Showing papers in "Journal of Radioanalytical and Nuclear Chemistry in 2018"
TL;DR: A brief background of the development of the theranostic approach in nuclear medicine is given and seven radionuclide pairs, namely 44gSc/47Sc, 64Cu/67Cu, 83Sr/89Sr, 86Y/90Y, 124I/131I, 152Tb/161Tb and 152tb/149Tb, are considered as mentioned in this paper.
Abstract: A brief historical background of the development of the theranostic approach in nuclear medicine is given and seven theranostic pairs of radionuclides, namely 44gSc/47Sc, 64Cu/67Cu, 83Sr/89Sr, 86Y/90Y, 124I/131I, 152Tb/161Tb and 152Tb/149Tb, are considered. The first six pairs consist of a positron and a β−-emitter whereas the seventh pair consists of a positron and an α-particle emitter. The decay properties of all those radionuclides are briefly mentioned and their production methodologies are discussed. The positron emitters 64Cu, 86Y and 124I are commonly produced in sufficient quantities via the (p,n) reaction on the respective highly enriched target isotope. A clinical scale production of the positron emitter 44gSc has been achieved via the generator route as well as via the (p,n) reaction, but further development work is necessary. The positron emitters 83Sr and 152Tb are under development. Among the therapeutic radionuclides, 89Sr, 90Y and 131I are commercially available and 161Tb can also be produced in sufficient quantity at a nuclear reactor. Great efforts are presently underway to produce 47Sc and 67Cu via neutron, photon and charged particle induced reactions. The radionuclide 149Tb is unique because it is an α-particle emitter. The present method of production of 152Tb and 149Tb involves the use of the spallation process in combination with an on-line mass separator. The role of some emerging irradiation facilities in the production of special radionuclides is discussed.
92 citations
TL;DR: In this paper, a three-dimensional porous polydopamine functionalized attapulgite/chitosan (AT@PDA/CS) aerogel was designed and prepared for uranium(VI) adsorption, and its morphology and structure were characterized by TEM, SEM-EDS, XRD, FT-IR, Raman and XPS techniques.
Abstract: A novel three-dimensional porous polydopamine-functionalized attapulgite/chitosan (AT@PDA/CS) aerogel was designed and prepared for uranium(VI) adsorption, and its morphology and structure were characterized by TEM, SEM-EDS, XRD, FT-IR, Raman and XPS techniques. According to batch experiments, its adsorption equilibrium was reached within 40 min at pH 5.0. The adsorption isotherms was fitted well for Langmuir isotherm model and maximum adsorption capacity was 175.1 mg g−1 at 328 K. The thermodynamic analysis indicated that the adsorption was an endothermic and spontaneous process. Furthermore, the aerogel has superior absorption reusability and the removal efficiency was maintained at 78% after five adsorption–desorption cycles.
44 citations
TL;DR: In this paper, the adsorption of uranium from a nitric acid waste solution using the cation exchange resin Amberjet 1200 H (AHR) has been investigated in order to assess the performance of AHR in uranium adaption.
Abstract: The present work deals with the adsorption of uranium from a nitric acid waste solution using the cation exchange resin Amberjet 1200 H (AHR) . Batch experiments were performed in order to assess the performance of AHR in uranium adsorption. The influences of pH, contact time, initial uranium concentration and temperature have been enhanced. The physical parameters including the adsorption kinetics, the isotherm models and the thermodynamic data have also been determined to determine the nature of the uranium adsorption by AHR. The studied resin has been agreed with both the pseudo second order reaction and Langmuir isotherm.
44 citations
TL;DR: A review and discussion on the LSC based analytical methods for the determination of major radionuclides in environmental researches, decommissioning of nuclear faculties and nuclear application are presented, in both measurement techniques and sample preparation using radiochemical separation as discussed by the authors.
