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Radiochimica Acta

International Journal for chemical aspects of nuclear science and technology

Editor-in-Chief: Syed M. Qaim
Edited by: Thomas Albrecht-Schoenzart , Zhifang Chai , Christoph Düllmann , Jonathan W Engle , Prasanta Kumar Mohapatra , Claire Le Naour and Akihiko Yokoyama

Language: English

First published: June 20, 1962

Publication Frequency: 12 issues per year

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Objective
Radiochimica Acta (RCA) publishes manuscripts encompassing chemical aspects of nuclear science and technology. The journal is meant for scientists who are actively engaged in research work.

Topics

radiochemical study of nuclear reactions including heavy ion reactions
radiochemically determined nuclear data for applications
chemical effects of nuclear transformations
radiation chemistry
chemistry of the actinides, transactinides and other radioelements
radioanalytical chemistry
radiopharmaceutical chemistry
scientific and technological applications of radionuclides, stable isotopes and nuclear methods in all fields
environmental and ecological studies using radiochemical techniques
chemistry of the nuclear fuel cycle (especially partitioning)
chemistry of radionuclides in geomedia (especially speciation, migration, etc.)

Article formats
Original Papers, Review Articles, and Rapid Communications (short communications of more timely interest)

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Specialized journal dedicated to all aspects of radiochemistry
Leading journal in the field
Fundamental and applied novel research results
Rigorous peer-review

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Radiochemical investigation of TENORM waste associated with non-nuclear industries: iron and steelmaking – case study

September 26, 2025

Ahmed M. Shahr El-Din, Yasser T. Mohamed, Elsayed M. El Afifi

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The industry of iron and steel production is considered as one of the global economic backbones, and has been worldwide ranked as one of the largest industrial sources of environmental contamination. The radiometric measurements by γ - and α -spectroscopy indicated that the steel waste samples contain natural radionuclides ( 226 Ra and 228 Ra) below the exemption safe limits set by the ICRP and IAEA. The estimated radiological hazard indices as external hazards ( I γ 1 , I γ 2 & I γ 3 ) and internal hazard ( I α ) were below the maximum safe limit (i.e., <1). The estimated ecological risk indices of Cr, Fe, Mn and Ni in the steel waste as single indices (EF, CF and E r ) and integrated indices (CD, PLI and RI) revealed that the accumulated steel waste in its physical state has low ecological risk to the surrounded environment (RI < 150). Moreover, the mobilization behavior of radionuclides and heavy metals in steel waste was investigated using two standard leaching methods (TCLP and EU) to simulate the natural wetting conditions such as rain or groundwater. It is found that natural γ -emitters (e.g., 228 Ra, 226 Ra, 214 Pb, 214 Bi and 210 Pb) and α -emitters (e.g., 232 Th, 238 U, 226 Ra, 210 Po and 222 Rn) are detected in the extraction solution@1 of TCLP test with low activity levels below the safe limits (<10 Bq/L). Also, the concentrations of Fe and Cr were 17.5 and 2.2-folds above the recommended safe limits in drinking water set by the WHO, respectively. Regarding to speciation diagrams, 226 Ra in the steel waste samples can be mobilized out as soluble acetate species (CH 3 COO– 226 Ra–OH and/or 226 Ra(CH 3 COO) 2 ), while the highly toxic Cr 6+ is leached out as soluble anionic species of chromates (HCrO 4 − and CrO 4 2− ) and/or dichromate (HCr 2 O 7 − ) and Cr 2 O 7 2− . Thus, these wastes can be managed to prevent or minimize their hazards; either long-term storage in designated landfills (i.e., engineered), or recycled in civil engineering applications as additives in the cement industry, and roadbed construction…etc.
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Health risk assessment of thoron concentrations in external and internal materials samples used by newborns in Iraq

