell at different temperature of 80 °C (ESHANP) and calcination at the 850 °C (CESHA) adsorbent materials and characterized by some instruments. Sorption studies of 60Co and 109Cd from aqueous waste solutions onto ESHANP and CESHA were performed at different pH solutions, initial ion concentration and contact time. The obtained data were analyzed using some kinetic, diffusion and isotherm models. It can be recommended ESHANP as remediation agent for nuclear waste sites.

Nano trigonal prismatic Ba

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 (K

The Prussian blue functionalized SiO2 (nano-material of SiO2-Fe-CN) was successfully prepared using a novel and simple preparation route. The SiO2 nanoparticles were functionalized by amino group by refluxing with (3-Aminopropyl) trimethoxysilane, iron (III) immobilized the modified nanoparticles through interaction with the amino group, finally, SiO2-Fe-CN nanomaterial produced as a result of potassium ferrocyanide addition. SEM, FTIR and XRD techniques were used for detecting the morphology, particle size, different functional groups and the crystal structure of the prepared nano-materials. The sorption potential of nano-material of SiO2-Fe-CN towards cationic and anionic radioisotopes from aqueous and HNO3 solutions were tested using carrier free method. The experimental results showed that nano-material of SiO2-Fe-CN have high effective retention and recovery for 134Cs, 60Co and 99Mo from nuclear liquid waste. Moreover, sorption of 90Sr/90Y is insignificant using SiO2-Fe-CN nano adsorbent material. It is a promising and efficient nano adsorbent that could be used for upscaling design and application on liquid radioactive waste treatment facility.

Three synthetic hematite (SH) materials as iron oxides nanofibers were prepared and applied for the removal of 51Cr and radioiodine (131I) as anions associated with nuclear industry technology. The results exhibited that 70% of Cr(VI) and 90% of 131I were removed from aqueous solution using the SH1 adsorbent. In acid solutions, R % of Cr(VI) increased to > 90% with the decrease in concentration till 0.05M, while the R % of 131I was 94 and 79% at HNO3 and HCl, respectively. It was concluded that SH1 nanofibers is promising and selective adsorbent for Cr(VI) and 131I removal from aqueous or acid solutions.

The main objective of this study is directed to remove 226Ra, 228Ra radionuclides from TENORM scale waste without seriously degradation the physicochemical characteristics of soils or generating waste. It was found that 82, 87% removal of total radioactivity using successive washing by commercial and TX-100 solutions, respectively, after seven cycles. Some radiation risk before and after treatment with surfactants were determined. It is a promising and efficient as well as economic process. Our results from this task could provide a useful information for defining the establishing and operating on a pilot-scale plant for efficient and economic TENORM treatment.

Sorption of La3+, Eu3+, and Fe3+ onto new synthetic inorganic ion exchange material of aluminum silicotitante was investigated. The aluminum silicotitante (EX1, EX2, and EX3) are synthetic with dif...

In the present work, materials, namely mud, sand mud, ferruginous sandstone and sandstone with different densities are used to evaluate the effect of chemical composition and moisture content on the self-attenuation coefficient factor at γ-energy range from 59.5 to 1332.5 keV. The results revealed that the attenuation coefficient increases with increasing the moisture content until the material saturate with moisture. The average value of increasing linear attenuation coefficients based on increasing moisture content are 14.3%, 16.0%, 18.2%, 28.1% and 24.8% at γ-energies 59.5, 356.0, 661.7, 1173.4 and 1332.5 keV, respectively. Chemical composition of material affected on the values of attenuation, i.e. the elements with high density have high attenuation coefficient. Significant effect of self-attenuation correction factor was observed at low γ-energies up to 500 KeV. Application of the calculated correction of environmental sample with low radioactivity content has been carried out.

Synthesis and characterization of potassium zinc hexacyanoferrate (KZnFC) as nano ion exchanger material are performed. Sorption characterization investigations on the removal of some radionuclides (134Cs, 60Co), heavy metal (Pb2+) and lanthanides (Ce3+ and Gd3+) from aqueous and nitric acid solutions using mesoporous KZnFC ion exchange have been done. Selective removal of 134Cs rather than 60Co and Ce3+ (lanthanides) is achieved in aqueous solution and nitric acid solution, respectively. The maximum sorption capacity of 134Cs, 60Co, Pb2+, Ce3+ and Gd3+ is 170, 10.5, 3.88, 0.72 and 0.55 mg/g, respectively, onto nano-material of KZnFC.

A combined of various nuclear and analytical techniques were used for characterization of Egyptian zircon ore. Neutron activation analysis has been used for determination of the major, minor and trace elements from zircon ore. Non-destructive gamma-ray technique is also used for the radiometric analysis of zircon ore to quantify the natural radionuclides such as 238U, 235U, 232Th, 226Ra and 40K. Zircon ore has been characterized by different analytical tools such as Fourier transformer infrared (FTIR), X-ray fluorescence (XRF), powder X-ray diffraction (XRD), and scanning electron microscopy (SEM). In this study, a significant concentration of U, Th and rare earth elements (REEs) has been reported. The obtained results showed that the average activity concentration of 238U, 235U, 226Ra, 232Th and 40K are 4771±338, 230±17.1, 3588±125, 982±47.7 and 217±48.5 Bq/kg, respectively. The results indicated that 297, 318 and 838 mg/Kg for U, Th, REEs, respectively, using NAA. These results are consistent with those obtained by gamma-ray spectroscopy and/or XRF. It can be concluded that zircon ore is a riche with a valuable nuclear materials such as U, Th, Zr, and Hf. It is also containing a REEs of economic and industrial interest. Also, the different radiation hazardous parameters were found much higher than the permissible values.