Abstract: Liquid scintillation counting (LSC) is a major technique not only for measurement of pure beta emitting radionuclides, but also radionuclides decay by electron capture and alpha emission. Although it is a conventional radiometric technique, but still a competitive techniques for the measurement of many radionuclides. This paper summaries the major development of this measurement technique in instrumentation, methodology and applications in the past decades. The progresses in the instrumentation and methodology mainly focus on the commercialization of triple-to-double coincidence ratio based LSC techniques and its application in the determination of different radionuclides. An overall review and discussion on the LSC based analytical methods for the determination of major radionuclides in environmental researches, decommissioning of nuclear faculties and nuclear application are presented, in both measurement techniques and sample preparation using radiochemical separation. Meanwhile the problems and challenges in the development and application of the LSC are also discussed.
42 citations
TL;DR: This paper discusses both production and recycling potential of nitride fuels, which have a better thermal conductivity than the oxides and a similar melting point and thus have larger safety margins to melting during operation.
Abstract: Nuclear energy has been a part of the energy mix in many countries for decades. Today in principle all power producing reactors use the same techniqe. Either PWR or BWR fuelled with oxide fuels. This choice of fuel is not self evident and today there are suggestions to change to fuels which may be safer and more economical and also used in e.g. Gen IV nuclear power systems. One such fuel type is the nitrides. The nitrides have a better thermal conductivity than the oxides and a similar melting point and are thus have larger safety margins to melting during operation. In addition they are between 30 and 40% more dense with respect to fissile material. Drawbacks include instability with respect to water and a sometimes complicated fabrication route. The former is not really an issue with Gen IV systems but for use in the present fleet. In this paper we discuss both production and recycling potential of nitride fuels.
39 citations
TL;DR: For the first time, the pollution of the paddy soil within 2 km around the uranium tailing reservoir was investigated in this article, where the concentrations of U, Cd, Cr, Pb, Cu, Zn, Hg and As were determined by ICP-MS.
Abstract: For the first time the pollution of the paddy soil within 2 km around the uranium tailing reservoir was investigated. The concentrations of U, Cd, Cr, Pb, Cu, Zn, Hg and As were determined by ICP-MS. The study showed that there was severe pollution in the first area (within 0–1 km of the tailing reservoir), which was caused by Cd, As, U and Hg. The pollution level of the second area (within 1–2 km) was relatively low. Hg and As were the main pollutants. In the first area,
the contamination degree and risk of elements were positively correlated with the distance from the tailing reservoir. The second area was less polluted and influenced by mining and human activities because of mountain barriers.
34 citations
TL;DR: In the course of the study, COOH-GO demonstrated superior performance as a sorbent material for the selective removal of uranyl ions from aqueous solution with a distribution coefficient of 3.72 ± 0.19 × 103 mL g−1 in comparison to GO and graphite.
Abstract: The effect of competing ions on the sorption behaviour of uranium onto carboxyl-functionalised graphene oxide (COOH-GO) were studied in batch experiments in comparison to graphene oxide (GO) and graphite. The effect of increasing the abundance of select chemical functional groups, such as carboxyl groups, on the selectivity of U sorption was investigated. In the course of the study, COOH-GO demonstrated superior performance as a sorbent material for the selective removal of uranyl ions from aqueous solution with a distribution coefficient of 3.72 ± 0.19 × 103 mL g−1 in comparison to 3.97 ± 0.5 × 102 and 2.68 ± 0.2 × 102 mL g−1 for GO and graphite, respectively.
33 citations
TL;DR: In this paper, 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.
Abstract: 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.
33 citations
TL;DR: In this article, a novel magnetic core-dual shell Fe3O4@PDA@TiO2 adsorbents was successively prepared by polydopamine (PDA) coated and TiO2 film deposited on the surface of Fe 3O4.
Abstract: In this study, a novel magnetic core–dual shell Fe3O4@PDA@TiO2 adsorbents was successively prepared by polydopamine (PDA) coated and TiO2 film deposited on the surface of Fe3O4. The structure and properties were characterized by FT-IR, SEM–EDS TEM, VSM and XPS. The adsorption of U(VI) on Fe3O4@PDA@TiO2 was investigated as a function of contact time, solution pH, initial U(VI) concentration and other interfering ions. In addition, the U(VI) adsorption from practical wastewater and simulated seawater was also investigated. The results implied that the Fe3O4@PDA@TiO2 adsorbents exhibited promising adsorption performance for uranium (VI) from aqueous solution and simulated seawater.