September 23, 2025

Ban Hussein Ali, Ali Abid Abojassim

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One of the most important radioactive gases in the thorium series is thoron ( 220 Rn). However, it has received less scientific attention compared to radon ( 222 Rn), despite its potential health risks, particularly in vulnerable populations such as newborns. This study aims to compare thoron concentrations in a range of materials commonly used for newborns. 220 Rn concentrations were determined for 120 samples of external materials like (care product) and internal materials like (milk, healthy water, and liquid drugs) used by newborns in Najaf governorate that are available in pharmacies and hospitals. Measurements were done using CR-39 track detectors. Also, some of the radiological risks due to inhalation or ingestion of 220 Rn concentration, such as annual effective dose (AED inhalation and AED ingestion ), Lung Cancer Case (LCC), and Excess lifetime Cancer Risk (ELCR) were calculated. The results of 220 Rn concentrations in the external samples ranged from 4.23 Bq/m 3 to 77.47 Bq/m 3 , with an average of 27.19 Bq/m 3 , while, the results of 220 Rn concentrations in internal samples ranged from 1.49 Bq/m 3 to 49.82 Bq/m 3 , with an average value of 18.34 Bq/m 3 . Also, the results of the radiological risks due to inhalation, such as AED inhalation and LCC × 10 −6 , ranged from 0.02 to 0.29 mSv/y and from 0.29 to 5.28 mSv/y, respectively. The range values of the radiological risks due to ingestion, such as AED ingestion and ELCR × 10 −6 , were 0.0001–0.64 mSv/y and 0.0002–2.47, respectively. Results of 220 Rn concentrations in the present work were within the safe limit according to ICRP (International Commission on Radiological Protection). Thus, studied samples of external and internal materials used by newborns in Najaf governorate were found to be safe.
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Behavior of Cs in Grimsel granodiorite: sorption on main minerals and crushed rock

April 7, 2016

Eveliina Muuri, Jussi Ikonen, Minja Matara-aho, Antero Lindberg, Stellan Holgersson, Mikko Voutilainen, Marja Siitari-Kauppi, Andrew Martin

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In this study the sorption of cesium was investigated on four different minerals; quartz, plagioclase, potassium feldspar and biotite as well as granodiorite obtained from the Grimsel test site in Switzerland. The experiments were conducted in the presence of the weakly saline Grimsel groundwater simulant by determining the distribution coefficients using batch sorption experiments and PHREEQC-modelling across a large concentration range. In addition, the purity of the minerals was measured by XRD and the specific surface areas by BET method using krypton. The distribution coefficients of cesium were largest on biotite (0.304 ± 0.005 m 3 /kg in 10 – 8 M). Furthermore, the sorption of cesium on quartz was found to be negligibly small in all investigated concentrations and the sorption of cesium on potassium feldspar and plagioclase showed similar behavior against a concentration isotherm with distribution coefficients of 0.0368 ± 0.0004 m 3 /kg and 0.18 ± 0.04 m 3 /kg in 10 – 8 M. Finally, cesium sorption behavior on crushed granodiorite followed the trend of one of its most abundant mineral, plagioclase with distribution coefficient values of 0.107 ± 0.003 m 3 /kg in 10 – 8 M. At low concentrations (< 1.0 · 10 – 6 M) cesium was sorbed on the frayed edge sites of biotite and once these sites are fully occupied cesium sorbs additionally to the Type II and Planar sites. As a consequence, the sorption of cesium on biotite is decreased at concentrations > 1.0 · 10 – 6 M. Secondly cesium sorption on potassium feldspar and plagioclase showed similar non-linear behavior with varying concentration. The results were used to assist the interpretation of cesium diffusion process in the 2.5 year in-situ experiment carried out in the underground laboratory at Grimsel test site in Switzerland (2007–2009).
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Natural radioactivity and radiological risk in spices from southeastern Turkey: a pre-earthquake baseline study

December 8, 2025

Gülçin Bilgici Cengiz, İlyas Çağlar, Aysel Güven

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This study aimed to determine the activity concentrations of naturally occurring radionuclides ( 226 Ra, 232 Th, and 40 K) in commonly consumed spices collected from Kilis, southeastern Turkey, before the 2023 Kahramanmaraş earthquakes, and to assess the associated radiological health risks for adult consumers. Eleven spice samples were analyzed using NaI(Tl) gamma-ray spectrometry. Activity concentrations were determined for 226 Ra, 232 Th, and 40 K, and annual committed effective doses (E ing ) were calculated based on an assumed annual spice consumption of 1.8 kg per year. Dose conversion factors recommended by the International Commission on Radiological Protection (ICRP Publication 72) were applied. The mean activity concentrations were 25.70 ± 2.12 Bq·kg −1 for 226 Ra, 24.43 ± 1.65 Bq·kg −1 for 232 Th, and 409.67 ± 24.1 Bq·kg −1 for 40 K. The corresponding average total annual committed effective dose was 27.64  μ Sv·y −1 , well below the global UNSCEAR reference value of 290  μ Sv·y −1 for ingestion of natural radionuclides. Strong positive correlations were observed between 226 Ra, 232 Th, and total dose, indicating their predominant contribution to internal exposure. All measured radionuclide levels in the examined spices were within internationally accepted safety limits, suggesting negligible radiological health risk for typical adult consumers. The findings provide critical pre-seismic baseline data for post-earthquake environmental and food safety assessments in southeastern Turkey.
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Technetium management in liquid-liquid distribution systems for uranium extraction by DEHiBA

