Journal of Radioanalytical and Nuclear Chemistry最新文献

{"title":"Validation of a HPLC method for quality control of 68Ga-DOTATOC","authors":"B. Crosio,&nbsp;C. Subreville,&nbsp;P. Stein,&nbsp;Y. Fromage,&nbsp;B. Lortal","doi":"10.1007/s10967-026-10815-1","DOIUrl":"10.1007/s10967-026-10815-1","url":null,"abstract":"<div><p>Unexplained production issues with Ga-DOTATOC kits continue to cause economic losses and delays in patient care. This study aimed to adapt the European Pharmacopoeia method and validate a rapid UV/radiometric HPLC method to identify gallium-DOTATOC, free gallium, and unlabeled peptide, and to quantify free-gallium and DOTATOC in a single run. The method proved to be accurate, precise, and repeatable, providing a practical tool to investigate labeling failures. This work allows the optimization of quality control, the investigation of labeling failures, and the cut of associated costs.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"335 4","pages":"2483 - 2489"},"PeriodicalIF":1.6,"publicationDate":"2026-03-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10967-026-10815-1.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147734968","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Synthesis of eutectic UCl3–NaCl–KCl and UCl3–NaCl by chlorination of uranium metal with ZnCl2","authors":"Alexis S. Westwood,&nbsp;Nathan Rood,&nbsp;Aaron J. Unger,&nbsp;Chao Zhang,&nbsp;Allison Harward,&nbsp;Sayandev Chatterjee,&nbsp;Supathorn Phongikaroon,&nbsp;Michael F. Simpson","doi":"10.1007/s10967-026-10828-w","DOIUrl":"10.1007/s10967-026-10828-w","url":null,"abstract":"<div><p>Candidate fuel mixtures for molten chloride fast reactors require a high concentration (&gt; 30 mol%) of UCl₃ to form a eutectic mixture with a sufficiently low melting point. This work describes a novel way of producing the ternary UCl₃–NaCl–KCl eutectic and the binary UCl₃–NaCl eutectic by chlorinating uranium metal with ZnCl₂ starting with a low melting point molten ZnCl₂–NaCl–KCl mixture and ZnCl₂–NaCl mixture. This method produces the desired salt after complete reaction of the ZnCl₂. The three synthesis runs described here resulted in two near-eutectic mixtures of UCl₃–NaCl–KCl with UCl₃ concentrations of 31 and 35 mol % with Na/K mol ratios of 2.33 and 2.37 as well as one near-eutectic mixture of UCl₃–NaCl with 32 mol % UCl₃. It is shown that the ternary synthesis can be performed entirely in the liquid phase below 550 °C and results in a salt with a melting point between 468–482 °C. The binary synthesis can be performed below 575 °C and results in a salt with a melting point of 527 °C. The Zn byproduct of this reaction is readily removed by distillation above 450 °C and has a final concentration less than 0.1 wt% in the final salt product. When a U–Zr pellet is used instead of pure U for chlorinating, ZrCl₄ is first formed in the melt which either vaporizes out or later reacts with excess U to form UCl₃. The final ZrCl₄ content in the salt is easily reduced to less than 0.01 wt %.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"335 4","pages":"3071 - 3081"},"PeriodicalIF":1.6,"publicationDate":"2026-03-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147735082","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"One-pot synthesis of graphene oxide supported nanoscale zero-valent nickel as a novel nanotrap toward highly efficient uranyl capture","authors":"Shaoming Zhu,&nbsp;Weijiang Wang,&nbsp;Yuxin Ding,&nbsp;Changjun Zhang,&nbsp;Yuanyuan Xie","doi":"10.1007/s10967-026-10842-y","DOIUrl":"10.1007/s10967-026-10842-y","url":null,"abstract":"<div><p>Herein, we reported one-pot synthesis of graphene oxide (GO) supported nanoscale zero-valent nickel (NZVN), used as–synthesized GO@NZVN for capture of uranyl ions. Structural characterization established aggregation of NZVN was diminished by immobilization onto GO, contributing to improved reactivity of GO@NZVN which enable superior removal performance towards U(VI) in comparison with NZVN. The D–R model provided the best description of isotherm data of U(VI) adsorption onto GO@NZVN. The pseudo–second order model contributed to a better description of adsorption kinetics for U(VI) capture. Thermodynamic analysis revealed endothermic and spontaneous adsorption of U(VI) onto the GO@NZVN adsorbents. XPS analyses allude that U(VI) adsorption onto composite surfaces followed by reduction into U(IV) were the central mechanism. Results of this contribution unveiled that GO@NZVN exhibited potential applicability in remediating heavy metal pollutants.