31 citations
TL;DR: In this article, the authors focused on the sorption of uranium, lanthanum and europium ions from low grade monazite leachate and found that the removal percent for Eu3+, La3+ and UO2 2+ are 94.6, 91.6 and 73.4%, respectively.
Abstract: Gamma radiation polymerization method was used for the modification of kaolin to produce (poly acrylamide-acrylic acid)-Kaolin (PAM-AA-K). Monazite ore is one of the main resources of uranium and lanthanide elements, therefore, this work focused on sorption of uranium, lanthanum and europium ions from low grade monazite leachate. The removal percent for Eu3+, La3+ and UO2
2+ are 94.6, 91.6 and 73.4%, respectively. Monolayer capacity of Eu3+, La3+ and UO2
2+ were found to be 54.64, 45.87 and 37.59 mg/g, respectively. The sorption mechanism of lanthanum and europium ions on PAM-AA-K composite mainly takes place as Ln(OH)2+, and for uranium as uranyl ion, UO2
2+.
31 citations
TL;DR: In this paper, the drying of the cooling pond of Chernobyl NPP, which will cause the weathering of previously preserved fuel particles in the (former) sediment of the pond, is discussed.
Abstract: Radioactive particles have been released from multiple sources since the mid-twentieth century. Famous examples include nuclear fuel particles from Chernobyl, glassy microparticles from Fukushima as well as particles from nuclear weapons production facilities (e.g., Windscale, United Kingdom and the facilities in the former Soviet Union), nuclear weapons accidents at Palomares (Spain) and Thule (Greenland), and atmospheric nuclear explosions. Current challenges in environmental research of radioactive particles include the drying of the cooling pond of Chernobyl NPP, which will cause the weathering of previously preserved fuel particles in the (former) sediment of the pond. Environmental aspects of resuspended particles as well as natural particles and aerosols contaminated with radionuclides (e.g., 131I) are briefly discussed.
TL;DR: In this paper, a novel graphene oxide/bentonite composite was synthesized and then characterized through powder X-ray diffraction, fourier transform infrared spectroscopy, thermogravimetric analysis, scanning electron microscopy, and energy dispersive spectrography.
Abstract: A novel graphene oxide/bentonite composite (GO/bentonite) was synthesized and then characterized through powder X-ray diffraction, fourier transform infrared spectroscopy, thermogravimetric analysis, scanning electron microscopy, and energy dispersive spectroscopy. Adsorption achieved equilibrium within 10 min. Moreover, U(VI) adsorption on GO/bentonite was highly dependent on solution pH and independent of ionic strength. These characteristics suggested that inner-sphere surface complexes of U(VI) formed on GO/bentonite. The adsorption of U(VI) from aqueous solution on GO/bentonite was fitted to the pseudo-second-order and Freundlich isotherm models. The maximum sorption capacity of GO/bentonite was 234.19 mg g−1 under neutral pH at 303 K. GO/bentonite is a potentially powerful adsorbent for the efficient removal of U(VI) from aqueous solutions.
TL;DR: In this article, the effect of strontium ions on manganese oxides obtained by sol-gel technique reduction of KMnO4 by different reagents (H2O2, MnCl2 and polyvinyl alcohol) was studied.
Abstract: Sorption behavior of strontium ions on manganese oxides obtained by sol–gel technique reduction of KMnO4 by different reagents (H2O2, MnCl2 and polyvinyl alcohol) was studied. Sorption capacity of the most effective sorbent reaches 200 mg g−1 and distribution coefficient Kd (85Sr)—3.67 × 105 cm3 g−1. Ion-exchange and chemisorption mechanism of strontium ions removal by manganese oxides were confirmed by means XRD, FT-IR, N2 adsorption–desorption and SEM–EDX methods. The obtained sorbents are promising for liquid radioactive water treatment from strontium radionuclides.
TL;DR: In this article, the U(VI) adsorption of pine needles prior and after carbonization and following oxidation has been investigated by batch-type experiments and characterized by FTIR and SEM measurements.