December 17, 2025

Peter R. Zalupski, Travis S. Grimes, Corey D. Pilgrim, Santa Jansone-Popova, Jopaul Mathew

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Technetium-99 is one of the most problematic byproducts of nuclear fission due to its high environmental mobility and unpredictable solution chemistry which complicate the isolation and storage options. Efficient management of technetium is difficult in flowsheets designed to recover uranium from used nuclear fuel effluents due to pertechnetate anion’s tendency to follow the uranyl cation. The accessible standard electrode potentials of technetium have offered a gateway to its efficient routing away from uranium based on the manipulation of Tc redox speciation. The intra-molecular oxoanion recognition has been a much less explored strategy, where the main obstacle resides with binding specificity for pertechnetate in mixtures containing great excess of nitrate. This work explores molecular constructs based on the guanidinium moiety, seeking affinity for a pertechnetate anion as expressed in the observable influence on the liquid-liquid partitioning of Tc-99. The unsubstituted guanidinium cations showed evidence of pertechnetate recognition, yielding a modest impact on Tc distribution in mixtures containing a thousand-fold excess of nitrate anion. Guanidiniums containing an amino substituent are oxidized via a Tc-catalyzed redox mechanism which reduces technetium to its tetravalent state. This transformation affords TcO 2+ species, which are excluded from the DEHiBA uranyl solvate in the organic phase. As a result, over 90 % of Tc-99 can be efficiently scrubbed when equilibrated with moderately acidic mixtures of diaminoguanidine.
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Natural radionuclides in sedimentary rocks: monitoring and radiation risk assessment

November 13, 2025

Shalaw Zrar Sedeeq, Jahfer Majeed Smail, Saddon Taha Ahmad

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This study measures and assesses the activity concentration levels of 226 Ra, 232 Th, and 40 K using a gamma ray spectrometry system based on a high-purity germanium detector in sedimentary rocks collected from the Koya Mountains in the Kurdistan region, northeast of Iraq. The mean value of radioactivity concentrations in the rock samples varied from 2.63 ± 0.25 Bq kg −1 in gypsum rock to 378.36 ± 2.62 Bq kg −1 in marlstone for 226 Ra, from 2.53 ± 0.14 Bq kg −1 in gypsum to 28.25 ± 1.92 Bq kg −1 in claystone for 232 Th, and from 15.93 ± 2.01 Bq kg −1 in gypsum to 375.6 ± 6.31 Bq kg −1 in claystone for 40 K. The adequacy of the rock types for building purposes, considering radioactive hazards, was assessed using radiation hazard indices. The obtained results for the absorbed dose rate and the outdoor annual effective dose equivalent showed that the claystone, shale, and marlstone samples exceeded the recommended limits of 59 nGy h −1 and 70 μSv y −1 , respectively.
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Study of dissolved radon and optimization of ²¹¹Rn/²¹¹At generator

December 22, 2025

Koh Tanaka, Yusuke Shimizu, Tomonori Ida, Kohshin Washiyama, Ichiro Nishinaka, Masato Asai, Mariko Segawa, Akihiko Yokoyama

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Alpha particle therapy is gaining attention as a cancer treatment. 211 At, an α-emitting nuclide with a 7.2-h half-life, is ideal for labeled compound production and body retention. However, an accelerator is required for the nuclide production, which limits its use. To address this issue, a 211 Rn- 211 At generator was developed. This generator system utilizes 211 Rn for transport, and 211 At is produced by its decay for on-site use. This study analyzed the dissolution of Rn in solution to investigate gas-phase recovery conditions of Rn in the generator system. The dissolution of a Bi target in a nitric-hydrochloric acid mixture and subsequent neutralization has been shown to enhance the Rn recovery efficiency. In this study, the gas-phase Rn recovery rate reached 88 %, while 50 % of available At has been recovered, and further improvement can be expected in the future.
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The redox behavior of technetium is central to its mobility, separation, and long-term containment

