Gallium oxide target was irradiated with 46 MeV alpha-particle beam, which produced 71,72As and 67Ga radioisotopes in the matrix. Separation of radio-arsenics from the bulk gallium target was carried out by caffeine, a nature-resourced reagent, extracted from black tea leaves. 71,72As radionuclides were preferentially attached with caffeine and precipitated with caffeine in 2 M Na2SO4 solution as caffeine was insoluble in aqueous medium under this condition. With increase in weight of caffeine, extraction of 71,72As and bulk gallium significantly increased. Bulk Ga along with 67Ga remained in the supernatant. Geometry optimization of caffeine–metal complex was carried out by theoretical computational analysis. DFT calculation corroborated with the experimental findings where As3+ preferentially binds with caffeine in presence of gallium and arsenic. As evidenced by the short As–O and As–N distances, the high binding energies are a result of the metal ion’s strong binding to the carbonyl and nitrogen centres, whereas no such result could be obtained in case of bulk gallium.

GeO2-doped magnesium-telluroborate transparent glasses were synthesized in the current investigation using the traditional melt-quench procedure. XRD and FT-IR were used to examine the glasses’ structural properties. Following the measurement of the density, various physical parameters (including oxygen molar volume, oxygen packing density, etc.) were estimated and examined. From the FTIR results, one can deduce that clear structural alterations are seen which support the presence and conversion of BO3 and BO4 units. This is a result of the glass network forming more GeO4, TeO4, and BO4 units, which means that decreased NBO is forming, and more stiff networks are forming as a result. The increase in the overall stretching force constant of the glasses may also have an impact on the elastic moduli. The optical parameters were studied as optical energy band gap, Urbach energy and refractive index of the fabricated glass. According to the HVL data, the current glasses have a significant ability to lessen the intensity of gamma rays with lower energy. The glass with a small amount of GeO2 has a high HVL, whereas the glass with a higher amount of GeO2 has a lower HVL, as shown by the HVL data. The G5 glass demonstrated its superiority as a shielding glass over the other glass samples (G1–G4).

In this investigation, the photons shielding factors for tungsten tellurite glasses with the yWO3–(90 − y)TeO2–10Na2O (y = 05, 10, 15 and 20 mol%), were reported. The penetration and attenuation factors for this system at various energies were reported using the Phy-X/PSD program. With increasing energy, it is observed that the linear attenuation coefficient (LAC) values, which range from 1.087–0.234 cm−1 (for TWN1) to 1.354–0.248 cm−1 (for TWN4), decrease exponentially. The LAC values were found to increase with the addition of WO3 from 1.087 to 1.354 cm−1 at 0.245 MeV and from 0.515 to 0.586 cm−1 at 0.444 MeV. Additionally, the greater potential for photon interactions at higher WO3 concentrations was indicated by the findings of the effective atomic number (Z eff) calculation. According to the obtained results, the maximal Z eff occurred at 0.284 MeV, which is equivalent to 32.53 for TWN1 and 36.89 for TWN4. The half value layer (HVL) for the samples under consideration between 0.245 and 1.458 MeV has been determined using the Phy-X/PSD. The HVL results demonstrated that at 0.284 MeV, more gamma rays are shielded whereas the potential of photon shielding decreases as energy increases. The tenth value layer (TVL) increased with rising energy and decreased with rising WO3 concentrations. TVL for TWN4 is the lowest (1.701 cm at 0.245 MeV and 9.284 cm at 1.458 MeV).

Adsorption of molybdenum was carried out on two materials; potassium doped γ-Al2O3 (KA) and bentonite iron oxide composite (BIOC) with purpose of using in production of chromatographic 99mTc generators, for KA absorbent, different ranges of potassium loadings have been considered, for BIOC solid the used weight ratio was (Bentonite/Fe = 2/1). Samples were characterized by XRD and WDXRF. Adsorption of MoxOy z− species was carried out at pH 2.5 and 25 °C, effects of contact time and pH were studied. The Mo adsorption data onto used materials were well fitted using Freundlich and Langmuir models. Doped alumina samples showed higher adsorption capacities (∼90 mg g−1) than the usual alumina used in generator technology (∼60 mg g−1), whereas adsorption capacities of BIOC solid were in the range of (∼75 mg g−1).