Abstract: Adsorption of U(VI) by pine needles prior and after carbonization and following oxidation has been investigated by batch-type experiments and characterized by FTIR and SEM measurements. The experimental data have been fitted by the Langmuir adsorption isotherm and the highest adsorption efficiency was observed for the carbonized and surface oxidized material, followed by the non-treated pine needles and the carbonized material. The highest U(VI) adsorption observed after surface oxidation of the carbonized material is attributed to the presence of carboxylic moieties, which possess increased affinity for the U(VI) cations and form inner-sphere surface complexes.
TL;DR: In this paper, the activities of 238U, 226Ra, 232Th and 40K nuclides in DAP, potash and NPK fertilizers commonly used in Viet Nam were measured using a high-purity germanium (HPGe) detector.
Abstract: Chemical fertilizers contain a significant amount of natural radionuclides 238U, 226Ra, 232Th and 40K, which can be dispersed into environment due to a high use of fertilizer in agriculture and increase the external and internal doses to the population In this study, the activities of 238U, 226Ra, 232Th and 40K nuclides in DAP, potash and NPK fertilizers commonly used in Viet Nam were measured using a high-purity germanium (HPGe) detector Experimental results showed that for DAP fertilizer, the activities of 226Ra, 232Th and 40K nuclides had low values, of 34, 94 and 346 Bq/kg, respectively For potash and NPK fertilizers, activities of 226Ra and 232Th nuclides were lower 55 Bq/kg for 226Ra and 176 Bq/kg for 232Th, but those of 40K were about thousands Bq/kg Based on the measured activities, the radiological health hazard parameters, such as Raeq, Hex, OADR, OAED, IAED, ELCRin, were calculated The result showed that for DAP fertilizer, these parameters were within allowed ranges, whilst most of them in potash and NPK fertilizers exceeded the permissible limits
TL;DR: Samples of the zeolite have been tested in column experiments to determine their ability to remove radioactive Cs+ and Sr2+ ions under increasing concentrations of competing ions, Ca2+, Mg2+, Na+ and K+.
Abstract: Mud Hills clinoptilolite has been used in an effluent treatment plant (SIXEP) at the Sellafield nuclear reprocessing site. This material has been used to remove 134/137Cs and 90Sr successfully from effluents for 3 decades. Samples of the zeolite have been tested in column experiments to determine their ability to remove radioactive Cs+ and Sr2+ ions under increasing concentrations of competing ions, Ca2+, Mg2+, Na+ and K+. These ions caused increased elution of Cs+ and Sr2+. Ca2+, Mg2+ and K+ were more effective competitors than Na+. For Na+, it was found that if concentration was reduced, then column performance recovered rapidly.
TL;DR: In this article, three different heterocyclic dicarboxamides (2,6-pyridinedic-carboxamide, 2,2-bipyridine-6,6′-dicara-boxamide and 1,10-phenanthroline-2,9-DICAR-amides) were studied.
Abstract: Extraction of actinides from aqueous nitric acid by three different heterocyclic dicarboxamides (2,6-pyridinedicarboxamide, 2,2′-bipyridine-6,6′-dicarboxamide and 1,10-phenanthroline-2,9-dicarboxamides) was studied. It was shown that all studied ligands extract actinides at different oxidation states (U(VI), Np(V), Pu(IV), Am(III), Cm(III)) from acidic solutions. All studied diamides extract Am(III) better than Cm(III). Et(pHexPh)ClPhen contains electron-withdrawing chlorine atoms at the positions 4 and 7 of the phenanthroline moiety (SFAm/Cm = 4–6) and possesses the highest separation factor Am(III)/Cm(III). The studied ligands possess high extraction ability to all actinides present in HLW and therefore they could be used for simultaneous extraction of actinides in the GANEX-type process.
TL;DR: In this paper, the COSINE experiment is searching for dark matter using ultra-low background NaI scintillating crystals, where NaI powder samples with different purities were purified by fractional recrystallization using de-ionized water.
Abstract: The COSINE experiment is searching for dark matter using ultra-low background NaI scintillating crystals. In order to reduce the internal contamination of the initial NaI powder to grow NaI crystals, NaI powder samples with different purities were purified by fractional recrystallization using de-ionized water. The concentrations of the main radioactive elements, K, Pb, Th, and U, which are major backgrounds for the dark matter search, were reduced to the level required for the experiment. Further, the concentrations of other impurities, e.g., Ba, Ca, Cr, and Fe, were also reduced, which is important to realize good quality NaI crystals.