October 31, 2025

Mohamed Touiza, Alexey Vladilenovich Ananiev, Alexey Anatolievich Lavrukhin

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Technetium is part of the fission products of uranium formed during the operation of a nuclear reactor. The accumulation of technetium in the fuel of modern NPPs with VVER-100 type reactors is about 1,090 g/t-U with a burnup of 40 GW·day/t U or 4 % of heavy atoms. the presence of Tc has a significant impact on the processes occurring during SNF reprocessing, since this element is characterized by the half-life is 212 thousand years and the presence of multiple valence forms, as well as catalytic activity and the ability to interact with reducing agents, including those used in Purex, and its removal into radioactive waste together with relatively short-lived ( T 1/2 = 30–50 years) fission products, the handling of which involves near-surface storage, seems unacceptable. Therefore, the removal of technetium into a separate stream at the hydrometallurgical stage and its subsequent isolation in a form suitable for long-term controlled storage in anticipation of transmutation or for deep burial in geological formations are important technological tasks. Interest in redox transformations of technetium is due to the development of new approaches to the processes of spent nuclear fuel reprocessing, radioactive waste management, and the emergence of new redox reagents for the technology of spent nuclear fuel. This review considers the main redox processes that determine the behavior of technetium in SNF reprocessing and in the environment.
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Thermodynamics on the first hydrolysis reaction of dysprosium and holmium in aqueous solutions: potentiometry and calorimetry

November 10, 2025

Qingye Zhou, Hu Song, Shufeng Zhao, Xiang Li, Yuyu Liang, Chenchen Yuan, Zeng Huang, Jun Tu, Xingliang Li

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The potential release of Dy 3+ and Ho 3+ ions from 166 Dy/ 166 Ho or 166 Ho microspheres during radionuclide therapy poses a radiotoxicological risk, as their biochemical behavior is governed by hydrolysis. This study presents a comprehensive thermodynamic investigation of the first hydrolysis step of Dy 3+ and Ho 3+ in aqueous solutions, employing potentiometry and isothermal titration calorimetry (ITC). We report, for the first time, the direct calorimetric determination of the hydrolysis enthalpies for these lanthanides. Our results identify two viable models for the first hydrolysis step – monomeric [Ln (OH)] 2+ and dimeric [Ln 2 (OH) 2 ] 4+ species – with thermodynamic parameters quantified for both. The hydrolysis reactions are endothermic and predominantly electrostatic. Under simulated physiological conditions (pH 7–8), 15–20 % of Dy 3+ and 22–27 % of Ho 3+ are hydrolyzed. A key practical implication is that hydrolysis is thermodynamically disfavored at low temperatures, suggesting that refrigerated storage of microspheres can minimize ion release. These findings provide critical thermodynamic benchmarks for predicting lanthanide speciation and recommend storing therapeutic microspheres at low temperatures to suppress hydrolysis.
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Measurement of neutron capture cross section of the ¹⁶⁵Ho(n,γ)¹⁶⁶Ho reaction at 0.0372 eV energy

December 22, 2025

Amel Dib, Naima Belouadah, Nadjet Osmani

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The neutron capture cross section of the 165 Ho(n,γ) 166 Ho reaction at an incident neutron energy of 0.0372 eV was accurately measured using the horizontal beam channel of the Neutron Diffraction Facility (NDF) at the Es-Salam nuclear research reactor. The Neutron Activation Analysis (NAA) technique via the 197 Au(n,γ) 198 Au reference reaction was adopted. A hyper pure germanium detector was able to detect the gamma ray spectra of the holmium oxide target powder and two thin gold foils. A resulting value of σ ≈ (52.71 ± 2.7) b was determined for the thermal neutron cross section after correction for gamma attenuation effects. There are, so far as we know, no measured cross sections reported in the libraries of neutron databases for such an energy, so the value measured in this work cannot be compared with tabulated data for the 0.0372 ± 0.0014 eV energy. The experimental value was then extrapolated to 0.0253 eV energy, assuming 1/ ν dependence in the thermal energy region, and was compared with experimental values that were integrally measured and evaluated in the literature.
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Efficient removal of U(VI) by self-assembly organic-embedded mesoporous silica spheres