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"335 4","pages":"3037 - 3053"},"PeriodicalIF":1.6,"publicationDate":"2026-03-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147734902","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Technetium quantification in CORAL process streams: Implications on waste management strategy and selection of an appropriate analytical method","authors":"Arvind Prasad,&nbsp;K. S. Vijayan,&nbsp;P. Sivakumar","doi":"10.1007/s10967-026-10825-z","DOIUrl":"10.1007/s10967-026-10825-z","url":null,"abstract":"<div><p>COmpact Reprocessing facility for Advanced Fuels in Lead shielded cell (CORAL) is facility in India to reprocess spent fast reactor fuels. Waste streams from a reprocessing facility must be characterized using reliable analytical methods to support effective waste management and enable potential resource recovery. This study examines ⁹⁹Tc distribution in waste streams of the CORAL by Tetraphenyl arsonium chloride (TPAC)–Chloroform extraction method. ⁹⁹Tc was analysed using gross beta counting using Geiger–Müller (G–M) counter and Inductively Coupled Plasma–Optical Emission Spectrometry (ICP-OES). The result of this study indicates that ICP-OES offering superior accuracy as compared to beta counting method. Mass balance studies showed ~ 92% of ⁹⁹Tc is in raffinate, ~ 1.5% in products, 1.5% in ADU filtrate, and ≤ 5% in lean organic. These results will provide valuable inputs to waste managers for optimizing waste-management strategies for high and low activity wastes containing ⁹⁹Tc generated during fast-reactor fuel reprocessing.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"335 4","pages":"3055 - 3062"},"PeriodicalIF":1.6,"publicationDate":"2026-03-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147734991","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Ozonolysis of selenium: an alternative oxidation method for radiochemical separations of arsenic and selenium","authors":"Connor K. Holiski,&nbsp;Kelly N. Kmak,&nbsp;John D. Despotopulos,&nbsp;Nicholas D. Scielzo","doi":"10.1007/s10967-026-10847-7","DOIUrl":"10.1007/s10967-026-10847-7","url":null,"abstract":"<div><p>Many arsenic and selenium radiochemical separation methods use hydrogen peroxide (H₂O₂) to oxidize selenite (Se(IV)) to selenate (Se(VI)), but this reaction is challenging to control and replicate. This study introduces a simple ozonolysis apparatus with an in-line oxygen-ozone generator and impinger system for rapid selenium oxidation in aqueous samples as an alternative to H₂O₂. The system quickly converts Se(IV) to Se(VI), enabling successful separations of arsenic-73 and selenium-75 with high recoveries using ion-exchange chromatography (1-X8). Compared to traditional H₂O₂ treatment, ozone oxidation is a faster and more easily controlled method for selenium redox chemistry.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"335 4","pages":"3063 - 3070"},"PeriodicalIF":1.6,"publicationDate":"2026-03-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147734955","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Preparation and preliminary biological evaluation of [131I]I-yg-15 peptide","authors":"Yang Wang,&nbsp;Yuxin Wang,&nbsp;Xuecen Cao,&nbsp;Zijun Kuang,&nbsp;Lin Ma,&nbsp;Lan Zhang,&nbsp;Yuxia Liu,&nbsp;Zheng Li,&nbsp;Qingnuan Li","doi":"10.1007/s10967-026-10824-0","DOIUrl":"10.1007/s10967-026-10824-0","url":null,"abstract":"<div><p>The CLDN18.2 protein, which is highly expressed in tumors such as gastric cancer, has emerged as a critical molecular target for the development of anti-cancer diagnostic and therapeutic drugs. The CLDN18.2-targeted peptide radiopharmaceutical [¹³¹I]I-yg-15 was prepared and evaluated in this study. Molecular docking simulations reveal the binding site between the peptide and the CLDN18.2 protein at the atomic level. Under optimized preparation conditions, [¹³¹I]I-yg-15 achieved a labeling efficiency of 96.86 ± 1.34% and a specific activity of 5.63 GBq/μmol. In CLDN18.2-overexpressing cells, cellular uptake within 1 h was 3.31 ± 0.14%, significantly higher than that in the blocking group (1.0 ± 0.39%). SPECT-CT imaging and biodistribution studies confirmed that [¹³¹I]I-yg-15 specifically targeted and accumulated in CLDN18.2-positive tumor tissues, with a 1-h SUV of 0.41 ± 0.04, initially demonstrating the feasibility of peptide radiopharmaceuticals for the diagnosis and treatment of 18.2-positive tumors.