{"title":"Electroextraction of fission element thulium from copper electrode in LiCl–KCl molten salt electrorefining process and its kinetic analysis","authors":"Huiyu Liu, Yingcai Wang, Yunxiu Zhang, Yuanping Jiang, Zhibin Zhang, Yunhai Liu","doi":"10.1515/ract-2025-0017","DOIUrl":"https://doi.org/10.1515/ract-2025-0017","url":null,"abstract":"Abstract To enhance the utilization of spent fuel and achieve nuclear fuel recycling, the extraction of rare earth element thulium (Tm) was studied using electrorefining methods. The electrodeposition processes of Tm(III) and Cu(II) ions on a W electrode, as well as Tm(III) ions on a Cu electrode, were examined using open-circuit chronopotentiometry (OCP), square wave voltammetry (SWV) and cyclic voltammetry (CV) in a LiCl–KCl molten salt environment. The process of alloy formation and dissolution of Tm on the cathode was studied using open-circuit chronopotentiometry. The changes in entropy and enthalpy of the formed Cu 5 Tm alloy were computed as 205.05 kJ·mol⁻¹ and -30.92 J·mol⁻¹·K⁻¹ correspondingly. Additionally, the cathode deposits were characterized and investigated using X-ray diffraction (XRD), scanning electron microscopy (SEM), and energy-dispersive spectroscopy (EDS). It was found that the extraction rate of Tm(III) by constant potential electrolysis averages 94.35 % based on the ICP-OES measurements of the TmCl 3 concentration in the molten salt prior to and following electrolysis. Therefore, electrolytic refining through the dry reprocessing of spent fuel can effectively remove key fission products from the spent fuel.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":"114 3","pages":"191-200"},"PeriodicalIF":0.0,"publicationDate":"2025-12-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147920841","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Separation of Th(IV) from U(VI) and lanthanides with functionalized ionic liquid","authors":"Xiaomin Li, Peng Liu, Meiying Liu, Xupeng Zhi, Xinlong Chen, Keliang Shi, Yinglin Shen","doi":"10.1515/ract-2024-0318","DOIUrl":"https://doi.org/10.1515/ract-2024-0318","url":null,"abstract":"Abstract The rapid development of nuclear energy has greatly increased the possibility of nuclear leakage, and the rapid detection of radioactive leakage in emergency situations requires rapid analytical methods. Pu(IV) is almost non-existent in nature, so radioactive contamination in the environment is usually analyzed by detecting the radioactivity level of plutonium. Here, the neutral extractant, PyDAM, and the novel functional ionic liquid, PyDAMI, were synthesized by introducing two amide groups into the pyridine for separating Pu(IV). Due to the high radioactivity of Pu, Pu(IV) was replaced by Th(IV) in extraction experiments. It was found that PyDAM in kerosene or [C 4 mim][NTf 2 ] could not extract Th(IV), U(VI), Eu(III), Ce(IV) and Nd(III) from nitric acid media, while PyDAMI could extract both U(VI) and Th(IV), but hardly extract other metal ions, which indicates that electrostatic interactions play a key role. The distribution coefficients of U(VI) and Th(IV) in PyDAMI/[C 4 mim][NTf 2 ] increase with an increase in the concentration of nitric acid, while they first increase and then decrease in PyDAMI/kerosene, indicating that PyDAMI has different extraction mechanisms in kerosene and [C 4 mim][NTf 2 ] and their respective extraction mechanisms were studied through extraction experiments and some characterization techniques. In addition, the separation performance and separation factor of PyDAMI for thorium and uranium are improved in kerosene. Finally, the effect of temperature on PyDAMI’s ability to extract uranium and thorium was investigated. It was found that the ability of PyDAMI to extract uranium and thorium decreased with increasing temperature, indicating that the extraction of uranium and thorium by PyDAMI was an exothermic reaction.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":"113 12","pages":"953-961"},"PeriodicalIF":0.0,"publicationDate":"2025-10-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147897514","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Daoqing Ma, Jicheng Xu, Zhixuan Yi, Bin Ma, Ming Fang, Xiaoli Tan