December 10, 2025

Yaorui Li, Yanan Ren, Nanting Qiu, Zhihao Wei, Heyang Sun, Mengxun Liu

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In this research, an in-situ encapsulation strategy for constructing two organic-embedded mesoporous silica spheres (OMSS-1 and OMSS-2) is presented, which achieves efficient U(VI) extraction from solution. By confining L-aspartic acid or citric acid within mesochannels (2.52 nm) during self-assembly, the composites attain exceptional U(VI) affinity. The OMSS-1 and OMSS-2 exhibit high U(VI) adsorption capacities of 172.4 and 188.3 mg/g. The adsorption isothermal and kinetic models are carried out to study the adsorption of U(VI) on the composites. The adsorption processes of U(VI) on OMSS-1 and OMSS-2 are in accordance with Langmuir model and the pseudo-second-order model. Crucially, aspartate-embedded spheres (OMSS-1) demonstrate excellent selectivity in multicomponent systems containing 13 competing ions. The confinement-stabilized ligands enable outstanding regenerability, retaining >93 % capacity over 5 adsorption-desorption cycles with minimal leaching (<0.8 wt%/cycle). This work provides a reference for the design and synthesis of advanced adsorption materials by reconciling the traditionally conflicting objectives of high capacity, specificity, and stability in radionuclide management.
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Improving the sensitivity of atmospheric carbon-14 measurement by liquid scintillation counting through method optimization

December 16, 2025

Hugo Jaegler, Yoan Riquier Marcussy, Danièle Dias Varela, Roselyne Beurel, Patricia Hennequet, Laura Fabbiano, Sandrine Fleury, Olivier Connan, Mariane Rozet, Kevin Galliez, Azza Habibi, Maxime Morin

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Monitoring environmental activities of radiocarbon ( 14 C) requires specific preparation procedures and measurement techniques. For 14 C in air samples, trapped by bubbling in NaOH solutions, the most used technique is the precipitation of carbon as BaCO 3 and activity quantification by liquid scintillation counting (LSC). However, the main drawback is that the solid precipitate in the scintillation cocktail did not form a clear and homogeneous solution in the vial during the measurement period. This issue leads to variability in the quenching effect, poor precision and repeatability, and high detection limits. In the literature, a methodology was proposed using Insta-Gel Plus scintillation cocktail, which can form a gel with the precipitate. In our study, carbonate mass and ultrasonic agitation were optimized, the quenching value remains constant throughout the measurement period, leading to more precise measurements and a lower detection limit. The method was validated using environmental samples previously characterized by accelerator mass spectrometry, as well as spiked samples at very low levels, close to the detection limit. This detection limit was estimated at 0.12 Bq/L or 90 Bq/kg C, demonstrating the method’s capability to analyze 14 C in air samples at environmental levels without influence from nuclear industry.
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The effect of P/Ti ratio in titanium phosphate on the adsorption U(VI) in aqueous solution

November 17, 2025

Ziyi Zhang, Youqun Wang, Wenzheng Cui, Zhibin Zhang, Xiaohong Cao, Yunhai Liu

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Titanium phosphate (TiP) exhibits significant potential for the removal of U(VI) from aqueous solutions. In this study, tetra-n-butyl titanate (TBOT) and phosphoric acid were employed as titanium and phosphorus sources, respectively, and the P/Ti ratio was varied during the hydrothermal synthesis. Both amorphous and α-type TiPs were successfully synthesized, and their physicochemical properties at different P/Ti ratios were characterized using XRD, FTIR, SEM, zeta potential, and TG analysis. The effects of pH and P/Ti ratio on adsorption performance were systematically investigated, revealing that all TiPs achieved maximum adsorption capacity at pH 7.0. The adsorption behavior conformed to the Langmuir model, with a theoretical maximum adsorption capacity of 266.4 mg g −1 at a P/Ti ratio of 2. In the presence of multiple competing ions, amorphous TiP demonstrated higher selectivity for U(VI) compared to α-type TiP. Mechanistic studies indicated that U(VI) adsorption primarily occurs via surface complexation and ion exchange processes on the TiP surface. Overall, the adsorption efficiency of U(VI) can be effectively optimized by adjusting the P/Ti ratio in TiP.
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Scaffold polymer blend based on wheat gluten/poly (vinyl butyral), synthesized by gamma radiation and its application in tissue engineering

November 13, 2025

Sanna R. Mahdy, El-Sayed A. El-Samanody, Mai Khatab, Yasser K. Abdel-Monem, Amal S. Awad, Magdy M. H. Senna