Self-absorption effect has a significant impact on gamma spectrometry measurement for the highly precise determination of the radionuclides activity. Among the main factors affecting the self-absorption effect especially at low gamma energies is the matrix composition of the sample. For this purpose, we studied the matrix composition effect on the self-absorption correction for plant and soil matrices using a Monte Carlo simulation model, composed of High Purity Germanium (HPGe) detector and a cylindrical geometry source. The simulated configuration model was validated by comparison of simulated full energy peak efficiency (FEPE) values with the experimental ones using a standard radioactive solution, covering large interval gamma energies in the range of 59.54–1836.12 keV. The results show that the FEPE values of low gamma energies are affected by the matrix composition, where in the soil matrix the FEPEs decreased by 36% and only by 1% in the plant matrix. The Monte Carlo results were applied in order to accurately calculate the transfer factor of the environmental radionuclides 226Ra, 232Th and 40K from soils to several crops, mustard, artichoke and fennel through their specific activities.

Bee pollen and bee bread are considered for a good source of nourishing and polyphenol substances which may act as powerful antioxidants. Some main phenolic compounds of studied non-irradiated and irradiated samples were identified and compared by high performance liquid chromatography (HPLC). The effects of irradiation treatment of bee pollen and bee bread on their phenolic content were studied. For this purpose, the samples were γ-irradiated with 2, 5, 10 and 20 kGy. The results show that the ionizing radiation affect phenolic content of analyzed samples depends on the dose and the chemical composition of honey bee product. The identified phenolic substances and changes in their amount after irradiation were related to free radical scavenging activity (FRSA) of studied samples. FRSA of bee pollen and bee bread were determined by electron paramagnetic resonance (EPR). Gamma treatment with 5 kGy has a positive effect on antioxidant potential at both honey bee products.

Today about 440 nuclear power plants, with total installed capacity of 390 GW(e) are in operation worldwide generating around 10% of global electricity which are largely fuelled by enriched uranium oxide [Nuclear Power in the World Today. http://world-nuclear.org/information-library/current-and-future-generation/nuclear-power-in-the-world-today.aspx]. Thorium is 3–4 times more abundant than uranium and needs to be exploited by countries with limited stock of uranium. Historically, there have been several attempts to develop Th based reactors, but none has reached commercial scale. In recent years, High Temperature Reactor based on thorium has gained prominence for production of hydrogen with long term goal of complete carbon neutrality. However, unlike natural uranium, which contains ∼0.7% fissile 235U isotope, natural thorium does not contain any ‘fissile’ material and is made up exclusively of the ‘fertile’ 232Th which can be converted to ‘fissile’ 233U, thereby enlarging the fissile material resources. However, there is a need to develop robust closed fuel cycle to address to the challenges of high gamma dose due to the presence of decay products of 232U. It is necessary to gain more experience with promising THOREX process to achieve the desired recovery and D.F. of 233U from the irradiated 232Th. There is also scope to have a close look at some of the alternative extractants and emerging separation techniques for the reprocessing of spent Th based fuels. In view of the distinct advantages of non aqueous reprocessing over aqueous reprocessing, there is need to intensify the efforts to develop the former on a commercial scale. Molten Salt Breeder Reactor (MSBR) is particularly promising in this context. There is a need to investigate Th as energy amplifier under Accelerator Driven Sub-critical System (ADSS) which has potential to burn long lived radio nuclides, considered as a threat to environment over million of years.