{"title":"Separation and purification of Zr from a low-temperature LiCl–KCl–CsCl eutectic by the formation of dendritic crystal","authors":"Daoqing Ma, Jicheng Xu, Zhixuan Yi, Bin Ma, Ming Fang, Xiaoli Tan","doi":"10.1515/ract-2024-0355","DOIUrl":"https://doi.org/10.1515/ract-2024-0355","url":null,"abstract":"Abstract Zirconium is widely used in the nuclear industry as a cladding material for nuclear reactors and loading nuclear fuel. From the perspective of safety and the economy, the recovery of zirconium from cladding waste at low temperatures is of strategic significance for nuclear energy. This work studied the electrochemical behavior of Zr(IV) and the separation of Zr metal in a low-temperature LiCl–KCl–CsCl molten salt system at 573 K (300 °C). Zr(IV) ion was reduced to metallic Zr through a two-step four-electron reaction process Zr(IV) → Zr(III) → Zr on the W electrode. The diffusion coefficients of Zr(IV) on the W electrode calculated by cyclic voltammetry and chronoamperometry were 5.805 × 10 −5 cm 2 s −1 and 2.861 × 10 −5 cm 2 s −1 , respectively. Furthermore, the reaction activation energy of the Zr(III)/Zr(0) pair was measured to be 34.52 kJ mol −1 by the Tafel method. Then, the electrochemical recovery of Zr was accomplished on the W electrode by potentiostatic electrolysis at −2.0 V or galvanostatic electrolysis at 0.01 A, and two zirconium-containing products with the dendritic and flakes morphologies were obtained accordingly. This study provides a new low-temperature molten salt system for the reprocessing of zirconium cladding and shows the application potential of low-temperature molten salts LiCl–KCl–CsCl for spent fuel reprocessing.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":"113 9","pages":"665-678"},"PeriodicalIF":0.0,"publicationDate":"2025-08-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147902418","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Cong Huang, Qiang Zhao, Wei Zhao, Xuebin Su, Rong Hua
{"title":"Adsorption behavior of Se(IV) in calcium-based (natural) bentonite and sodium-based (engineered modified) bentonite","authors":"Cong Huang, Qiang Zhao, Wei Zhao, Xuebin Su, Rong Hua","doi":"10.1515/ract-2025-0044","DOIUrl":"https://doi.org/10.1515/ract-2025-0044","url":null,"abstract":"Abstract Bentonite plays a significant role as a buffer backfill material in geological disposal due to its unique properties that are crucial for the safe containment of high-level radioactive waste. In this work, the impact of various factors on the adsorption of selenite (Se(IV)) by both calcium-based and sodium-based bentonite was examined using batch experiments. As a result, both types of bentonite achieve adsorption equilibrium with Se(IV) within approximately 120 h. The adsorption capacity decreases with increasing initial concentration of Se(IV), while it is positively influenced by longer contact times and higher temperatures. The partition coefficient ( K d ) exhibits a complex relationship with pH, initially decreasing, then increasing, and finally decreasing again. Additionally, ionic strength significantly affects the adsorption process. These observations suggest that Se(IV) adsorption on bentonite is pH-dependent and involves a non-spontaneous heat-absorbing process, likely a chemical reaction dominated by the ion-exchange form of chemisorption in a monomolecular layer. This process aligns well with the isothermal adsorption model and the simulated secondary kinetics of the Langmuir model. Furthermore, the adsorption of Se(IV) is notably hindered by the increased electrostatic repulsion between the negatively charged bentonite surface and the negatively charged species HSeO 3 2− and SeO 3 2− . The Fourier transform infrared spectra showed that the positions, intensities and shapes of the spectral characteristic peaks of the functional groups before and after adsorption did not change significantly.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":"113 10","pages":"791-803"},"PeriodicalIF":0.0,"publicationDate":"2025-07-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147909043","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Mechanistic insights into La(III) extraction using HDEHP: toward effective rare earth recovery from radioactive waste","authors":"Lan Wang, Lingyun Luo, Kai Huang, Xiaonan Liu","doi":"10.1515/ract-2025-0040","DOIUrl":"https://doi.org/10.1515/ract-2025-0040","url":null,"abstract":"Abstract The rare earth element (REE) recovered from radioactive wastewater is of great significance for the resource sustainability, and radioactive waste minimization and management. In this study, the light REE La selected as an example, the extraction behavior of La(III) has been