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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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About this journal

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)

Your Benefits

Your benefits:

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

History

The journal Radiochimica Acta was founded in 1962, under the patronage of the Nobel Laureate Otto Hahn, to cater for the publishing needs of the then fast expanding field of radiochemistry. In those days the radiochemists published their work in several different journals of chemistry and physics and had thus no platform of their own for technical communications. With the introduction of Radiochimica Acta a new era dawned for radiochemistry. Although published in Germany, right from its inception the journal aimed at inculating an international character and flavor. The international character has been maintained, continuously nurtured and further developed over its liefe of 50 years. Today all the articles are published in English language.

Visit our Special Jubilee Issue

Visit our open access journal Proceedings of Radiochemistry

Other publications in the field
P. Adloff, K. Lieser, G. Stöcklin,One Hundred Years after the Discovery of Radioactivity, De Gruyter 2008.

Back Issues

Volumes 1 to 103.

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Enhancing physico-chemical and antibacterial properties of gamma irradiated poly (vinyl alcohol) films filled with silver-bagasse fiber nanocomposite

September 29, 2025

Mohamad Bekhit, Heba A. Raslan, Mohamed S. Abd El-Al, Khaled F. El-Nemr

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Recently, environmental pollution and inhibition of non-degradable and non-renewable resources have attracted researchers to develop a new kind of natural products. Fibers obtained from natural sources provide certain assistance to synthetic fibers because of their characteristics such as low cost, low density, non-toxicity and similar strength, and they do not encounter any problem during the disposal of materials into the environment. Silver nano-hybrid materials are getting much attention in antibacterial applications, due to its bactericidal nature. In this study, nanosilver-bagasse (Ag-bagasse) fiber as a nanocomposite was successfully prepared by using gamma radiolysis method. The Ag-bagasse fibers were blended with PVA at different weight ratioto improveits physicochemical and antimicrobial capabilities. All prepared films were exposed to 25 kGy of gamma radiation. Various analytical techniques are utilized to investigate the crystal structures, functional groups and surface morphology of the prepared Ag-bagasse fiber and PVA nanocomposite films. XRD shows the formation of silver nanoparticles over bagasse fiber in a single phase with an average crystallite size 10.89 nm. The mechanical properties of nanocomposite films obtained with different amounts of Ag-bagasse fiber reinforcement have been demonstrated. The PVA films were strengthened by the addition of Ag-bagassefiber and the optimum ratio was 5 wt%. Owing to the addition of Ag in the biopolymer matrices, the PVA/8 % Ag-bagasse nanocomposite film demonstrated good antibacterial activity against Escherichia coli , Salmonella typhimurium , Staphylococcus aureus , and Bacillus subtilis . The utilization of bagasse fiber can boost the economic worth of agricultural waste, and the unique characteristics of PVA/Ag-bagasse nanocomposites may find application in the packaging and medical industries.
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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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Performance degradation of crystalline silicon solar cells under bremsstrahlung exposure

September 11, 2025

Ismail Kabacelik

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This study investigates the degradation of crystalline silicon (c-Si) solar cells under high-energy polyenergetic Bremsstrahlung radiation, relevant to space and high-radiation terrestrial environments. Cells were irradiated with doses up to 900 Gy using a clinical linear accelerator (cLINAC). Results demonstrate significant dose-dependent performance loss, with the power conversion efficiency ( η ) decreasing by approximately 7.6 % at the highest dose of 900 Gy. This degradation was driven mainly by reduced short-circuit current density ( J sc ) and increased recombination. External quantum efficiency (EQE) measurements confirmed substantial losses at longer wavelengths, indicating bulk defect generation. Capacitance and conductance analyses revealed the accumulation of deep-level traps and interface states, further elucidating the degradation mechanisms. These findings highlight the vulnerability of c-Si solar cells to Bremsstrahlung exposure and provide critical insights for developing radiation-hardened photovoltaic technologies.
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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.
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Design and evaluation of multi-layer polybenzoxazine composites for enhanced gamma and neutron shielding