TL;DR: In this paper, Radon (222Rn) isotope has been used to quantify SGD in coleroon river estuary, India and continuous Radon analyses were attempted for 10 days in groundwater and pore water samples at three different locations.
Abstract: Submarine groundwater discharge is the fresh groundwater discharge to sea that impacts the coastal regions. Radon (222Rn) isotope has been used to quantify SGD in coleroon river estuary, India. Continuous 222Rn analyses were attempted for 10 days in groundwater and pore water samples at three different locations. 222Rn in groundwater ranges between 35.0 and 222.0 Bq m−3 and in pore water between 14.0 and 150.0 Bq m−3 irrespective of locations. The radon mass balance estimated total SGD rate ranges between 2.37 and 7.47 m days−1. The SGD increases with distance from coast, influenced by tides and hydrological features.
TL;DR: In this paper, carboxyl-modified multiwalled carbon nanotubes were immobilized in chitosan-based composite membranes (CS-CNTs) which were used as efficient sorbents for U(VI) sorption.
Abstract: The carboxyl-modified multiwalled carbon nanotubes were immobilized in chitosan-based composite membranes (CS-CNTs) which were used as efficient sorbents for U(VI) sorption. The incorporation of CNTs in the CS-CNTs membranes improves their mechanical strength as well as U(VI) sorption performance. XPS analysis indicates that both amine and carboxyl groups are responsible for the complexation of U(VI). The sorption kinetics followed the pseudo-second order equation, whereas the sorption isotherms fitted well with Langmuir model (qm = 126.7 mg g−1 at 298 K). Moreover, the U(VI)-loaded CS-CNT8 can be effectively desorbed by 0.2 M acidified EDTA and reused.
TL;DR: In this paper, carboxymethylated chitosan (CMC)/Na-bentonite (Na-Bt) composite membranes were prepared and throughly characterized.
Abstract: The carboxymethylated chitosan (CMC)/Na-bentonite (Na-Bt) composite membranes were prepared and throughly characterized. The Na-Bt/CMC mass ratio was optimized, and CB10 (membrane with Na-Bt/CMC mass ratio of 10%) was selected as the best membrane for U(VI) sorption. XPS analysis indicates that the main mechanism for UO22+ sorption onto CB10 is through inner-surface complexation. The sorption kinetics followed pseudo-second order model, indicating the chemisorption as the rate-controlling step. The U(VI) sorption on CB10 is endothermic and spontaneous, with the maximum mono-layer adsorption capacity of 115.6 mg/g at pH 5.0 and 298 K. Finally, the U(VI)-loaded CB10 can consecutively desorbed and reused for several cycles.
TL;DR: In this article, the in situ formed magnetite nanoparticles were encapsulated by maleated chitosan to synthesize a novel magnetic nano-sorbent (MCN-MA) for the effective sorption of uranium.
Abstract: The in situ formed magnetite nanoparticles was encapsulated by maleated chitosan to synthesize a novel magnetic chitosan nano-sorbent (MCN-MA) for the effective sorption of uranium. The sorption kinetics could be described by the pseudo-second-order model, whereas the sorption isotherms could be fitted to the Langmuir model (q
m = 187.9 mg/g). The MCN-MA showed higher U(VI) sorption capacities (compared to MCN) due to high affinity of carboxylate groups introduced from grafting maleic anhydride. Thermodynamic parameters indicate that U(VI) sorption is endothermic and feasible. The nano-size and magnetic property of the MCN-MA allow its efficient U(VI) sorption and facile magnetic separation from wastewaters.
TL;DR: In this paper, the authors dealt with the assessment of annual inhalation dose due to exposure of indoor radon, thoron and their progeny concentrations in the villages situated in sub-mountainous region of Jammu & Kashmir, India.
Abstract: The present work deals with the assessment of annual inhalation dose due to exposure of indoor radon, thoron and their progeny concentrations in the villages situated in sub-mountainous region of Jammu & Kashmir, India. The distribution of the data and the homogeneity of medians among different seasons and dwellings were assessed with the Shapiro–Wilk test and the Mann–Whitney test. The estimated total annual inhalation dose in these villages varied from 0.5 to 1.9 mSv year−1 which is less than the prescribed limit by ICRP (2008). Thus, the investigated area is safe from irradiation of radon, thoron and their progeny.
