While whole body counters are employed in in-vivo measurements of internal contamination due to high energy photon emitters, the presence of external contamination can interfere with quantification of activity burden. The present study demonstrated a methodology for screening of Cs external hotspots using Quick Scan Whole Body Monitor (QSWBM) for routine monitoring of radiation workers. In case of accidental scenarios involving broader level of external contamination, estimation of internal contamination using in-vitro method is also discussed here. A set of five ratios (R-values) based on net count rates in QSWBM detectors for anterior and posterior counting corresponding to external contamination as well as internal contamination were evaluated using computational phantoms and FLUKA code. The study demonstrated that implementing two ratios - R (the ratio of net count rates in upper and lower detectors in anterior counting) and R (the ratio of net count rates in anterior and posterior counting) - can effectively screen variety of external hotspot scenarios involving Cs using QSWBM. If persistent and broader external contamination is expected as in case of accidental scenarios, in-vitro method using urine samples and gamma spectrometry can be implemented for quick and reliable estimation of internal contamination. HPGe based detection system was calibrated for 75 mL and 250 mL bottle geometry for accurate measurement of activity excretion rate. Minimum Detectable Activity (MDA) values for this method showed that excretion rate that can lead to Committed Effective Dose (CED) < 1 mSv can be quantified even up to 10 days since intake.

Positron emission tomography (PET) scanner for small animals is of great importance for developing new radiopharmaceuticals for molecular diagnosis and therapy and, thus, for potential clinical applications. The calibration procedure of these systems is essential for quantitative studies and image quality evaluation. It requires several steps, materials, and a suitable phantom. This study aimed to develop a 3D-printed mouse phantom based on the DM_BRA voxel mouse phantom and demonstrate its applicability for small animal PET studies. The physical mouse phantom consists of the 3D printing of a minimum of 2 mm thick with an empty internal cavity corresponding to the real dimensions of the DM_BRA voxel phantom. The model was impermeabilized with epoxy resin to prevent leakage. Counting efficiency and count rates performance evaluations were conducted using the PET scanner (LabPET4 Solo, GE Healthcare Technologies) at the Molecular Image Laboratory (LIM/CDTN/CNEN) in Brazil. Tests revealed that the counting efficiency of the system is about 6.4kCPS·MBq. In general, the absolute values from DM_BRA zoomorphic phantom count rates curves are lower than those from the recommended NEMA NU 4-2008 cylindrical phantom. However, the shape of the count rates curves from both phantoms are very similar: (i) prompt curves increase up to their maximum value at 100MBq and after decrease slowly to around 90 % of the maximum value at 180MBq; (ii) true curves reached their maximum value around 100MBq, corresponding to 50 % of prompt counts; (iii) random curves reach similar plateau value around 50 % of prompt counts; (iv) NEC curves in both studies reach their maximum value at 90MBq. The study revealed that despite the lower counts rates performance, the zoomorphic model offers an anatomically representative design. Its adaptability for different radionuclides and straightforward preparation enhances its usability in routine laboratory protocols.

This study evaluates the influence of body-mass index (BMI) on radiation dosimetry in PET/CT procedures, focusing on radiation dose variations across BMI categories. Data were collected from 1000 patients at Institut Kanser Negara, Malaysia, comprising 516 females (51.6 %) and 484 males (48.4 %) who underwent whole body F-FDG PET/CT procedures from July 2023 to December 2023. Parameters such as administered dose, CTDI, DLP, and effective dose were analysed. The findings indicate that CTDI and DLP values increase with BMI, imposing higher radiation doses for larger patients to maintain diagnostic image quality. Administered doses showed minimal variability across different BMI categories and genders, reflecting standardized radiotracer administration protocols. Male patients generally received higher radiation doses than female patients due to differences in body composition and size. Effective dose (E) from CT scans was significantly higher in patients with higher BMI, ranging from 7.1 ± 2.4 mSv for underweight to 19.3 ± 4.7 mSv for obese patients. Effective dose (E) from PET scans remained relatively consistent across BMI categories, ranging from 0.2 ± 0.07 mSv for underweight to 0.2 ± 0.07 mSv for obese patients, highlighting the need for personalized dosing techniques. All pairwise differences were statistically significant at p > 0.001. This study underscores the necessity for personalized dosimetry protocols that account for BMI variations to optimize imaging quality while minimizing radiation exposure. The study recommends developing and implementing such protocols and establishing guidelines for radiopharmaceutical dosage adjustments based on BMI categories to ensure standardized and safe practices across clinical settings.