September 8, 2025

Hasan Oğul

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This study investigates the gamma and neutron shielding performance of novel polybenzoxazine (PBz) based composites reinforced with Mo 2 C, Boron, and WS 2 additives. The additives are mixed into the matrix at various mass ratios and then each sample is evaluated in terms of radiation interactions. A three-layered shielding structure was further designed with PBz-Mo2C-25 as the front layer, PBz-B-25 as the intermediate layer, and PBz-WS2-25 as the rear layer. The obtained results show that multi-layer configuration, PBz-3L, further enhanced low-energy neutron attenuation, achieving substantially greater reductions in thermal and epithermal flux compared to single-layer Mo 2 C- and WS 2 -reinforced composites. For photons, the multilayer structure achieves radiation protection efficiency (RPE) values exceeding 99 % at low gamma energies. Total ionizing dose (TID) and displacement per atom (DPA) analyses are also reported. These findings confirm the superior shielding capability of the three-layer composite, highlighting its potential for advanced radiation protection applications in nuclear and aerospace environments.
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Radiosynthesis and preclinical evaluation of [^99mTc]Tc-HYNIC–durvalumab for immuno-SPECT imaging of PD-L1 expression in tumor models

September 2, 2025

Syed Qaiser Shah, Ralph Santos-Oliveira, DeryaIlem-Ozdemir, Saba Shirin

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Accurate, non-invasive measurement of programmed death-ligand 1 (PD-L1) expression is crucial for the optimization of immune checkpoint inhibitor cancer treatments. We describe the radiosynthesis and preclinical assessment of a new technetium-99m ( 99m Tc) conjugated immuno-SPECT agent, [ 99m Tc]Tc-HYNIC–durvalumab, for PD-L1 imaging in vivo . Durvalumab was conjugated with hydrazinonicotinamide (HYNIC) through lysine residues using an N-hydroxysuccinimide (NHS) ester-based method and subsequently radiolabeled with technetium-99m ( 99m Tc) in the presence of tricine and ethylenediamine-N,N′-diacetic acid (EDDA) as co-ligands. Radiochemical purity, physicochemical stability in physiologically relevant media, and immunoreactivity were determined. Specific binding affinity and kinetics of internalization were studied in PD-L1-positive A549 cells. Biodistribution and SPECT imaging were carried out in A549 xenograft-bearing mice and rabbits. Specificity was confirmed by co-injection with an excess of unlabeled durvalumab. 99m Tc-HYNIC-Durvalumab had 98.14 ± 0.27 % radiochemical purity and good stability (>90 % intact at 4 h in serum). The tracer showed high PD-L1 affinity and extensive receptor-mediated binding (28.54 ± 0.65 % at 4 h). In vivo , tumor uptake at 4 h post-injection was 6.42 ± 0.11 %ID/g, significantly reduced by co-administration of excess unlabeled antibody (1.56 ± 0.05 %ID/g, p < 0.01). Tumor-to-background ratio was 3.84, allowing for high-contrast SPECT imaging that accurately defined PD-L1-expressing tumors. These findings support 99m Tc-HYNIC-Durvalumab to be a highly specific, stable, and clinically translatable SPECT radiotracer for quantitative PD-L1 expression imaging. This agent has great promise to enable patient stratification and therapeutic monitoring in immuno-oncology. Further studies toward clinical translation is warranted.
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Excitation functions of (p,γ) and (p,n) reactions on zinc up to 4 MeV

September 2, 2025

Md. Shuza Uddin, M. Mehedi Hasan, Md. Moniruzzaman, M. Asad Shariff, Syed M. Qaim

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Proton-induced reaction cross sections for 64 Zn( p,γ ) 65 Ga, 67 Zn( p,γ ) 68 Ga, 70 Zn( p,n ) 70 Ga, and nat Zn( p,x ) 67 Ga were measured in the 2.0–4.0 MeV energy range at a 3 MV Tandem Accelerator, using the stacked-foil activation technique in combination with high resolution γ -ray spectrometry. The obtained results are comparable to literature data determined via prompt γ -counting and X-ray counting methods. The excitation functions of this work are reproduced well by a model calculation using the code TALYS with a few chosen input parameters. The data should be useful in astrophysical research as well as in production of radionuclides at a small medical cyclotron.
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Study on the migration of radioactive nuclides Uranium (U) and Thorium (Th) and the properties of solid waste in coal-fired power plants with zero liquid discharge of desulfurization wastewater

August 19, 2025

Changan Kang, Mingbiao Luo, Min Liu, Linxi Zhang, Rong Zou, Lin Yang, Yushuang Yuan, Qiang Yao, Yang Zou, Jun Li, Rongxing Lin, Ruihe Lyu