TL;DR: Two main technologies, radionuclide and seismo-acoustic monitoring, are deployed in the International Monitoring System used for the verification of the CTBT.
Abstract: The Comprehensive Nuclear-Test-Ban Treaty (CTBT) bans the testing of nuclear explosive devices underground, in the atmosphere and underwater. Two main technologies, radionuclide and seismo-acoustic monitoring, are deployed in the International Monitoring System used for the verification of the CTBT. Medical isotope production from fission-based processes is the dominant contributor to a worldwide background of radioxenon. This background can make the discrimination of nuclear tests from legitimate nuclear activities very challenging. Even if emissions from medical isotope producers experienced a large reduction, there remain other important sources of radioxenon that contribute to the global background such as research reactors and nuclear power plants. Until recently, the largest producer of medical isotopes was located in Canada, at the Canadian Nuclear Laboratories (CNL) facility. The characterization of CNL emissions and its research reactor can provide valuable information for effective verification of the CTBT.
TL;DR: In this paper, a reactive dye indigo carmine (IC) in aqueous solutions was irradiated at doses of 0.1-5kGy, and the change of absorption spectra, colorimetric study, chemical oxygen demand (COD), total organic carbon (TOC) and pH variation were carried out and studied.
Abstract: A reactive dye indigo carmine (IC) in aqueous solutions was irradiated at doses of 0.1–5 kGy. Change of absorption spectra, colorimetric study, chemical oxygen demand (COD), total organic carbon (TOC) and pH variation were carried out and studied. It was found that the absorption band located at λ = 611 nm decreased more rapidly than the UV visible bands when irradiation dose increases. The degree of decolorization and the value of color difference (∆E*) increases quadratically with increasing the value of radiation dose. The COD reduction for the dye solutions was approximately 96% at 5 kGy. Finally, based on different spectrophotometric measurements carried out in this work showed that the kinetic degradation of indigo carmine is pseudo-first order. We have also demonstrated that colorimetric study applied to a given solution could be used as a quantitative method for kinetic behavior study.
TL;DR: New scientific investigations have been carried out therefore which have not been possible before either because of lack of sensitivity or required large sample size.
Abstract: Recent developments in radiometric and mass spectrometry technologies have been associated in the radiometric sector mainly with underground operations of large volume Ge detectors, while the mass-spectrometry sector, represented mainly by accelerator mass spectrometry and inductively coupled plasma mass spectrometry has become the most sensitive technique for ultra-low-level analyses of long-lived radionuclides. These new developments have had great impact on investigations of rare nuclear processes and applications of radionuclides in environmental, life and space sciences. New scientific investigations have been carried out therefore which have not been possible before either because of lack of sensitivity or required large sample size.
TL;DR: The comparative analysis of MGF-198AuNPs with other radioactive gold nanoparticles, functionalized either with epigallocatechin gallate or the Gum Arabic, has revealed significantly superior tumoricidal characteristics of the MGF, thus corroborating the importance of the tumor-avid glucose motif of M GF.
Abstract: We report herein an innovative approach to prostate tumor therapy using tumor specific radioactive gold nanoparticles (198Au) functionalized with Mangiferin (MGF). Production and full characterization of MGF-198AuNPs are described. In vivo therapeutic efficacy of MGF-198AuNPs, through intratumoral delivery, in SCID mice bearing prostate tumor xenografts are described. Singular doses of the nano-radiopharmaceutical (MGF-198AuNPs) resulted in over 85% reduction of tumor volume as compared to untreated control groups. The excellent anti-tumor efficacy of MGF-198AuNPs are attributed to the retention of over 90% of the injected dose within tumors for long periods of time. The retention of MGF-198AuNPs is also rationalized in terms of the higher tumor metabolism of glucose which is present in the xanthanoid functionality of MGF. Limited/no lymphatic drainage of MGF-198AuNPs to various non-target organs is an attractive feature presenting realistic scope for the clinical translation of MGF-198AuNPs in for treating prostate cancers in human patients. The comparative analysis of MGF-198AuNPs with other radioactive gold nanoparticles, functionalized either with epigallocatechin gallate or the Gum Arabic, has revealed significantly superior tumoricidal characteristics of MGF-198AuNPs, thus corroborating the importance of the tumor-avid glucose motif of MGF. Oncological implications of MGF-198AuNPs as a new therapeutic agent for treating prostate and various solid tumors are presented.