Radiotherapy is an effective treatment for cancer, but it should be avoided during pregnancy due to the potential harm to the fetus, which may include malformations, intellectual disability, impaired growth of the head (microcephaly), reduced IQ, and an increased risk of cancer, depending on the gestational age. However, some situations cannot wait until the postpartum period, requiring treatment during pregnancy. The use of mobile shields constructed specially for these specific cases has been reported as a reliable and efficacious way to reduce the fetal doses. In this work, a mobile shield was constructed to be used during the cancer treatment of a pregnant woman's thigh. The shield was built using Monte Carlo simulations and the patient was represented by a voxelized phantom of a 29-year-old pregnant woman. The results show a 26 %-69.5 % reduction on fetal absorbed doses and no extra radiation scattering to the patient, meaning that the mobile shield is safe and efficient.

The mass attenuation coefficient (MAC) plays a key parameter in computed tomography (CT) imaging and the development of novel contrast agents. In practical applications, the MAC depends not only on photon energy but also on complex, interrelated factors such as material composition, contrast agent concentration, and mixture density, exhibiting pronounced nonlinear characteristics. Existing theoretical databases and pointwise simulation methods are often inadequate for rapid, high-resolution predictions across broad parameter spaces. In this work, we propose a new, high-throughput MAC prediction framework that integrates high-resolution Geant4 Monte Carlo simulations with a random forest machine learning regression model. The X-ray attenuation properties of contrast agent-water mixtures were systematically modeled under varying photon energies, molecular weights, concentrations, electron densities, and bulk densities, producing a comprehensive and high-resolution simulation dataset within clinically relevant energy and concentration ranges. Using five key physical parameters as input, the random forest model was trained with normalized preprocessing, grid search hyperparameter optimization, and K-fold cross-validation, yielding good generalization and predictive performance. The proposed method demonstrated strong agreement with Monte Carlo simulations for both training and test sets, as indicated by R, MAE, and RMSE metrics, while improving computational efficiency for large-sample, multivariable cases. Compared with conventional approaches, this study establishes-for the first time-a high-resolution simulation dataset encompassing the major parameter ranges relevant to CT imaging, and realizes a stable, scalable MAC prediction framework based on machine learning. The developed framework enables automated, high-throughput MAC estimation across vast, multi-dimensional parameter spaces, facilitating real-time adaptation to diverse clinical or engineering scenarios.

PSresins have arisen in the past years as a promising material for the measurement of radioactivity. PSresins are a material composed of a PSm support coated with a selective extractant on its surface, allowing the separation and measurement. However, for some applications, a capacity problem could be presented due to the flat surface of the PSm support. For this reason, the objective of this study has been to prepare a macroporous PSm support that allows the preparation of a PSresin for Tc with higher capacity than the current existing PSresin. To achieve this, two porogens, dodecane and heptane, were studied. Both produce pores on the surface with similar diameter, but heptane has the best radiometric characteristics. Several proportions of heptane were studied, observing that an increase in the porogen content increased the surface area and PSm diameter, but with a low effect on the radiometric characteristics. Finally, PSresin for Tc were prepared with these supports. The more porous supports could accept a higher quantity of extractant, thereby increasing the capacity of the PSresin, without significant effect on the radiometric characteristics or the sample volume at which the extractant starts leaching.

