Journal of Radioanalytical and Nuclear Chemistry最新文献

Research on the selective separation of graphene oxide (GO) for actinides under irradiation is of significant importance for safeguarding the sustainable development of nuclear energy. Herein, adsorption performance of GO for actinides and lanthanides under gamma irradiation was investigated in detail, the results suggested that irradiation-induced reduction of GO could enhanced the adsorption selectivity of GO for actinides. When ethanol was introduced for promoting the irradiation reduction of GO, adsorption selectivity was enhanced furtherly. This work provided a novel strategy for the selective separation of actinides and lanthanides using GO as adsorbent.

Electrorefiner salt waste from pyroprocessing presents challenges due to its chloride-rich composition and radiological risks. This review evaluates vitrification as a durable immobilization pathway, with emphasis on iron phosphate glasses. Two dehalogenation precursors: ammonium dihydrogen phosphate (ADP) and phosphoric acid (H₃PO₄) are compared regarding reaction mechanisms, byproduct generation, salt loading, and process safety. ADP offers effective dechlorination but introduces complex gaseous byproducts, whereas H₃PO₄ achieves higher waste loading with simpler emissions. Overall, phosphate-based vitrification demonstrates strong potential for scalable immobilization, supporting sustainable management of nuclear waste within advanced reactor cycles.

This study investigated the effect of gamma irradiation on photocatalytic performance of carbamazepine and mefenamic acid under visible light. The optical band gap of the pure and irradiated Fe₃O₄ samples was found to range between 2.57 eV and 2.42 eV. The change in optical and structural parameters can be due to the defects that induced by gamma irradiation. Photoluminescence (PL) analysis showed that γ-irradiation altered recombination pathways, which directly improves the photocatalytic performance. The sample irradiated with 6.0 kGy showed degradation efficiency of 83.3% and 92.3% for carbamazepine and mefenamic acid, respectively. The results highlight the significance of optimizing gamma radiation doses for efficient degradation of pharmaceutical drugs, demonstrating a promising approach for environmental remediation. The conclusion is that the photocatalysts exposed to gamma radiation are favourable materials for degradation of effluents.

This study aims to analyze the recovery yield of radioisotopes using the hot acid extraction method as an alternative to conventional dissolution and calcination techniques. Various filters with different characteristics were evaluated for their potential use in the characterizing radioactive waste removed via ablation probes. The target elements in this research were ⁶⁰Co, ¹³⁷Cs, ²³⁸U, and ²³²Th, as these isotopes are commonly found in nuclear facilities. The results indicated that the polyethersulfone membrane filter is effective for the analysis in question.

In this study, magnetic Hami-melon peels biochar (MHPBC) was successfully prepared from Hami-melon peels. Characterisation results showed that Fe₃O₄ particles were successfully loaded on the surface of the material, conferring good magnetic properties. The analysis of the adsorption mechanism showed that the removal of U(VI) mainly relied on electrostatic interaction with the complexation of oxygen-containing functional groups on the surface, and no redox reaction was involved. After five adsorption–desorption cycles, the removal rate of U(VI) by the material remained above 90%, showing good stability and reusability. Kinetic and isothermal adsorption fitting analyses showed that the adsorption process was consistent with the monomolecular layer chemisorption mechanism. It was shown that MHPBC demonstrated efficient recycling ability and reusability, and could be used as a very promising low-cost adsorbent.