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In order to investigate the migration and distribution characteristics of radioactive nuclides Uranium (U) and Thorium (Th) in coal-fired power plant with zero liquid discharge of desulfurization wastewater, the fly ash, slag, gypsum and particulate matter from a 1000 MW coal-fired power plant were tested and leaching toxicity assessment of fly ash, slag and gypsum was performed.(1)Studies on the migration of radionuclides U and Th show that: U and Th radionuclides introduced by coal burning are mainly enriched in fly ash, U constitutes 88.8 % of the total U content, Th comprises 92.2 % of the total Th content.(2)The enrichment degree of U and Th in solid waste is related to the particle size of solid waste, the content of U and Th in fly ash is 1.67 and 2.19 times that of U and Th in slag. U and Th are more enriched in fine particulate matter, and the enrichment level of Th shows a greater dependence on particle size.(3)Testing of the leaching toxicity of U and Th in solid waste was conducted to evaluate the environmental risks associated with U and Th contaminants, the results show that among all solid waste leachates, the concentration of U in gypsum leachate is the highest, and the concentration of Th in slag leachate is the highest, this suggests that gypsum facilitates U leaching, while slag enhances Th mobility. Gypsum and slag are more likely to impact the environment when exposed. (4) By calculating the input and output of U and Th, verification of the U and Th mass balance was performed. The mass balance rates of U and Th are 128.5 % and 121.4 %, respectively, indicating that the detection data are reliable and acceptable.
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Incomplete fusion reaction producing ²³⁴U, ²³³U, and ²³²U in the ²³²Th + ⁷Li reaction

August 15, 2025

Ayumu Nagai, Hiroyuki Hosokawa, Kakeru Teranishi, Ryoga Morita, Ayano Seto, Akihisa Nakajima, Yukiko Komori, Takuya Yokokita, Daiki Mori, Yudai Shigekawa, Akihiro Nambu, Yang Wang, Aya Sakaguchi, Hiromitsu Haba, Akihiko Yokoyama

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The nuclide of 237 Np ( t 1/2 = 2.1 × 10 6  y), produced in nuclear facilities, is important because its investigation is relevant to environmental pollution and material cycling in earth sciences. It is expected to be analyzed by mass spectrometry with a neptunium tracer as a spike, such as 236g Np ( t 1/2 = 1.5 × 10 5  y). Our research group has collected fundamental data for cross-sections of the 232 Th + 7 Li reaction products for use in spike production and chemical separation. In addition to the complete fusion reaction producing Np nuclides, incomplete fusion also occurs, especially in the reaction of 7 Li, which splits into α and t and only a part of the projectile fuses with the target nucleus. In this study, the excitation functions of 234 U, 233 U, and 232 U, produced by the incomplete fusion, were measured. The reaction mechanism is discussed by comparing the experimental values with those calculated using the EMPIRE code. In addition, we investigated the effect of incomplete fusion on the overall reaction.
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Crystal structures of non-centrosymmetric fluorouranylates Na₃[UO₂F₅] and CaRb₄[UO₂F₄]₃⋅3H₂O

August 14, 2025

Viktor N. Serezhkin, Mikhail S. Grigoriev, Marina V. Sukacheva, Anton V. Savchenkov, Larisa B. Serezhkina

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The structure of Na 3 [UO 2 F 5 ] (I) and CaRb 4 [UO 2 F 4 ] 3 ⋅3H 2 O (II) crystals was studied using X-ray diffraction analysis. The uranium-containing structural units are pentagonal bipyramids [UO 2 F 5 ] 3− , which are isolated from each other in I and linked by bridging fluorine atoms into trinuclear complexes of the composition [(UO 2 ) 3 F 12 ] 6− in II. The latter one fills the existing gap in the crystal chemistry of uranyl fluorides and oxofluorides by representing the first example of a trinuclear complex, while di-, tetra- and pentanuclear complexes have been observed before. The first compound has been known for more than half a century, although here we present the first report on its crystal structure. The crystal chemical formulae of the uranium-containing complexes in I and II are AM 1 5 and A 3 M 2 3 M 1 9 , where A = UO 2 2+ , М 2 and М 1 = F − . In both structures, the uranyl-containing complexes are linked into 3D frameworks by R –F and R –O coordination bonds with outer-sphere R cations ( R = Na, Rb or Ca). As both compounds I and II turned out to be non-centrosymmetric their ability to generate the second harmonic was theoretically predicted based on parameters of Voronoi–Dirichlet polyhedra. Experimental verification of the obtained values is of undoubted interest.
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Extraction and stripping behaviour of U(VI) from TBP/n-dodecane phase containing the degradation product HDBP

August 13, 2025

Mukundan Poornima, Sareddy Ramakrishna Reddy, Manavalan Balamurugan, Konda Athmaram Venkatesan