With an increasing use of nuclear radiation in medical, industrial, and research fields, effective shielding materials are essential to minimize the risks of radiation exposure. This study explores polyaniline (PA) enhanced with the heavy metal oxide cobalt ferrite (CoFeO or CoFe) as a potential lightweight, flexible, non-toxic shielding material. The gamma-ray attenuation efficiency of these composites was analysed across the energy range 0.015-15 MeV at 31 discrete photon energies with the help of Phy-X/PSD software. The results were further validated using the XCOM software. Additionally, shielding against fast neutrons was studied for the prepared samples and was also compared with the commercially available radiation shielding materials. Results indicate that with cobalt ferrite incorporation, S (0.6 wt% CoFe) exhibited 34.96 % higher FNRC than S (0 wt% CoFe) and 15.96 % better HVL reduction than PVC. The studied PA-CoFe composites exhibit promising radiation shielding capabilities. They can be effectively utilized as lightweight, flexible shielding panels, coatings, casings, and protective barriers in nuclear reactors, medical radiotherapy, and other radiation-intensive environments.

Zirconium (Zr) based ceramic glass is a commonly utilized glass ceramic due to its exceptional mechanical and chemical properties. These materials exhibit high durability and resistance to acid attack, making them prospective materials for ionizing radiation protection applications. This study aims to evaluate the neutron and gamma radiation shielding properties of a Zirconium (Zr) based glass ceramics (ASZx) by computing the Linear attenuation coefficient (LAC), Mean free path (MFP), Half-value layer (HVL), Effective atomic number (Z), and Fast neutron removal cross-section (FNRCS) using WinXCOM at different photon energies. The samples were formulated using varying molar percentages (mol%) of Aluminum Oxide (AlO), Silicon dioxide (SiO), and Zirconia (ZrO) to produce AlO-SiO-ZrO. Results show that ASZ1 displays the highest LAC of 37.71 cm and MAC value of 10.47 cm/g at 0.015 MeV, trailed by ASZ2 and ASZ3, demonstrating that ceramic glasses with higher Zr have higher attenuation properties at lower energies. The result also showed that ASZ1 exhibited a maximum FNRCS value of 0.1072 cm indicating that a composition of ASZ1 ceramic glass is effective in fast neutron shielding than some traditional neutron shielding materials. This suggests that the ASZx ceramic glass system is a potential alternative to commercially available SCHOTT shielding glasses for some special applications.

Monte Carlo simulations are essential tools in dosimetry research for Nuclear Medicine and Radiotherapy, enabling high-precision calculations of radiation dose distribution. Among the available radiation transport codes, MCNP is widely recognized for its robustness and versatility. However, the manual creation of MCNP input files, particularly for voxelized phantoms, remains a labor intensive and error prone task. This work presents the development of GHOST (Generator of Health Optimized Simulation Templates), an automated and efficient tool for generating MCNP input files with voxelized phantoms derived from 3D medical images. GHOST was developed as a plugin for 3D Slicer, written in Python. It constructs lattice format phantoms directly from segmented volumetric datasets, allowing users to assign material definitions based on segmentation labels and to incorporate custom materials beyond the predefined database. To validate GHOST, energy deposition simulations were performed using a 30 × 30 × 30 cm PMMA cube filled with water. The MCNP input file generated by GHOST from an image in MHD format, the result was compared with an equivalent phantom built using RPP cards. Additionally, cross-validation was conducted using GATE, another Monte Carlo simulation platform capable of generating phantoms from medical images. A maximum discrepancy of 2.3% was observed in dose calculations between GHOST generated inputs and both MCNP-RPP and GATE-based simulations. GHOST has proven to be an agile option for the automatic generation of voxelized ghosts to be used in MCNP.