This study deals with the measurements of radon and physicochemical properties of ground water from 34 natural spring (12 springs, 15 public fountains, and seven wells) in the region of Metohija. Radon concentration in water was measured by the alpha spectrometric method using the RAD7H2O device. The mean value of radon concentration in drinking water was 11.7 Bq l⁻¹. Mean value of estimated total annual effective dose (ingestion + inhalation) of radon was 30.8 μSv y⁻¹. Physical and chemical properties from water’s natural sources expressed through the mean values of pH, electrical conductivity (EC), total dissolved solids (TDS), and temperature were: 7.6, 458 μS cm⁻¹, 231 ppm, and 19.6 °C, respectively. Statistically processed data showed a strong correlation between EC and TDS - r² = 0.94. When observing the correlation between radon in water and other investigated parameters, it can be said that only between EC and radon in water is there some correlation - r² = 0.27. The Kruskal Wallis test (α < 0.01) indicated a significant difference between radon concentration in the public fountains and wells. Additionally, the mean value of ambient dose equivalent rate of gamma radiation measured at each sampling site using RADEX RD1503 + device was 110 nSv h⁻¹. The spatial distribution maps of analyzed parameters, radon in water samples, and annual effective doses for adults and children in the Metohija region were created.

The aim of this study is to investigate the influence of cerium concentration on thermoluminescence properties of LuAG:Ce³⁺ nanopowders which is necessary for any material exhibiting a suitability for dosimetry of ionizing radiation. Varying the dopant concentration within the LuAG host induces changes in trapping centres, consequently altering the thermoluminescence characteristics. Dose–response linearity study was carried out under β-irradiation has shown an enlargement of linearity range. The repeatability study demonstrated that all samples exhibit low variation on measurements. The study of fading behaviour displayed a clear rapid loss of thermoluminescence signal, which is more convenient for short-term thermoluminescence dosimetric measurements.

Estimating Titanium (Ti) and Nickel (Ni) in D9 and T91 alloys using Neutron Activation Analysis (NAA) via the (n,γ) reaction presents significant challenges due to the short half-lives of their activation products and the intense Compton background arising from the high-yield gamma emissions of ⁵⁶Mn. This study explores k₀-NAA extension to (n,p) reactions for the estimation of Ti and Ni in advanced alloy. The gamma energy of 159.4 keV from ⁴⁷Ti(n,p)⁴⁷Sc and 810.8 keV from ⁵⁸Ni(n,p)⁵⁸Co was employed for their quantification. The important k_f-factors were determined using the established fast spectrum of the Pneumatic Fast Transfer System (PFTS), KAMINI reactor. Additional parameters, such as the fast-to-epithermal neutron flux ratio, were evaluated using the reference gamma energy of ⁵⁸Ni(n,p)⁵⁸Co, along with the h-factor, which accounts for deviations specific to a reaction and irradiation facility. Standardized h-factors were measured, based on standardized k_f-factors and a fast flux ratio measured using Ni-58, for Ti-46, Ti-47, Ti-48 and Fe-54. These h-factors allow direct comparison with previously reported literature data for 4 different reactors and many channels with other newly measured values for different reactors and channels.

Mining-induced radionuclide contamination has become an issue of increasing concern, as it disrupts natural background concentrations and poses potential risks to ecosystems and human health. This study integrates soil data from nine types of mining activities across fifteen countries to systematically assess contamination levels and associated radiological hazards. Results indicate that rare earth elements, phosphate, tin, and uranium mining sites exhibit significantly elevated concentrations of ²³⁸U, ²³²Th, ²²⁶Ra, and ⁴⁰K, with radiation risks well above the global baseline.To further evaluate anthropogenic influences, activity ratios of ²³⁸U/²²⁶Ra and ²³²Th/²²⁶Ra were analyzed.

This study investigates the interaction mechanisms between uraninite (nominally UO₂) and sulfuric acid leaching solutions. After 7 days (d), uranium (U) concentrations reached 16,453.1 mg L⁻¹ (61.50% extraction rate) in sulfuric acid. U leaching followed the John Mehl Avrami (JMA) model (0‒1 h) and then the shrinking core model (SCM, 1 h‒4 d), with U existing mainly as UO₂SO₄. No significant mineral phase changes occurred, but ore surface roughened with corrosion pits, porosity rose from 33.44 to 54.77% (4 d later), particle size decreased, and reaction interface moved inward—all verifying SCM adherence.