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"335 4","pages":"2987 - 2998"},"PeriodicalIF":1.6,"publicationDate":"2026-03-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147735083","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Radon-222 exhalation mitigation from uranium tailings using CaO-activated lithium slag-based cementitious materials","authors":"Yan He,&nbsp;Ruixiang Xu,&nbsp;Qianlin Li,&nbsp;Xia Liu,&nbsp;Xilong Xue,&nbsp;Qian Kang","doi":"10.1007/s10967-026-10836-w","DOIUrl":"10.1007/s10967-026-10836-w","url":null,"abstract":"<div><p>Uranium tailings (UTs), constituting radioactive solid waste generated during uranium ore processing, facilitate radon-222 (Rn-222) emanation into the ambient environment via their intrinsic porous networks, particularly under dynamic soil–water–air coupling conditions, thereby posing substantial radiological hazards. Radon exhalation mitigation may be achieved through cementation treatments that attenuate pore connectivity in uranium tailings. Lithium slag (LS), a solid waste in lithium battery industries possessing latent pozzolanic properties, was selected to explore a high-value utilization strategy as supplementary cementitious material (SCM). In this study, chemical modification via mixing, melting, and water-quenching with CaO reagent was employed to enhance the reactivity of LS. Characterization results demonstrate that CaO incorporation, functioning as a network modifier, promotes the depolymerization of fully polymerized Q⁴ silicate units through the cleavage of Si–O–Si bonds. This process facilitates the formation of Q³ and Q² species, which are characterized by an increased population of non-bridging oxygens (NBOs). This structural transformation yields reduced binding energy in silicate glass, thereby conferring enhanced pozzolanic activity to the CaO-activated LS (CLS). Cemented UTs samples (CLSU) were prepared from CLS with CaO additions of 0,10, and 20%, ordinary Portland cement (OPC), UTs, and distilled water at a mass ratio of 1:1:4 (CLS:OPC:UTs) and a water to cement ratio of 0.5. Radon exhalation rates (RER) of CLSU samples were quantified throughout a 28-day curing period. Elevated CaO content correlated with significant RER attenuation, and the sample of CLSU20 exhibited an RER of 0.235 Bq·m⁻²·s⁻¹ at 28 days, corresponding to a 34% reduction relative to untreated UTs. Enhanced release of amorphous Si and Al from CLSU samples with higher CaO additions promoted pozzolanic reaction with Ca(OH)₂ (CH), generating supplementary calcium aluminosilicate hydrate (C–A–S–H) gel that densified the microstructure via pore channel filling, as revealed by SEM and MIP analyses. These findings demonstrate an effective strategy for utilizing CLS as a high-performance SCMs to mitigate radon exhalation from UTs, contributing to substantial energy saving for the uranium and lithium industries.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"335 4","pages":"2969 - 2986"},"PeriodicalIF":1.6,"publicationDate":"2026-03-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147734965","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Nitric-oxidized vs alkaline-activated carbon nanomaterials for thorium(IV): mechanism-resolved adsorption and reuse","authors":"Akram I. Abu Shawer,&nbsp;Omar A. Alnasra,&nbsp;Fawwaz I. Khalili,&nbsp;Ehab A. Hamzeh","doi":"10.1007/s10967-026-10806-2","DOIUrl":"10.1007/s10967-026-10806-2","url":null,"abstract":"<div><p>Nanostructured carbons derived from olive pomace were tailored through chemistry-focused oxidation (Bio-N) or texture-focused alkaline activation (Bio-O) to disentangle how surface functionality and pore architecture govern thorium(IV) capture from acidic water. Structure–property analysis revealed that Bio-O provides faster access to binding domains, whereas Bio-N offers stronger temperature-enhanced site affinity. Both materials showed spontaneous, endothermic uptake and effective acid regenerability, with distinct reloading behaviors reflecting their differing chemistries. The study highlights a dual design principle—chemistry-first for capacity leverage and texture-first for rapid capture—establishing olive–pomace carbons as promising low-cost media for radionuclide polishing.