TL;DR: In this article, soil and rock samples as well as all-purpose water samples were collected and measured with regard to radioisotope content and contamination by other pollutants such as, e.g., heavy metals.
Abstract: From earlier surveys conducted by soviet researchers, the Kabul area was identified as a region of high natural radioactivity. In addition, depleted uranium ammunition was used by the Soviet armed forces. Fragmentary maps (often only given in relative units) indicate regions of anomalously elevated gamma radiation dose rates. In recent years, residential houses have been built in some of these places. However, no detailed information of uranium and thorium distributions in the upper soil and rock exists. In order to assess possible radiological risk, soil and rock samples as well as all-purpose water samples were collected and measured with regard to radioisotope content and contamination by other pollutants such as, e.g., heavy metals. Activity concentrations in soil and rocks ranged between 160 to 28,600 Bq/kg, 73 to 383,000 Bq/kg, and 270 to 24,600 Bq/kg for uranium, thorium, and potassium, respectively. The elevated thorium abundances was traced back to incorporation into cheralite minerals. No anomalies of the radioactive equilibria were found in the decay chains. Hence, contributions of depleted uranium or other anthropogenic sources can be excluded. However, the high uranium content causes enhanced radon levels in houses and dwellings up to mean activity concentrations of 2000 Bq/m3 strongly exceeding the reference level of 300 Bq/m3 recommended by the ICRP. Heavy metal concentrations of some of the investigated waters also exceed the regulatory limits and are not safe for drinking. Dose assessments are given.
TL;DR: In this article, radionuclide concentrations of 226Ra, 232Th and 40K contained in two phosphate ores and six granular fertilizer samples were determined using gamma-ray spectrometry.
Abstract: In this paper, radionuclide concentrations of 226Ra, 232Th and 40K contained in two phosphate ores and six granular fertilizer samples were determined using gamma-ray spectrometry. The mean activity concentrations of 226Ra, 232Th and 40K were found to be 255 ± 12, 193 ± 7 and 23 ± 6 Bq kg−1, respectively, in phosphate ores and 86 ± 4, 12 ± 2 and 1348 ± 95 Bq kg−1, respectively, in phosphate fertilizers. The total absorbed dose rates in air (D) calculated from the concentrations of the three radionuclides ranged from 14 to 297 nGy year−1, and the external annual effective dose rates (AEDR) were determined to be between 0.01 and 0.36 mSv year−1. Based on the annual effective dose calculations, the estimated excess lifetime cancer risks due to phosphate ores and phosphate fertilizers are 1.02 × 10−3 and 0.42 × 10−3, respectively. The mean values of radium equivalent activity (Raeq), external hazard index (Hex), and internal hazard index (Hin) were also calculated, and their mean values are 532 Bq kg−1, 1.9 and 2.25 respectively, in phosphate ores and 205 Bq kg−1, 0.55 and 0.78, respectively, in fertilizers. Results were discussed and compared with those reported in similar studies and with internationally recommended values.
TL;DR: Wang et al. as discussed by the authors studied the sorption of activated bentonite and found that surface complexation was the main sorption mechanism, physisorption and ion exchange as secondary factors also participated in sorption processes.
Abstract: Activated bentonite was obtained from acid activation and purification of raw bentonite, sorption of Th(IV) onto activated bentonite was studied by batch experiments. Characterization of activated bentonite and sorption behavior of Th(IV) demonstrated that Th(IV) could quickly absorbed on activated bentonite, and kinetic process fitted well with the pseudo-second-order model. Sorption percentage of Th(IV) on activated bentonite strongly depended on pH, background anion, ionic strength and temperature, which indicated surface complexation was the main sorption mechanism, physisorption and ion-exchange as secondary factors also participated in sorption processes. The results showed activated bentonite was an efficient material for Th(IV) sorption.