studied systematically using bis(2-ethylhexyl) phosphate (HDEHP) as extractant, optimizing operational parameters and elucidating the underlying mechanism for REE recovery. Optimal conditions yielded an extraction ratio exceeding 98 %, achieved at the contact time of 30 min, phase ratio of 1:1, and HDEHP concentration of 0.1 mol L −1 . Increasing HCl concentration was observed to suppress extraction, whereas elevated temperatures benefited the performance supported by thermodynamic analysis this was a spontaneous (Δ G = −8.80 kJ mol −1 ) and endothermic process. Mechanistic investigations via FT-IR spectroscopy and slope method analysis confirmed La(III) coordination with the P=O double bond of HDEHP, forming stable complex with stoichiometric ratio of 3:1 (HDEHP:La 3+ ), and the La(III) was extracted through cation exchange. These findings not only deepen the theoretical understanding of La(III) extraction, but also provide guidelines for the REEs recovery processes in the radioactive wastewater treatment.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":"113 10","pages":"771-777"},"PeriodicalIF":0.0,"publicationDate":"2025-07-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147887486","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Particle-reinforced ion exchange resin for selective separation and recovery of cesium from highly acidic water","authors":"Huilian Mo, Xiangjian Meng, Wen Zhou, Jing Wang, Suwen Chen","doi":"10.1515/ract-2025-0033","DOIUrl":"https://doi.org/10.1515/ract-2025-0033","url":null,"abstract":"Abstract The efficient separation of 137 Cs from high-level liquid waste (HLLW) is of great significance for the development of nuclear energy. However, for columns commonly used in the industry, ion exchangers need to be loaded on the resin matrix, which is typically not resistant to strong acids. Consequently, a particle-reinforced ion exchange resin (PR AWP-CA) was designed and prepared. In PR AWP-CA, the active component (ammonium phosphotungstate) and particle reinforcer were encapsulated by carrier resin (calcium alginate). The formulation of was optimized by preparing the resin with different content. The results show that PR AWP-CA has great mechanical strength, high acid resistance and excellent selectivity. In 3 mol/L nitric acid, the adsorption equilibrium was reached after only 2 h. Cs could be selectively separated, and the recovery of cesium was greater than 98 % when the extraction of interference elements was close to 0. The cesium separation ability of the resin was stable in 3.0 mol/L nitric acid at 25–55 °C. PR AWP-CA exhibited good compressive resistance in column experiment. After five cycles, the resin could still present high adsorption capacity. A particle reinforced ion exchange resin, suitable for the separation of cesium in high level radioactive waste liquid, was successfully obtained.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":"113 9","pages":"679-691"},"PeriodicalIF":0.0,"publicationDate":"2025-06-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147887202","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Combining synergistic interaction and ion imprinting to improve adsorption capacity for selective uranium extraction from seawater","authors":"Huilian Mo, Tao Chen, Chao Jiang, Ziyang Wang, Xiangjian Meng, Fei Wu, Wei Liu, Suwen Chen","doi":"10.1515/ract-2024-0321","DOIUrl":"https://doi.org/10.1515/ract-2024-0321","url":null,"abstract":"Abstract To ensuring the demand for uranium by utilizing unconventional uranium resources, the development of materials for selective capturing uranyl ions is increasingly important. Hence, the ion-imprinted polymer (IIP) based on specific binding sites was designed and prepared for selective enrichment of uranium from seawater. The existence of specific adsorption sites and the corresponding adsorption mechanism were confirmed by a series of experimental analyses and supported by density functional theory (DFT) calculations. Under the influence of seawater environment, the maximal uranium uptake of IIP reached 58.31 mg g −1 . Significantly, the mass ratio of U and V (Sr or Ni) adsorbed by IIP was greater than 15, and the adsorption capacity did not change obviously after five cycles of use. The strategy combining ion imprinting and synergistic interaction is expected to improve uranium extraction performance.