Journal of Radioanalytical and Nuclear Chemistry最新文献

Radiosensitization approaches have shown promise in enhancing the therapeutic efficacy of radiation in nuclear medicine. This review article focuses on using nanoparticles (NPs) as radiosensitizers in nuclear medicine applications. This review covers various NP-based radiosensitization mechanisms, such as increasing radiation-induced DNA damages, alternation and modulation of tumor microenvironment, and improving radionuclide delivery efficiency. We also discussed about the challenges and opportunities of NP radiosensitization in clinical practice. Our review showed that NP-based radiosensitization strategies can result in important advancements in nuclear medicine and therefore improve cancer treatments. Despite these advancements in NP radiosensitization strategies, there are several challenges that limit their application in clinical practice. Therefore, continued research is needed to address key challenges in oncology. The future of NP radiosensitization strategies in nuclear medicine looks promising, with potential therapeutic options. This article tried to provide insights into the current status, challenges, and future perspective of NP-based radiosensitization strategies in nuclear medicine treatments.

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Surrogate nuclear explosive debris (SNED) is critical to post-detonation nuclear forensic science. We report a systematic study optimizing the dissolution characteristics of sol–gel based SNED. Total carbon analyses of sol–gels indicate elimination of unreacted carbon from residual ethyl groups when samples are annealed above 500 °C. Sol–gel SNED annealed between 600 and 800 °C dissolves similarly to Trinitite when using both HCl/HF and HNO₃/HF based dissolution approaches. Taken together, these data demonstrate the ability to produce highly tunable, realistic SNED samples that can be employed to support future laboratory analysis applications.

Based on the water samples collected from Minjiang river, the spatiotemporal pattern of stable isotopes in different waters and the influencing mechanisms were investigated in the article. Our findings suggested that the stable isotopes of oxygen and hydrogen in waters exhibited obvious spatiotemporal variations influenced by temperature and precipitation amount since precipitation is an important recharge source for Minjiang river water and that the ‘latitude effect’ was observed in the river water whereas the ‘elevation effect’ was obscured. The results of this study will be helpful in understanding the hydrological cycle and promoting the scientific management of water resources in basins at east transition of Qinghai–Tibet Plateau.

The hardware of the pneumatic transfer system used to perform instrumental neutron activation analysis at the IBR-2 reactor (JINR, Dubna) has undergone a modernization. For this purpose, the new control panel, representing a desktop program for Windows, was developed. In terms of the gamma spectrometry automation outdated sample changers were replaced by four KUKA KR10 R1100 manipulators with all necessary controllers. Additionally, to use fixed geometry of irradiated samples during induced activity measurement special containers and a protective box for sample repacking were developed.

Radioisotopes of actinium are valuable because of their potential use in the medical industry. Actinium-225 shows promise for treating disease—like cancer—via targeted alpha therapy (TAT), and the longer-lived actinium-227 is the parent of two radionuclides with potential application in TAT radiopharmaceuticals, thorium-227 and radium-223. Continuing progress in the development of these medical applications requires robust and diverse methods for extracting and purifying actinium from a wide range of matrices. To define the strengths and limitations of separation methods commonly employed in actinium processing, we characterized the performance of ion exchange and extraction chromatographic steps for removing contaminants found in stainless steel (chromium, iron, nickel, and silicon) and aluminum from actinium-227. While AG-MP1 anion exchange resin with HCl_(aq) successfully removed iron, cation exchanger AG 50W-X8 removed most other contaminants. The most persistent contaminant was aluminum, which was removed using a DGA Normal extraction resin. These results are presented within the context of applying that methodology toward actinium purification strategies.

In this study, the solvent extraction behavior of tin (Sn), specifically ¹²⁶Sn, from high-level radioactive waste was evaluated using six different extractants in a HNO₃ system. Among the tested extractants, N,N-Didodecyl-2-hydroxyacetoamide (HAA) exhibited higher efficiency, still not sufficient for industrial implementation. In systems where HCl was added to HNO₃, both tributyl phosphate (TBP) and N,N,N,N’-tetra-2-ethylhexyl diglycolamide (TEHDGA) achieved D_Sn values greater than 1 at > 1 M HCl. However, due to practical challenges in industrial applications, HAA extraction in HNO₃ systems, particularly at low Sn concentrations (0.0008 M), may provide a more effective solution for Sn recovery.