The excitation functions of 89Y( $\alpha$ ,n) 92mNb, 89Y(d, $\alpha$ )87mSr, 89Y(d,2n)89cumZr and 89Y(d,p)90mY nuclear reactions using 10 MeV deuterons and 20 MeV $\alpha$ -particles were measured. Thin samples of Y2O3 were prepared on Al substrates using the sedimentation method. Two different stacks were irradiated for each nuclear reaction to cover all the energy range from threshold to maximum energy of the incident particle. Model calculations of the excitation functions of the above-mentioned nuclear reactions were performed using TALYS-1.6 and EMPIRE-3.2 codes. Variation of the input parameters on the TALYS code results were investigated by using different optical model parameters (OMP). The integral thick target yields were estimated for the investigated reactions based on the proposed average excitation functions.

Sorption of fission products onto polycondensed aluminosilicates (PC-AS(s)) is a relatively recent and gets out the mechanisms by which the formers are trapped. Here, PC feldspar (PC-FD), perlite (PC-PR) and their blend (PC-FDPR) were synthesized by the alkaline activation using Na-/K-silicates at Si-modulus of 1.35. XRD patterns revealed the semi-crystalline natures of sorbents. Na- and K-feldspars were detected in PC-FD while Na-based carbonate crystals were detected in others. Components of the poly(sialate-disiloxo) structure were detected in FT-IR spectra. Thermographs were deconvoluted and the amounts of the sticking and zeolitic water were estimated. Kinetic batches for sorption of 134Cs and 152+154Eu onto the elaborated yields were constructed. Ranking of sorbed amounts (qe) was varied from 134Cs (PC-FDPR>PC-FD>PC-PR) to 152+154Eu (PC-PR>PC-FD>PC-FDPR). Maximum qe was recorded at elevated temperature (323 K) to be 4.28 and 1.45 mg/g for 134Cs/PC-FDPR and 152+154Eu/PC-PR, respectively. Along all batches, chemi-sorption mechanism is common denominator. The effective diffusion coefficients (Di) were in the order of 10−14 m2/s. Both PC-FD and PC-FDPR recorded greater Di values of 134Cs than 152+154Eu. The low values of Ea (kJ/mol) reflected the weak adsorbats-adsorbents interactions. While, the high negative values of ∆S‡ suggested that the studied radionuclides were sorbed in associative reaction mechanism

Alpha spectrometry is one of the greatest nuclear techniques for identification and quantification of α-emitters in the environment due to nuclear fuel cycle operations, nuclear materials and geochemical studies or forensic medicine investigations. This study was conducted to re-evaluate and optimize the factors affecting the performance of a multi-chamber alpha spectrometer (EGG while the better resolution (FWHM) was ~36 keV. These values are lower than those warranted when supplied before 20 years. The minimum detectable activity (MDA) of the detectors varies between 0.8 and 3.1 mBq for the chamber in use. The alpha spectrometer was also verified by certified reference samples to measure activity concentration of alpha emitters (e.g., 238U, 232Th, 226Ra and 241Am) with acceptable coefficient of variance ( ζ -score (

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.

New Nanocopper ferrocyanide-silica nanoparticles (SiO2-CuFe-CN) NPs were synthesized by co-condensation (one-pot) procedure; the prepared composite were characterized using FTIR, XRD, EDS and SEM. The sorption affinity of nanocopper ferrocyanide-SiO2 materials towards 134Cs and 60Co radioisotopes from aqueous and nitrate medium were extensively studied. The factors affecting the sorption process such as mixing time, pH, metal ion concentrations and temperature were conducted. The experimental isotherm data were found to fit with both Langmuir and Freundlich isotherms. The thermodynamic parameters were evaluated. The results obtained proved that (SiO2-CuFe-CN) NPs is a promising material for the remediation of low level radioactive waste solutions contains 134Cs, 60Co, 99Mo and 90Sr of relatively low nitric acid concentration. The results obtained in the application section reveals that (SiO2-CuFe-CN) NPs gives high selective sorption of 99Mo radioisotope over other radioisotopes from 0.01 M HNO3.

BACKGROUND The removal and recovery of rare earth elements have gained great attention not only because of their industrial importance, but also from the viewpoint of environmental waste disposal. Ion exchange technology is currently the best way to remove and recover metal ions from aqueous solutions. Therefore, the aim of this work is to synthesize a thermally stable inorganic ion exchange material with high adsorption efficiency for lanthanides. RESULTS A number of aluminum silicotitanates (AST 1–31) have been synthesized under different conditions of preparation including molar ratio, concentration, ageing time and drying temperature. These materials were characterized structurally using Fourier transform infrared spectroscopy (FTIR), X-ray fluorescence (XRF), thermogravimetry (TG) and differential thermal (DT) analysis, scanning electron microscopy (SEM) and BET-surface area. The material was found to have the formula [Al6Si4TiO19] 8H2O. Their properties as potential inorganic ion exchange materials have been examined for the removal of La(III), Eu(III), Fe(III) from aqueous solution. CONCLUSION The adsorption of rare earth elements and iron was found to be 99 and 79%, respectively. Thus it is concluded that the AST inorganic exchanger is more efficient for recovery of rare earth elements than iron. © 2015 Society of Chemical Industry