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 paper presents first investigations on a novel An(III), Ln(III), Cs(I) and Sr(II) co-extraction conceptual process using a CHON solvent composed of the calixarene crown-ether MAXCalix and the diglycolamide TODGA in a 1-octanol/kerosene diluent. The co-extraction is followed by a sequential stripping of (1) Cs(I) and Sr(II), (2) An(III) and (3) Ln(III).

The hydrothermal preparation of active MnO2 via KMnO4 and MnSO4.H2O as inorganic forerunners is demonstrated, and it is evaluated as an adsorbent for the 99Mo produced by 235U fission. The structure and morphology of MnO2 were distinguished using various methods such as FTIR spectrum, FESEM, EDX, XRD, TGA. The 99Mo adsorption conduct on active manganese oxide was investigated, and the Mo uptake capacity was determined using static and dynamic techniques, and it was found to be 22.8 ± 1 and 6.72 ± 0.3 mg/g MnO2, respectively. This sorbent material was used in preliminary studies to prepare a 99Mo/99mTc generator. 99mTc eluted from the prepared generator was estimated to be 78–82 % with a low 99Mo breakthrough (0.002 %) and acceptable radiochemical, radionuclidic, and chemical purities.

The cross-sections for the 197Au(p,pxn)196-193Au and 197Au(p,xn)197,195,193Hg reactions within the proton energy range of 49.8–65.5 MeV were measured at the high-intensity proton linac facility (KOMAC) in Korea using the stacked-foil activation and off-line γ-ray spectrometric technique The proton beam intensity was determined based on the natCu(p,x)62Zn monitor reaction with the recommended cross-section accessed from the IAEA database library. The data gathered in the present work are compared with the available data from the literature, which agreed well with each other. In this study, the 197Au(p,p5n)193Au reaction cross-section was measured for the first time. The data from the present work and existing literature were compared with the TALYS-1.9-based data taken from the TENDL-2019 library, which generally agreed well.

Two new Np(V) azide complexes with electroneutral N-donor ligands of terpyridine derivatives have been synthesized and structurally characterized: [(NpO2)(Cl-Terpy)(N3)(H2O)] (1) and a centrosymmetric dimer [(NpO2)(EtO-Terpy)(N3)]2·2CH3OH (2). The coordination polyhedra of Np atoms in compounds are pentagonal bipyramids with “yl” oxygen atoms in apical positions. The equatorial plane of the bipyramid in complex 1 is formed by: a nitrogen atom from an anion, three nitrogen atoms from an electroneutral Cl-Terpy ligand and an oxygen atom of a water molecule. The equatorial plane of bipyramids in dimer 2 is formed by five nitrogen atoms: two atoms from two anions [N3]− and three atoms from EtO-Terpy. In compound 1, the anion [N3]− acts as a monodentate ligand, and in compound 2, the anion [N3]− is a bidentate-bridging ligand.

An iridium-192 miniature sealed source was produced by irradiation of 12 metal disks of natural iridium (470.5 mg) under a thermal neutron flux of 9.4 × 1013 n cm−2 s−1 during 200 h in Es Salam research reactor (Algeria). The preliminary activity was measured after 10 days decay time by a CAPINTEC type CRC-712 M dose calibrator, the given activity was 1.9 × 1011 Bq (5.2 Ci). To estimate source activity, a modeling of reactor core and irradiation container with the targets was made by MCNP5 code with and without iridium targets to evaluate the effect of the disturbance and reaction; the calculated activity using disturbed flux was comparable with that measured. A non-destructive test using 192Ir sealed sources with GammaMat TSI type B(U) projectors was carried out to evaluate the integrity of the weld joint at the bend of a carbon steel pipe. The weld quality of two plates; carbon steel and stainless steel was also evaluated. In terms of sensitivity, the resulting gamma images matched well and reported a real finding on the state of tested samples.

