Journal of Radioanalytical and Nuclear Chemistry最新文献

In order to effectively remove Co²⁺ from radioactive wastewater, β-cyclodextrin/graphene oxide (β-CD/GO) was synthesized. The factors affecting the adsorption of Co²⁺in water were determined by static adsorption experiments, and the synthesis and adsorption mechanism of the materials were discussed by using Density Functional Theory (DFT). The results show that β-CD and GO are mainly bonded by ester group and hydrogen bond, the adsorption of Co²⁺ by β-CD/GO belongs to single molecular layer chemisorption, and the intramolecular diffusion is the main factor of affecting the adsorption rate. The adsorption capacity of Co²⁺ can reach 95.83 mg/g under appropriate conditions, but it will be affected by interference ions.

⁶⁵Zn, a fission product found in cooling water reactors, poses significant environmental risks due to its toxicity. This study explores the use of Ca–Fe²⁺ phosphate (SB1) and Ca–Fe³⁺ phosphate (SB2) as sorbents for Zn(II), prepared via the wet chemical method. The Zn(II) solution, spiked with ⁶⁵Zn radionuclides, was analyzed radiometrically. Optimal sorption conditions were determined to be pH 4.5, a contact time of 24 h, and a sorbate volume to sorbent mass ratio of 1:10 at 20 °C. The Langmuir isotherm model best fit the adsorption data, indicating monolayer adsorption capacities of 0.574 mmol g⁻¹ for SB1 and 0.621 mmol g⁻¹ for SB2. Sorption kinetics followed a quasi-n^th-order model. Furthermore, 0.1 M FeCl₃ effectively desorbed 99% of Zn(II) from both sorbents. The sorption process was found to be spontaneous and endothermic. These findings suggest that SB1 and SB2 have potential applications in recycling Zn(II) from the black mass of expired batteries.

Uranium is a highly hazardous heavy metal and radionuclide. The distribution of uranium in rock, soil, fruit, and water has been measured in the Balod area. Samples were collected using one square kilometer griding technique from Jhalmala Paragaon, Parsoda, Dewerbatt, Pakurbatt, and Jagarata Deur tarai. The distribution of uranium is quantified within the ranges of 0.7–3.6 (ppb) in soil, 0.5–4.4 ppb in rock, 0.2–52.6 ppb in groundwater, and 0.2–0.7 ppb in fruit.The presence and movement of uranium has been verified through a systematic statistical investigation, and its mobility in environmental components has been established.

Experimentally ensuring the quality of neutron beam before patient treatment is a topic of central importance for a boron neutron capture therapy (BNCT) facility. The procedure of beam quality assurance currently adopted at THOR-BNCT lacks a direct indication related to the energy distribution of neutrons. A new device based on multiple activation foils was therefore proposed to provide a quick confirmation of the unchanged neutron spectrum before patient irradiation. The device’s responses to the THOR-BNCT neutron beam are presented. A series of experimental tests were repeated to establish the baseline performance of the device, and further numerical simulations were conducted to determine its sensitivities to various perturbations in the reference spectrum. To increase the rigorousness of beam quality assurance by supplementing additional information about neutron spectrum, the device has been suggested to assist the role of Au/Cu activation foils in the current procedure as and when required.

Traditional methods for measuring the ²²⁶Ra activity are time-consuming and the equipment is large and inconvenient to carry. This article proposes a new method for quickly measuring the activity of high-concentration ²²⁶Ra using RAD7, which is simple to operate, does not require chemical separation. The ²²²Rn production rate is obtained by measuring the ²²²Rn concentration in a nonequilibrium state using RAD7, and the ²²⁶Ra activity is yielded according to the law of radioactive decay. Verification experimental results demonstrate that, compared with the FD125 measurement method, the proposed method reduces the measurement time by 92%, with result deviation within 6%. Therefore, the proposed method can provide technical support for rapid measurement during the ²²⁶Ra production process.

With the advancement of the detector systems for γ-ray radiation, simultaneous measurement of time correlated photoelectric and Compton events recorded by employing segmented HPGe detectors (Clover Detectors) with very high energy resolution and efficiency, allows measuring the polarization of the γ-ray radiation in addition to the energy of the γ-ray radiation. The polarization measurement of the γ-ray radiation provides information regarding its electric or magnetic nature, which is essential for determining the parity of the decaying nuclear state. Data is shown for the low laying states of ¹³⁶Ce with information on the R_DCO and polarization measurements. These measurements were carried out with the help of Indian National Gamma Array (INGA), New Delhi setup.

A granular manganese oxide-based sorbent was synthesized. One volume of the sorbent decontaminates 125–145 volumes of hardness water from strontium radionuclides to background values of radioactivity. The synthesis includes interaction of MnSO₄ with KMnO₄ in aqueous medium at [Mn²⁺]/[MnO₄⁻] = 1.8, followed by the precipitation, aging the precipitate at pH = 11, and calcining it at 160 °C. Characteristics of the sorbent obtained were as follows: the distribution coefficient of the tracer ⁸⁵Sr radionuclide in 0.01 mol dm⁻³ CaCl₂ solution of 1.6 × 10⁴ cm³ g⁻¹, the batch capacity by Ca²⁺ of 1.10 mol g⁻¹, and the Sr/Ca pair separation coefficient of 65.

Hydrogen generation was obtained with homogeneous n-C₆H₁₄, 88.5% n-C₆H₁₄+11.5% H₂O, 50% n-C₆H₁₄+50% H₂O and 11.5% n-C₆H₁₄+88.5% H₂O and heterogeneous Al₂O₃+n-C₆H₁₄, Al₂O₃+88.5% n-C₆H₁₄+11.5% H₂O, Al₂O₃+50% n-C₆H₁₄+50% H₂O and Al₂O₃+11.5% n-C₆H₁₄+88.5% H₂O systems. Hydrocarbons (methane, ethane, propane, butane, pentane, and hexane) and other organic molecules (methanol, acetaldehyde, and acetic acid) were also used for optimization. The activation energies were 3.50 and 3.74 kJ/mol for Al₂O₃+n-C₆H₁₄ and Al₂O₃+C₆H₁₄+H₂O systems. Maximum hydrogen produced was 54.0×1017 molecules/g.

The present study reports the terrestrial gamma radiation exposures in dwellings in Makum Coalfield, India, using a Micro-R Gamma Survey Metre. The geometric means (GMs) of indoor and outdoor gamma dose rates were found to be 150.3 ± 7.4 nGy h⁻¹ and 129.2 ± 6.6 nGy h⁻¹, respectively, which are considerably higher than the global population-weighted average of 84 nGy h⁻¹ and 59 nGy h⁻¹, respectively. The estimated GMs of annual effective dose equivalents and excess lifetime cancer risks were also found to be substantially higher than the global recommended values of 0.48 mSv y⁻¹ and 1.45 × 10^–3, respectively.

Four chromatographic supports were functionalized with bis-(2-ethylhexyl) phosphoric acid (HDEHP) and examined for radiation stability when used for f-element separations after exposure to high levels of ionizing gamma radiation. Changes in Eu(III) partitioning were evaluated and compared to an analogous solvent extraction system using HDEHP in n-dodecane. The solvent extraction system showed an increase in Eu(III) uptake with increasing γ irradiation dose to the solvent in the presence of nitric acid. The Eu(III) distribution profiles indicate that the functionalized chromatographic support materials are less affected by γ irradiation, when exposed in a radiation environment of up to 2.5 MGy in the presence of nitric acid.