The aim of this study is to remove ¹²⁵Sb and ⁶⁰Co from low-level liquid radioactive waste using Analytical Grade Activated Carbon (AGAC) as an adsorbent from a research reactor coolant waste. AGAC is a highly porous adsorbent used to remove metals/pollutants from water. The AGAC was characterized using SEM, EDX, and FT-IR. Experimental studies included Point of Zero Charge, fixed bed, and batch studies. In the fixed bed study, breakthrough curves were determined for different bed heights and flow rates to optimize the sorption capacity of the adsorbent. Cycle III of AGAC showed the highest breakthrough capacity at 964.28 Bq/g for ¹²⁵Sb and 2530 Bq/g for ⁶⁰Co with specific conditions. The Thomas model was found to be the best fit for the fixed bed study results. In the batch study, various parameters such as contact duration, adsorbent dose, pH, temperature, and initial activity were optimized using isotherm and kinetic models. The Freundlich Isotherm Model and Pseudo 2nd Order kinetic model were the best fits for ¹²⁵Sb and ⁶⁰Co adsorption with AGAC, respectively, based on the R² values obtained.

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In this paper, we report a new combined method of chemical coprecipitation-ionic liquid electrodeposition for the determination of trace uranium in seawater. The procedure involves coprecipitation of trace uranium on Fe(OH)₃ upon addition of ferric chloride and electrodeposition of uranium in EMIMBF₄ to determine by inductively coupled plasma optical emission spectrometry(ICP-OES). The solution, which ferric chloride was added to 1 L of seawater sample and adjusted the pH to 4, was placed at 80 °C for 30 min to coprecipitate uranium with iron hydroxide. The precipitate was then dissolved in nitric acid and electrodeposited in EMIMBF₄ to determine uranium by ICP-OES. The coefficient of diffusion (D) of electrodeposition of U (VI) on platinum electrode in EMIMBF₄ was evaluated, which was 3.31 × 10⁻⁹ cm²/s. The electrochemistry experiments indicated that the reduction of U (VI) at platinum electrode in EMIMBF₄ was a quasi-reversible single step two-electron transfer. The percent of chemical coprecipitation recovery of U (VI) was 98.9% and recovery in electrodeposition was 99.5%. Using combine of two methods can determined trace uranium in seawater.

In this study, the in-situ synthesis of birnessite successfully removed Co²⁺ from simulated radioactive wastewater. The optimal reaction conditions were determined by single-factor experiments: a reaction time of 60 min, a pH of 11, a reaction temperature of 50°C and a Mn²⁺/Co²⁺ molar ratio of 7:1. The removal rate of Co²⁺ reached 99.97%. XRD confirmed birnessite as the precipitate. FTIR, precipitate dissolution and XPS analyses indicated that the removal mechanisms of Co²⁺ included hydroxide precipitation (0.36%), adsorption (4.70%) and ion exchange (94.94%). In conclusion, the in-situ synthesis of birnessite for Co²⁺ removal is promising for the treatment of radioactive wastewater.

Uranium-containing wastewater from the nuclear fuel cycle poses severe hazards to human health and the environment. In this study, a carboxylated multi-walled carbon nanotube/copper oxide/nano silver modified graphite felt electrode (MCA) material was designed, exhibiting electrosorption performance with electrical double layer and pseudocapacitance characteristics. Electrosorption processes proved the ability to adsorb U(VI). MCA-2 had the highest removal rate (93.31%) due to superior conductivity, stability, and capacitance characteristics. A high adsorption capacity of 361 mg/g was reached in a 200 mg/L U(VI) solution. MCA achieves good cycling stability and high selectivity, making it a potential electrode material for radioactive wastewater treatment.