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Polymer blends based essentially on wheat gluten (WG) as a protein polymer and different ratios of poly (vinyl butyral) PVB were prepared by solution casting in the form of thin films and then exposed to different doses of gamma radiation. We looked into how gamma irradiation can improve the compatibility of polymeric blends made with wheat gluten. X-ray diffraction (XRD), scanning electron microscopy (SEM), differential scanning calorimeter (DSC), and Fourier-transform infrared spectroscopy (FTIR) were all examined. The results showed that gamma-irradiation improved the physical properties. It was found that the degradation of the wheat gluten component caused the gel content to decrease at higher irradiation doses. However, the presence of wheat gluten improved the thermal stability at higher irradiation doses. Vero (Monkey kidney) cells proliferate more rapidly in the blend WG/PVB (90/10 %) irradiated to 25 kGy than in the irradiated one. On the other hand, the Paulownia Tomentosa cells proliferation was better in blends with a higher concentration of WG.
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Examining yttrium oxide-doped neodymium-phosphate glass’s optical properties and radiation protection effectiveness

September 8, 2025

Gharam A. Alharshan, Mamdouh I. Elamy, Ragab A. Elsad, Asmaa M.A. Mahmoud, Mohamed Elsafi

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Melt-quenching was used to develop a new glass series with composition (59.5– x ) P 2 O 5 –20 Li 2 O–15ZnO–5Bi 2 O 3 –0.5 Nd 2 O 3 – x Y 2 O 3 , where x = 0.0, 0.25, 0.5, and 1.0 mol%. X-ray diffraction (XRD) was used to investigate these glasses’ glassy structure. Substituting phosphate oxide (P 2 O 5 ) with yttrium oxide (Y 2 O 3 ) increases density and decline molar volume of resulting glass specimen. Y 3+ ions have an impact on the phosphate network by breaking P–O–P bonds, which increases the quantity of non-bridging oxygens (NBOs). The optical measurements of free and doped yttrium were studied in spectral domain from 190 to 1,100 nm. Glasses’ optical characteristics, such as their band gap for direct E g (d) and in direct E g (ind) , surface-energy loss function, and extinction coefficient ( k ), were investigated in connection to energy refractive factor, n , investigated with wavelength. Where band gap E g (ind) decreases from 3.56 eV (N0.5Y0.0) to a minimum of 3.39 eV (N0.5Y1.0). As the Y 3+ ions rises, the transmission (T) falls while reflectance (R) increase suggesting higher absorption and scattering as a result of structural instability and the creation of defect states. The radiation shielding characteristics were then thoroughly evaluated by using Phy-x software and the results were verified with Geant-4 simulation. A modest improvement in LAC values was observed when the mole quantity of Y 2 O 3 in the composite was increased from 0 to 1 mol%. The LAC became 9.921, 10.131, 10.328, and 10.661 cm −1 in N0.5Y0.0, N0.5Y0.25, N0.5Y0.5, and N0.5Y1.0, respectively, for certain energies 0.04 MeV. For N0.5Y0.0, N0.5Y0.25, N0.5Y0.5, and N0.5Y1.0, the radiation shield efficiency (RSE) at 0.081 MeV was 63.0, 63.7, 64.3, and 65.2 % for thickness 0.5 cm, and 86.3, 86.8, 87.2, and 87.9 % for thickness 1 cm. These findings demonstrate the effectiveness of Y 2 O 3 -doped materials in gamma ray blocking, and they may find application in radiation protection.
Open Access
A new type of ¹⁰³Pd/^103mRh generator

December 11, 2025

Tomoyuki Ohya, Jun Ichinose, Kotaro Nagatsu, Yumi Sugo, Noriko S. Ishioka, Hiroshi Watabe, Masatoshi Itoh, Akihiro Nambu, Hiromitsu Haba, Katsuyuki Minegishi, Ming-Rong Zhang