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"335 4","pages":"2671 - 2689"},"PeriodicalIF":1.6,"publicationDate":"2026-03-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147735079","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Aging effect on the decontamination efficiency of 137Cs-adsorbed clay minerals using cationic surfactant","authors":"Akihito Matsushima,&nbsp;Herry Wijayanto,&nbsp;Satoru Nakashima","doi":"10.1007/s10967-026-10837-9","DOIUrl":"10.1007/s10967-026-10837-9","url":null,"abstract":"<div><p>Decontamination of ¹³⁷Cs from Fukushima soil is a very important issue after Fukushima Daiichi Nuclear Power Plant accident. Since most ¹³⁷Cs is strongly fixed to the clay minerals in the topsoil, the presence of soil surface contamination further increases the risk of long-term human exposure. Cationic surfactant can be used to desorb ¹³⁷Cs from clay minerals to water phase, and their decontamination efficiency depends on the clay mineral type. However, ¹³⁷Cs adsorbed to Fukushima soil is difficult to be decontaminated. One of the reasons is the aging effect, which causes the stronger retention of adsorbed ¹³⁷Cs over time. In order to investigate the aging effect on the decontamination efficiency from clay minerals contaminated with ¹³⁷Cs, different types of clays (Na- and Ca-bentonite; both predominantly composed of montmorillonite clay mineral) and clay minerals (illite and kaolinite) that had adsorbed ¹³⁷Cs were stored from 0 to 60 days at room temperature, and then they were decontaminated using two types of cationic surfactants (benzyldodecyldimethylammonium bromide (BDAB) and dodecyltrimethylammonium bromide (DTAB)). No change in decontamination efficiency over storage time was observed for kaolinite and Ca-bentonite, while the change was observed for illite and Na-bentonite after 30 days storage. The decontamination using DTAB tended to show more significant storage-time effect (aging effect) than BDAB, which can be attributed to the lower decontamination efficiency of DTAB. The aging effect tends to appear when the layer charge is more negative. This means that the hydrated Cs⁺ in the clay mineral (Cs⁺_aq/clay) is more easily dehydrated and adsorbed to the clay mineral having more negative charge to form inner sphere complex. The differences in aging effect were discussed from the point of the equilibrium between Cs⁺_aq/clay and Cs⁺_adsorption(inner sphere complex) + aq in the layer of clay mineral. It was suggested that there is a difference in the cause between illite and Na-bentonite. Cs⁺_aq/clay may move to the wedge-shaped intermediate zone (frayed-edge site) to be adsorbed as the dehydrated Cs⁺ and then move to the deeper place for illite by exchanging with K⁺. On the other hand, smaller amounts of water adsorption when keeping at room temperature for Na-bentonite compared to Ca-bentonite hinder the equilibrium movement to the hydrated Cs complexes (Cs⁺_aq/clay) direction. Both changes would shift the equilibrium to the dehydrated Cs from hydrated Cs in the clay mineral.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"335 4","pages":"2999 - 3007"},"PeriodicalIF":1.6,"publicationDate":"2026-03-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147734900","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Thermodynamic analysis of the carbon anode reaction in the electrolytic reduction of LWR spent fuel","authors":"Jin-Mok Hur,&nbsp;Sangkwon Lee,&nbsp;Jae Soo Ryu","doi":"10.1007/s10967-026-10831-1","DOIUrl":"10.1007/s10967-026-10831-1","url":null,"abstract":"<div><p>This study presents an equilibrium-based thermodynamic analysis of carbon anode reactions in the electrolytic reduction process for recycling light water reactor (LWR) spent nuclear fuel. The analysis quantitatively evaluates carbonate, carbon, and carbide formation induced by carbon anodes and elucidates their detrimental impact on reduction efficiency. However, these adverse effects can be effectively mitigated by adjusting the anodic potential to a sufficiently positive value that enables the in-situ generation of chlorine gas, which suppresses carbonate and carbon formation.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"335 4","pages":"2937 - 2944"},"PeriodicalIF":1.6,"publicationDate":"2026-03-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147734903","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}