The key fragment element samarium (Sm) has a large neutron absorption cross section, which can hinder the absorption of neutrons by uranium and negatively affect the nuclear reaction. In order to realize the nuclear fuel cycle, the extraction of Sm was studied on the basis of electrolytic refining after the dry process. The electrochemical properties of SmCl3 and SnCl2 in LiCl-KCl molten system were systematically investigated by cyclic voltammetry (CV), square wave voltammetry (SWV), and open circuit potential (OCP). The diffusion coefficients of the Sn(II) and Sm(III) electrode processes were calculated to be 3.55–5.93 × 10−5 and 2.33–3.97 × 10−5 cm2 s−1, respectively. The co-reduction of Sm(III) and Sn(II) ions was studied. Sm was recycled by constant current electrolysis on the liquid Sn electrode, and the average extraction rate was about 94.23%. The samples were characterized and analyzed by X-ray diffraction analysis (XRD) and scanning electron microscopy coupled with energy-dispersive X-ray spectroscopy (SEM), and the results showed that Sm extraction from liquid tin is feasible.

Mushrooms are highly perishable in nature and deteriorate within a few days after harvesting due to their high respiration rate and delicate epidermal structure. Consequently, the shelf-life of freshly harvested mushroom is limited to 1–3 days at ambient condition. Hence, the current investigation was carried out to study γ-irradiation effects (1.5 and 2.0 kGy) and essential oils (EOs) fumigation including geranium (60 and 80 μL/L) and lemongrass (40 and 60 μL/L) on nutritional quality (Vitamins C and D2) as well as bio-ingredients such as total soluble proteins, phenolic and flavonoids contents, antioxidant activity were determined as an origin of potential natural antioxidant plus the profile of phenols and flavonoids identified by HPLC. As well as activities of some enzymes (PPO, SOD, PAL, and APX) of Agaricus bisporus mushroom at 4 °C during storage time for twelve days. The findings showed that there was a reduction in the contents of Vit. C and vitamin D2 in all mushroom samples during storage, where the essential oil treatment especially 60 μL/L of geranium and 40 μL/L of lemongrass gave the least decrease (3.42 and 3.28 mg/100 g FW, respectively) of ascorbic acid content compared to the other treatments while the irradiated samples (1.5, and 2.0 kGy) gave the lowest decrease of vitamin D2 (106.30 and 114.40 mg/kg DW, respectively) at the end of storage time. The content of the bio-ingredients content was affected by the storage periods, and the samples treated with oil fumigation gave the best content and the same trend happened with the antioxidant activity. The enzymes activity increased by the storage period, especially after 4 days of storage, and then the activity decreased after that. Quantification of phenolic and flavonoid compounds affected by storage periods in all treatments and the EO-treated mushrooms gave the best amount of them. Thus, samples of mushrooms treated with oil fumigation especially 60 μL/L of geranium and 40 μL/L of lemongrass can successfully increase the nutritional value plus maintain the value of the mushrooms during storage time.

Electricity generation using nuclear power has various advantages, such as carbon reduction, but the treatment of nuclear waste is emerging as a big issue in many countries. The development of technology that can selectively remove radionuclides from liquid radioactive waste is one of the ways to reduce nuclear waste. Here, we assessed a new way of removing radioactive cobalt from a liquid using an aptamer. Aptamers specifically binding cobalt ions were selected through systematic evolution of ligands by exponential enrichment (SELEX). Their binding strength and stability of their complexes with cobalt were analyzed through surface plasmon resonance assay and 2D program Mfold, respectively. The optimal aptamer/bead conjugate conditions for binding cobalt were established using an FA-C1 aptamer with the strongest binding to cobalt. Under these conditions, more than 80% of radioactive cobalt was removed, and more than 99.95% of removed cobalt was recovered. These results proved that radioactive cobalt removal using this aptamer can effectively reduce liquid radioactive waste. This means that the aptamer/bead complex can be utilized to remove various radioactive metal ions.