The search for alternatives to toxic lead-based shielding materials is vital for sustainable radiation protection. This study investigates polyvinyl alcohol (PVA) composites reinforced with recycled eco-friendly fillers: granite, glass, and redmud as substitutes for conventional gamma-ray shields. Shielding parameters, including Linear and Mass attenuation coefficients (μ, μ/ρ), Half value layer (HVL), Tenth value layer (TVL), Mean free path (λ), and Effective atomic number (Z), were measured for composites with 10-40 wt% filler concentrations using gamma energies from 511 to 1332 keV. Experimental results closely matched theoretical values determined from XCOM and AutoZeff softwares. The findings show that increasing filler concentrations lead to an increase in μ, μ/ρ, and Z, whereas decrease in HVL, TVL, and λ for all three PVA composites. The maximum value of μ/ρ i.e., 0.090, 0.089, and 0.082 cm/g is observed at 511 keV, and Z i.e., 10.068, 8.527 and 7.988 at 1332 keV for 40 wt% filler concentration for PVA - Granite, PVA-Glass and PVA-Redmud, respectively. Furthermore, among the composites, PVA-granite exhibited the highest μ (0.28 cm), μ/ρ (0.09 cm/g), and Z (10.07), along with the lowest HVL (2.50 cm), TVL (8.31 cm), and λ (3.61 cm) values at 40 wt% for a given energy. These results highlight that PVA-granite acts as a relatively better shielding composite and serves as a promising, lightweight, flexible, and eco-friendly alternative for radiation shielding in medical, nuclear, and aerospace applications.

Accurate and rapid online measurement of alpha radioactivity in radioactive solutions poses significant challenges in the nuclear industry. Conventional methods are often limited by susceptibility to detector contamination, operational complexity, and difficulties in real-time monitoring and calibration. This study presents an innovative online device and methodology based on a rotating-wheel liquid-film technique. A precision wheel generates a stable, uniform ∼100-micron-thick liquid film on its polished surface, enabling direct alpha detection. Optimization of wheel surface finish and rotation speed ensured reproducible film thickness. An integrated compressed air purge system effectively shields the detector from aerosols, preventing background accumulation during extended operation. Crucially, a built-in calibration disk facilitates online measurement calibration. A specially designed high-efficiency ZnS(Ag) scintillation detector enhances detection efficiency while ensuring stability. The performance of the online measurement device was evaluated using a plutonium-containing organic phase solution as the test material. It demonstrated excellent linearity (R = 0.9996) across a wide activity range of 1.16 × 10 to 1.16 × 10 Bq·L. Precision (relative standard deviation, RSD) was ≤2.61 %, with a detection limit of 1.45 × 10 Bq·L. The device maintained good stability (RSD = 1.91 %) during a 10-day continuous operation test. This device exhibits superior detection efficiency, contamination resistance, online calibration capability, and long-term stability, meeting the stringent demands for high-precision, real-time α monitoring in complex radiochemical streams.

The study investigates the generation of bremsstrahlung radiation from electrons in the "Elektronika U-003" accelerator using a tungsten target with a thickness of 1.7 mm and dimensions of 800 × 100 mm, positioned 100 mm from the exit window. It was experimentally established that at a distance of 500 mm from the converter, the uniform distribution of bremsstrahlung radiation corresponds to an area of 80 × 250 mm, with an absorbed dose ranging from 831 Gy to 668 Gy. At a distance of 250 mm, this area measures 90 × 160 mm, with doses ranging from 1.94 kGy to 2.28 kGy. To determine the contributions of bremsstrahlung radiation at various energies, lead "houses" were developed, allowing for the establishment that at energies of 3-5 MeV, the proportion of bremsstrahlung radiation in the interval 0.2 ≤ E < 0.5 MeV is 48.8 %, while in the ranges 0.1 ≤ E < 0.2 MeV it is 34.6 %, 0.5 ≤ E < 1 MeV is 9.6 %, E ≤ 0.1 MeV is 5.5 %, and above 1 MeV is 1.5 %. The results are consistent with calculations performed using the Monte Carlo method. Conditions for electron irradiation and the distance from the tungsten target to the irradiated object were identified, where bremsstrahlung radiation can be used for research objects with dose rates of 1.4 Gy/s and 3.8 Gy/s.