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Rh-103m is one of the best radionuclides for Auger therapy (i.e., targeted radionuclide therapy using Auger emitters). A radioisotope generator ( 103 Pd/ 103m Rh generator) is a feasible tool to supply 103m Rh owing to its short half-life (56 min). However, 103m Rh generators reported previously have drawbacks such as low yield, large volume of recovered extractant, and long operation time. Therefore, we developed a new type of 103 Pd/ 103m Rh generator using 103 Pd (without a carrier), which was adsorbed onto about 20 beads (3.7 mg of resin) of an anion-exchange resin (SA11AL), followed by 103m Rh extraction. We also prepared conventional generator (using 2.7 g of resin) for performance comparison with the new type. The 103m Rh produced by the conventional generator was 62 MBq. The new generator had a yield of up to 82 MBq. The yield of the new generator was 54 % ± 4 % compared with 37 % ± 1.9 % for the conventional one, and the product volume was 450 ± 40 µL compared with 5.9 ± 0.07 mL. Moreover, the operation time was reduced from 14 min to just 5 s. Although the new generator had a breakthrough that was about five times higher than that of the conventional one, the aforementioned benefits (i.e., minimizing volume of extract, shorter operation time, and higher yield of 103m Rh) resulted in the concentration of 103m Rh in the product fraction being about 19 times higher. In addition, the new generator was far smaller and could be handled with greater ease.
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Adsorption of molybdenum-99 on Co(II)–Fe(III) layered double hydroxide and evaluation of ⁹⁹Mo/^99mTc separation: column study

November 10, 2025

Moustafa A. Hamoud, Mamdoh R. Mahmoud, Hanan H. Someda, Mohamed A. Attia

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The efficient and high-purity separation of 99m Tc from 99 Mo is essential for its widespread use in nuclear medicine diagnostics. This work explores the potential of cobalt–iron layered double hydroxide (Co–Fe LDH) as an alternative sorbent compared to the traditional one, alumina (Al 2 O 3 ) for the separation of 99m Tc from 99 Mo in a fixed-bed column system. Co–Fe LDH was synthesized via co-precipitation and comprehensively characterized by Fourier-transform infrared spectroscopy (FTIR), Brunauer–Emmett–Teller (BET) surface area analysis and thermogravimetric and differential thermal analysis (TGA-DTA). The characterization confirmed its mesoporous structure, reasonable surface area (67.7 m 2 /g), and thermal stability up to 600 °C. Static batch experiments were conducted to assess the Co–Fe LDH uptake efficiency for 99 Mo (VI) under varying conditions. The maximum sorption capacity reached 229 mg/g at pH 3, which is higher than many reported sorbents. Furthermore, Co–Fe LDH maintained excellent performance after exposure to gamma irradiation up to 120 kGy, confirming its radiation stability and suitability for radioactive applications. Dynamic column experiments were performed under different experimental conditions to optimize the separation process. The optimal conditions, pH 3, 50 mg/L initial 99 Mo concentration, 0.5 g Co–Fe LDH, and a flow rate of 1 mL/2 min produced a high 99m Tc yield with minimal 99 Mo contamination. The Mo/Tc ratio under these conditions was as low as 0.006 %, demonstrating excellent separation performance.
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Electroextraction of fission element thulium from copper electrode in LiCl–KCl molten salt electrorefining process and its kinetic analysis

December 16, 2025

Huiyu Liu, Yingcai Wang, Yunxiu Zhang, Yuanping Jiang, Zhibin Zhang, Yunhai Liu

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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.
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Adsorption behavior of ¹³⁷Cs towards silica modified with polyacrylamide

November 17, 2025

Abeer E. Kasem, Ezzat A. Abdel-Galil, Riham A. Abou-Lilah

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Polyacrylamide/silicon dioxide (PAm/SiO 2 ) composite was synthesized via free radical polymerization of acrylamide using potassium persulfate as the initiator. The composite was characterized by Flash EA Analyzer (Elemental analysis, C, H, and N concentrations), X-ray fluorescence (XRF), X-ray diffraction (XRD), thermogravimetric analysis (TGA), attenuated total reflectance infrared spectroscopy (ATR/FT-IR), scanning electron microscopy (SEM), and Brunauer-Emmett-Teller (BET) surface area. Adsorption studies were conducted to examine the influence of contact time, solution pH, initial concentration, and adsorbent dose on Cs + adsorption. PAm/SiO 2 composite showed good thermal stability with 78.99 % recovery of adsorbing capacity after drying at 200 °C. Thermodynamic analysis confirmed that Cs + adsorption on the composite is spontaneous and endothermic. Freundlich isotherm model, pseudo-second-order kinetic model, and intraparticle diffusion model successfully explained the adsorption data. Desorption studies have revealed that CaCl 2 is the optimum eluent for full recovery of Cs + (about 90 %). According to column data, Cs + can be loaded and separated from the aqueous environment using different concentrations of CaCl 2 eluent. Practical application experiments also showed the high efficiency of PAm/SiO 2 composite for 137 Cs removal from simulated radioactive liquid solution and contaminated milk, with removal efficiencies of 94.26 % and 90 %, and decontamination factors of 17.43 and 10.25, respectively. These findings validate the promise of the PAm/SiO 2 composite as a highly efficient and economical adsorbent for the remediation of radiocesium in both environmental and food matrices.
Open Access
From bench to batch: scaling up copper-67 production via the ⁷⁰Zn(p,α)⁶⁷Cu nuclear reaction