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The separation of uranium and plutonium from the spent nuclear fuel solution is performed by the liquid-liquid extraction of actinides from the fuel solution in to the organic phase consisting of tri-n-butylphosphate (TBP) in n -dodecane ( n -DD). In this process, the TBP undergoes chemical and radiolytic degradation to yield dibutylphosphoric acid (HDBP), which is the major degradation product of organic phase. The presence of HDBP in organic phase alters the extraction of actinides to some extent, but severely affects the back extraction of actinides from the loaded organic phase during recovery. In view of this, the present investigation deals with the extraction and stripping behaviour of U(VI) (1 g/L = 0.0042 M) in both the batch and continuous counter-current mode using 1.1 M TBP + 0.015 M HDBP/ n -DD. The results were compared with those obtain in the absence of HDBP. The effect of HDBP on the distribution ratio of U(VI) in 1.1 M TBP/ n -DD was studied, and the number of contacts required for extraction and stripping of uranium was determined in the cross-current mode. A continuous counter-current extraction experiment was performed in a 16-stage annular centrifugal extractor (ACE) bank and the stage profiling of uranium and nitric acid, and the duration needed for the attainment of steady state was determined. Similarly, the stripping of uranium from the loaded organic phase was performed using 0.01 M nitric acid, as well as with dual acid (4 M and 0.01 M) at different locations of the ACE bank. About three stages were adequate for complete extraction of U(VI) from 4 M nitric acid in to both organic phases. While the recovery of U(VI) from 1.1 M TBP/ n -DD was quantitative in six stages, the entire amount of U(VI) was retained in the organic phase containing HDBP during stripping with 0.01 M nitric acid. In contrast to this observation, the stripping of U(VI) from 1.1 M TBP/ n -DD with dual acid displayed the unusual accumulation of U(VI) in the ACE bank due to the introduction of 4 M HNO 3 , which was facilitating the re-extraction of U(VI) in the bank, and the steady state, in this case, was achievable beyond 630 min of the counter-current run. The recovery of U(VI) from the HDBP containing organic phase was negligible during stripping with dual acid, and the poor recovery was essentially attributed to the formation of strong HDBP complexes of uranium retained in the organic phase.
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Radiation synthesis of superabsorbent hydrogels based on Carbopol 940 for fast swelling and slow release of urea fertilizer

August 12, 2025

Tarek Mansour Mohamed, Ehab E. Khozemy, Shaimaa M. Nasef

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In this study, a superabsorbent hydrogel based on Carbopol 940, carboxymethyl cellulose sodium salt (NaCMC), and acrylic acid (C/NaCMC/PAc) was prepared using gamma radiation. This technique serves as a clean and effective method for initiation and crosslinking, intended for agricultural use as a slow-release urea fertilizer. The parameters affecting the gelation percentage, such as Ac and Carbopol contents, as well as different irradiation doses, were studied. The optimal conditions for preparing C/NaCMC/PAc hydrogel were achieved with acrylic acid and Carbopol concentrations of 5 wt% and 3 wt%, respectively, at an irradiation dose of 5 kGy. The swelling rate was enhanced by increasing the Carbopole content, while its degree was enhanced by treating the prepared hydrogel with di-ethanolamine and raising the pH, reaching a swelling degree to 78 g/g. FTIR, XRD, EDX, and SEM were performed to characterize the structure and properties of the fabricated hydrogels. The synthesized hydrogels exhibited excellent urea loading (92 %) and slow release (91 % after 16 days). The extended urea release of Carbopol-co-poly-Ac hydrogels makes them a potential candidate for controlled delivery of urea fertilizer. The data showed that the prepared superabsorbent hydrogel has some advantages and can be used as a slow-release urea fertilizer.
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Development and evaluation of ¹⁷⁷Lu-imatinib: radiolabeling and cell culture studies

July 10, 2025

Emre Ozgenc, Merve Karpuz, Gunnur Guler, Zeynep Burak, Yücel Başpınar, Evren Atlıhan Gundogdu