The aim of this study is to evaluate the toxicity (NTCP: normal tissue complication probability) and estimate the risk of induced second primary cancer (EAR: Excess Absolute Risk) following volumetric modulated arc therapy using different regimens. A cohort of twenty prostate cancer patients, median age of 71 years and various stages, was biologically evaluated for organs at risk (rectum, bladder, and small intestine) using different schedules. This was done according to Lyman-Kutcher-Burman (NTCP) and EAR modeling. For each patient, three treatment plans were created and evaluated for dose schedules of 76 Gy/2 Gy/F, 70/2.5 Gy/F and 60 Gy/3 Gy/F. The biological effective dose (BED), was performed, using α/β = 1.5 for the tumour (prostate), and α/β = 3 for organs at risk. The results for the conventional and hypo-fractionated dose deliveryscheduleswere: for rectum, the NTCP (rectal bleeding endpoint) was 9.5 % for 2 Gy fractions, and 10.24 % and 7.6 % for hypo-fractionated total doses of 70 Gy and 60 Gy, respectively. Lower toxicity for the bladder, estimated at 0.05 %, 0.07 %, and 0.01 % for 76 Gy, 70 Gy, and 60 Gy with 2Gy, 2.5 Gy, and 3Gy per fraction, respectively. Linear relationship between the 2nd primary cancer and the "OED" for the linear Exponential model (Bell shape) was obtained for the bladder. In case of the small intestine and bladder, the EAR Mechanistic (Full) model was: 2.10 and 1.96, respectively, at 60 Gy; 2.04 and 2.73 at 70 Gy; and 6.30 and 2.18 at 76 Gy. Hypo-fractionated (HF schedules were beneficial in terms of decreasing the toxicity and the risk of induced second primary cancer.

This study presents a comprehensive theoretical investigation into the production of the medically and industrially relevant radionuclide Zn via the Zn (p, pn)Zn, Zn (d, t)Zn and Zn (α, αn)Zn reactions. A combination of Monte Carlo transport simulations (Geant4 toolkit and SRIM module) and nuclear reaction modeling (TALYS-2.0) was employed to evaluate the reaction mechanisms, excitation functions, and production yields. Stopping powers and penetration ranges of incident projectiles (proton, deuteron, alpha particle) in Zn were calculated using Geant4 and SRIM, showing strong mutual agreement. Excitation functions were simulated using both Geant4's hadronic physics models and TALYS-2.0, incorporating various optical model potentials and nuclear level density (NLD) formulations. Theoretical yields of Zn were determined for each reaction pathway, highlighting a marked improvement in production efficiency with increasing Zn isotopic enrichment. Geant4 was also utilized to assess the impact of target thickness on cross-section behavior, while final activation values and end-of-bombardment (EOB) activities were estimated for each reaction under standardized irradiation conditions. Among the investigated channels, the Zn (p, pn)Zn reaction demonstrated the highest production yield and activity, confirming it as the most effective route for Zn generation within the examined energy range.

High-activity Co irradiators can be adapted for low-dose research without hardware modification. We characterized the Da Nang Irradiation Facility (VINAGA1; 151 kCi ≈ 5.6 PBq) using MCNP6.3 and validated predictions with calibrated Fricke dosimetry across 20-200 Gy. A quasi-uniform plane was established at z = 80 cm above the conveyor base, with a dose-uniformity ratio (DUR) of 1.20-1.46. For most positions, the mean absolute deviation between simulation and measurement was <10 %; one boundary location exhibited 25.7 % due to steep local gradients and millimeter-scale placement sensitivity. Doses used two-sided exposures totaling 7.5-48 min per side, scaled to dose. Within the 60-120 Gy validation window, the mean absolute deviation was 8 % with a -4.9 % bias versus prescription. These results show that a Category-IV panoramic irradiator provides uniform low-dose fields suitable for mutation breeding, phytosanitary treatments, and materials research, offering a practical, cost-effective path to repurpose industrial Co facilities for controlled low-dose Research and Development (R&D), validated for accuracy and reproducibility, with transparent limits and scope.