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":"113 2","pages":"113-124"},"PeriodicalIF":0.0,"publicationDate":"2024-11-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147881534","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Uranium, plutonium and neptunium co-recovery with high nitric acid concentration in extraction section by simplified solvent extraction process","authors":"M. Nakahara, Y. Sano","doi":"10.1524/RACT.2009.1671","DOIUrl":"https://doi.org/10.1524/RACT.2009.1671","url":null,"abstract":"Abstract As a part of NEXT, the behavior of Np in a simplified solvent extraction process using TBP as an extractant for U, Pu and Np co-recovery was investigated. Two approaches to Np co-recovery with U and Pu in the irradiated fast reactor core fuel using a dissolver solution in a counter current were examined. One used a feed solution with a high HNO3 concentration, and the other used a scrubbing solution with a high HNO3 concentration. The leakages of Np to the raffinate were 1.1 and 4.7% using high HNO3 concentration feed and scrubbing solutions, respectively. Simulation results based on these experiments showed that high HNO3 concentration in the feed solution is advantageous for the Np extraction because Np oxidation progresses in the feed solution before being supplied into the centrifugal contactor, and there is less effect of HNO2 at the extraction section.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":"121 1","pages":"727 - 731"},"PeriodicalIF":0.0,"publicationDate":"2009-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76007528","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
A. Rout, K. Venkatesan, T. Srinivasan, P. Vasudeva Rao
{"title":"Extraction of americium(III) from nitric acid medium by CMPO-TBP extractants in ionic liquid diluent","authors":"A. Rout, K. Venkatesan, T. Srinivasan, P. Vasudeva Rao","doi":"10.1524/RACT.2009.1975","DOIUrl":"https://doi.org/10.1524/RACT.2009.1975","url":null,"abstract":"Abstract Extraction of americium(III) from nitric acid medium by a solution of tri-n-butylphosphate (TBP) and n-octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) in room temperature ionic liquid, 1-butyl-3-methylimidazolium bis(trifluoromethanesulfonyl)imide (bmimNTf2), was studied and the results were compared with that obtained with CMPO-TBP in n-doddecane (n-DD). The distribution ratio of 241Am(III) in TBP-CMPO/bmimNTf2 was measured as a function of various parameters such as concentrations of nitric acid, CMPO, bmimNO3, NaNO3 and TBP and temperature. Remarkably large distribution ratios were observed for the extraction of americium(III) when bmimNTf2 acted as diluent and the extraction was insignificant in the absence of CMPO. The stoichiometry of metal–solvate in organic phase was determined by the slope analysis of extraction data and it indicated the formation of 1:3 (Am:CMPO) complex in organic phase. Viscosity of TBP-CMPO/bmimNTf2 at various temperatures and enthalpy change accompanied by the extraction of americium(III) were determined and reported in this paper.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":"18 1","pages":"719 - 725"},"PeriodicalIF":0.0,"publicationDate":"2009-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78844327","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
P. Bienvenu, L. Ferreux, G. Andreoletti, N. Arnal, M. Lépy, M. Bé
{"title":"Determination of 126Sn half-life from ICP-MS and gamma spectrometry measurements","authors":"P. Bienvenu, L. Ferreux, G. Andreoletti, N. Arnal, M. Lépy, M. Bé","doi":"10.1524/RACT.2009.1673","DOIUrl":"https://doi.org/10.1524/RACT.2009.1673","url":null,"abstract":"Abstract A new value of 126Sn half-life was determined by combination of inductively coupled plasma-mass spectrometry (ICP-MS) and gamma spectrometry measurements on purified sample solutions collected from nuclear fuel reprocessing. 126Sn was isolated through dissolution of fission product precipitates and liquid-liquid extraction with N-benzoyl-N-phenyl-hydroxylamine (BPHA). The abundance of 126Sn atoms together with the absence of interfering species in the analysed solutions made it possible to measure both mass concentration and nuclide activity with high precision and accuracy. This led to a 126Sn half-life value of 1.980(57)×105 a.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":"42 1","pages":"687 - 694"},"PeriodicalIF":0.0,"publicationDate":"2009-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85739166","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}