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Targeted radiopharmaceuticals offer promising approaches for cancer diagnosis and therapy. This study developed freeze-dried kit formulations of 177 Lu-Imatinib (IMT) and evaluated their potential efficacy through in vitro studies. Four formulations (F1–F4) containing IMT and chelating agents were prepared and characterized via Fourier transform infrared (FTIR), ultraviolet spectrum (UV), and thermogravimetric analysis (TGA) to confirm complex formation. Biocompatibility was assessed in NIH-3T3 cells using the MTT assay. Radiolabeling with 177 Lu was optimized by varying pH, incubation time, and reactant ratios. Radiochemical purity and stability were analyzed over 7 days using HPLC. Binding affinity and cytotoxicity were evaluated in MCF-7 and NIH-3T3 cells. Spectroscopic analyses confirm successful complex formation. All formulations exhibited >90 % viability in NIH-3T3 cells. Optimal radiolabeling conditions (45 mg IMT-chelator, pH 5, 60 min incubation) yielded >90 % efficiency, with stable radiolabeling for 7 days. The 177 Lu-IMT-DOTA (F3) formulation showed significantly higher binding and cytotoxic effects in MCF-7 cells compared to controls. The 177 Lu-IMT-DOTA (F3) kit demonstrates high radiolabeling efficiency, stability, and selective in vitro cytotoxicity toward breast cancer cells, supporting its potential as a targeted radiopharmaceutical.
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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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Experimental investigation for the impacts of Er₂O₃ content on enhancing the physical and radiation shielding capabilities of composites based-epoxy

January 1, 2000

Mohammed I. Sayyed, Karem A. Mahmoud, Taha Yaseen Wais, Laith Ahmed Najam

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By employing erbium oxide (Er 2 O 3 ) as fillers, the current study seeks to improve the physical and radiation shielding performance of epoxy composites. Therefore, a series of epoxy-based composites were fabricated according to the chemical formula of (90− x ) epoxy + 10 Eu 2 O 3 + x Er 2 O 3 ; x ≈ 0, 5, 10, and 15 wt%. The impact of Er 2 O 3 fillers on the physical and radiation shielding properties of the prepared composites was investigated experimentally. The change in density of prepared epoxy-based Er 2 O 3 composites was measured according to the Archimedes method. The recorded data confirms an increase in the prepared composites’ density between 1.188 ± 0.018 g/cm 3 and 1.375 ± 0.021 g/cm 3 when the Er 2 O 3 concentration raised throughout a concentration range of 0–15 wt%. The impact of Er 2 O 3 on the gamma-ray shielding performance of epoxy-based composites was evaluated experimentally using the narrow beam transmission method. During the application of the narrow beam transmission method, a 5.08 × 5.08 cm NaI (Tl) crystal and two radioactive sources (Cs-137 and Co-60) were utilized. The measured data showed that the increase in Er 2 O 3 concentrations between 0 wt% and 15 wt% enhances the linear attenuation coefficient of the prepared composites between 0.0959 ± 0.0051 cm −1 and 0.1093 ± 0.0069 cm −1 , respectively, at 0.662 MeV. The investigation shows that the increase in the Er 2 O 3 concentration improves the linear attenuation coefficient by 14.04 %, 11.62 %, and 15.73 % at 0.662 MeV, 1.173 MeV, and 1.332 MeV, respectively.
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Cerium oxalate precipitation: effect of process and operating parameters on cerium oxalate particle size distribution

January 1, 2000

P. Vishnu Anand, Saroj K. Panda, Amit Kumar, Pankaj, Satyabrata Mishra, J. Gnanasoundari, R. Rajeev, N. Desigan, K.A. Venkatesan, A.W. Patwardhan

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The oxalate precipitation process has been adopted for the reconversion of plutonium nitrate present in nitric acid solution to plutonium oxide powder at the backend of nuclear fuel cycle. Due to the radioactivity associated with plutonium, the testing and development of plutonium oxalate precipitator can be conveniently performed using a non-radioactive surrogate such as cerium. In the present work, the effect of various operating and process parameters such as the concentration of nitric acid, cerium nitrate and oxalic acid, impeller design and speed, mode of precipitation on the particle size distribution of cerium oxalate was investigated. The results showed that the concentration of nitric acid and mode of precipitation were found to affect the particle size distribution of cerium oxalate to a significant extent. The D 50 of the cerium oxalate particles increased nearly five times (21–98 µm) with increasing the nitric acid concentration from 0.5 to 4.0 M. Forward strike mode of precipitation doubled the D 50 of cerium oxalate from 34 to 74 µm as compared to the typical batch precipitation. The cerium ion concentration in feed solution showed the negligible effect on D 50 of cerium oxalate, whereas width of the particle size distribution increased from 0.9 to 2.0 with increase of cerium in nitric acid from 3 to 43 g L −1 . Lowering the concentration of oxalic acid produced smaller sized particles with broad particle size distribution. For real applications, the surrogate studies showed that it is important to control the concentration of nitric acid in the feed solution for producing bigger plutonium oxalate particles, which is required for facile operation, and to minimize the loss of residual plutonium in the filtrate.

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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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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

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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.in
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. 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,

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eISSN:

2193-3405

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0033-8230

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First published:

June 20, 1962

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eISSN: 2193-3405

ISSN: 0033-8230

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