In this study, glass composition based on tungsten oxide (WO3) doped tellurium, titanium glasses: (100 − x − y) TeO2–xTiO2–yWO3: where (x = 5) and (y = 5, 10, 15, 20, 25) coded as TT5W5, TT5W10, TT5W15, TT5W20, and TT5W25 were investigated for shielding properties against ionizing radiation. Gamma radiation shielding parameters such as mass attenuation coefficients (MAC) are calculated through MCNPx code and Phy-X/PSD software in the energy range of 0.015–15 MeV. Obtained MAC values are then used to calculate other gamma radiation shielding parameters such as mean free path (MFP) and effective atomic number (Z eff). Besides this, the exposure buildup factor (EBF) was also calculated by using EXABCal software at different penetration depths (PDs) in the energy range of 0.015–15 MeV. Sample TT5W25, which has a larger WO3 content of 25 mol% shows higher values of MAC and lower values of MFP among all the examined glass samples. Our investigated TeO2–TiO2–WO3 glass samples possess the lowest MFP values in comparison with the different types of concretes and commercially available shielding glasses. In addition, fast neutron shielding characteristics in light of fast neutron removal cross-section have also been computed. Glass sample TT5W25 possesses the higher values of fast neutron removal cross-section as compared to the other glass samples. The results indicate that the adding up of WO3 improves shielding against the fast neutron and gamma radiation.

Cross sections of the 86Sr(p,3n)84mY, 86Sr(p,αn)82mRb, and 86Sr(p,x)85gSr reactions were measured from their respective thresholds up to 16.2 MeV and from 23.0 to 44.1 MeV at FZJ, and from 14.3 to 24.5 MeV at LBNL, using 96.4% enriched 86SrCO3 as target material. Thin targets prepared by sedimentation were irradiated with protons in a stacked-form, and the induced radioactivity was measured by high-resolution γ-ray spectrometry. Nuclear model calculations based on the code TALYS reproduced our experimental cross section data well. From the excitation functions, the integral yields of the above three radionuclides were calculated. The yield of 85gSr via the natSr(n,γ) process was also measured using the TRIGA Mark-II reactor at AERE, Savar. A comparison of the reactor and cyclotron production of carrier-added 85gSr is given. The production possibilities of the three investigated radionuclides in no-carrier-added forms at a 30 MeV cyclotron via new routes are discussed.

Uranium removal from wet phosphoric acid is a vital process for food and environmental security. The incorporation of thiourea-formaldehyde into the kaolinite networks was performed to obtain an effective and acid-resistant sorbent. The prepared composite was applied for U(VI) uptake from crude phosphoric acid. X-ray diffraction, EDX, scanning electron microscopy, and Fourier transform infrared analyses were carried out to explore the properties of the yield composite. The sorption characteristics, i.e., capacity, kinetic, isotherm, and thermodynamic were investigated. The anticipated data declare that the reaction is fast whereas 60 min is sufficient to reach the equilibrium state. The experimental results obeyed to Pseudo second-order kinetic model and Langmuir isotherm model. The maximum sorption capacity was about 5.8 mg g−1. Thermodynamic parameters displayed that the sorption process is endothermic, feasible, and spontaneous. The displayed results demonstrate that the prepared composite could be used as the proper material for producing eco-friendly fertilizers.

Theoretical predictions were made using TALYS-1.95(G) and EMPIRE 3.2 reaction-model codes for 69Ge, 67Ge, and medically used 68Ge, 67Ga, 68Ga, 65Zn, 64Cu radionuclides produced in the interaction of α-projectile with 66Zn-target at 10–40 MeV α-energies. Pearson’s statistical coefficients showed moderate to strong positive correlations between the theoretically predicted and experimentally measured production cross sections for radionuclides with practical medical applications. Furthermore, the present results indicated that a medium-sized cyclotron and a single α + 66Zn system (projectile + target system) might be an option for optimized production of 68Ge, 68Ga, 67Ga, 65Zn, and 64Cu radionuclides.