November 17, 2025

Santiago Andrés Brühlmann, Martin Walther, Nadiya Zhutova, Klaus Kopka, Martin Kreller

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In this work, we present a novel radiochemical separation method for isolating radiocopper from zinc targets, in particular optimized for use in compact cyclotron systems for 67 Cu production from 70 Zn. We further report – for the first time using compact cyclotrons – 67 Cu yields in the GBq range, with molar activities reaching 5–35 % of the theoretical maximum. In addition, high radionuclidic purities comparable to previously described values are presented (>99 %). The complete workflow, including target preparation, irradiation parameters, post-irradiation handling, and quality control, is described in detail, offering a robust and reproducible framework for advancing a reliable 67 Cu production in decentralized settings.

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Radiochimica Acta publishes special and thematic issues focussed on important and emerging topics in the field of study. The journal has established a rigorous process to ensure that any special issue manuscripts follow the same high-quality standards and peer review processes as regular manuscripts. For further information on the journal’s peer review policy please see the "Instructions for Authors".

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Volume 112 | Issue 7-8 Special Issue: NUCAR-2023

Journal Impact Factor	1.7	2024, Journal Citation Reports (Clarivate, 2025)
5-year Journal Impact Factor	1.7	2024, Journal Citation Reports (Clarivate, 2025)
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Editor-in-Chief
Professor Dr. Dr. h. c. mult. S. M. Qaim
s.m.qaim@fz-juelich.de
Forschungszentrum Jülich GmbH
Institut für Neurowissenschaften und Medizin
INM-5:Nuklearchemie
52425 Jülich
Germany

Editors
Professor Dr. T. E. Albrecht-Schönzart, Colorado School of Mines, USA, tschoenzart@mines.edu
Professor Dr. Z. Chai, Institute of High Energy Physics, Chinese Academy of Sciences, China, chaizf@mail.ihep.ac.cn
Professor Dr. Ch. E. Düllmann, Johannes Gutenberg University Mainz, Germany, duellman@uni-mainz.de
Professor Dr. J. Engle, University of Wisconsin, USA, jwengle@wisc.edu
Professor Dr. P. K. Mohapatra, Bhabha Atomic Research Centre, India, mpatra@barc.gov.i n
Dr. C. Le Naour, IJCLAB, France, claire.le-naour@ijclab.in2p3.fr
Professor Dr. A. Yokoyama, Kanazawa University, Japan, yokoyama@se.kanazawa-u.ac.jp

Advisory Board
M.F. Attallah, Egyptian Atomic Energy Authority, Cairo, Egypt
W. Cha, Korea Atomic Energy Research Institute, Republic of Korea,
N. Dacheux, University of Monpellier, France,
R. Eichler, Paul Scherrer Institut, Switzerland,
C. Ekberg, Chalmers University of Technology, Sweden,
N. D. M. Evans, University of Loughborough, UK,
M. Fassbender, Los Alamos National Laboratory, USA,
H. Geckeis, Karlsruhe Institute of Technology, Germany,
J. John, Czech Technical University in Prague, Czech Republic,
S. N. Kalmykov, Lomonosov Moscow State University, Russia,
S. Lahiri, Saha Institute of Nuclear Physics, India,
S. Lapi, University of Alabama at Birmingham, USA
Y. Li, Fred Hutch Cancer Center, Seattle, U.S.A.
Y. Nagame, Japan Atomic Energy Agency, Japan,
S. Parry, Imperial Colleage London, UK,
A. Sengupta, Bhabha Atomic Research Centre, India
R. Taylor, National Nuclear Laboratory, UK,
A. Türler, University of Bern, Switzerland,
M. S. Uddin, Atomic Energy Research Establishment, Bangladesh,
M. Wasim, Pakistan Institute of Nuclear Science and Technology, Pakistan,

Technical Editor
Birgit Zoglmeier
birgit.zoglmeier@degruyterbrill.com

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0033-8230

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eISSN: 2193-3405

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