Targeting breast cancer with radiotherapy demand a strategy by maximizing high dose radiation whilst crucially ensure the neighbouring healthy tissues can be preserved and protected from radiation exposure. In order to diminish this negative effect some radioprotector element seem essential. Current approach of using metal complexes as radioprotector in radiation therapy had shown a promising outcome in advanced targeted radiotherapy.

This study examines the mineralogical and radiological characteristics of mineralized gneiss from the Khor Abaleia and Wadi Nugrus areas in Egypt's Southeastern Desert, with particular emphasis on the mineralogical controls governing natural radioactivity. A total of eighteen representative samples were collected: twelve from two distinct units of the Abalea gneiss (AB1 and AB2) and six from the Nugrus gneiss. Heavy liquid separation, X-ray diffraction (XRD), and scanning electron microscopy with energy-dispersive spectroscopy (SEM-EDS) were employed to characterize heavy minerals and associated radioactive phases. The AB1 gneiss displayed the highest content of total heavy minerals (4.63 wt%), followed by AB2 (2.78 wt%) and Nugrus gneiss (1.85 wt%). Identified radioactive minerals include kasolite, uranophane, thorite, and uranothorite, together with zircon, xenotime, and ferrocolumbite, confirming the polymetallic and radioactive nature of these lithologies. Geochemical and radiometric data reveal marked variations in uranium, thorium, and potassium contents, as well as in disequilibrium states. AB1 samples are enriched in uranium (avg. 346 ppm; up to 4625 Bq/kg) with significant uranium-radium disequilibrium (avg. eU/Ra(eU) = 2.4). AB2 samples, although uranium-bearing (avg. 305 ppm; up to 4588 Bq/kg), exhibit elevated thorium levels (avg. 1588 Bq/kg), extremely low potassium, and low disequilibrium ratios (avg. 0.65), suggest extensive uranium leaching. Nugrus gneiss samples are comparatively less enriched in uranium (avg. 143 ppm; 1680 Bq/kg) but retain moderate thorium and higher potassium contents. All samples investigated exceed international radiological safety thresholds. AB2 is the most hazardous (Raq avg. 6519 Bq/kg; AED 26.7 mSv/year; ELCR 1.23 %), followed by AB1 and Nugrus gneiss. These results demonstrate that mineralogical composition exerts primary control on radionuclide distribution, disequilibrium patterns, and subsequent radiological risk. The findings highlight both the geochemical mechanisms responsible for radionuclide mobilization and the significant health and environmental hazards associated with these rocks. This underscores the necessity for continuous monitoring and risk mitigation strategies in any prospective mining or exposure scenarios.

In the search of tissue-equivalent materials in terms of ionizing radiations to provide solutions to the high demanding modern ionizing radiation applications, this work studies the behavior of the stopping power and the mass attenuation coefficient of two hydrogel-based dosimeters inoculated with Staphylococcus-aureus strains, known as MAA and MAAG, which have proven capability for biological dosimetry. The study is carried out for different energies of electron, proton, and photon beams within their corresponding therapeutic application range. The implemented approaches include theoretical formalisms along with simulation techniques based on the PENELOPE and the FLUKA Monte Carlo codes. Finally, the systems are analyzed using different experimental methodologies. The obtained results exhibit promising behaviors as water-equivalent systems in terms of the achieved consistency when comparing with liquid water reported data.

The objective of this work was to study the changes in track parameters, including diameter, bulk etch rate, and PADC detector sensitivity, due to UVA, UVB, and UVC light exposure. High-energy ions were utilized to conduct a simultaneous comparison of different track parameters. A PADC detector previously irradiated with 300 MeV/n Ni ions and fission fragments (ff from 252Cf) was employed. Fission fragments facilitated the determination of the bulk etch rate. High-energy ions generate identical track dimensions on both sides of the detector after etching. Ni and fission fragment irradiated samples were exposed to UV light in air from one side, while the other side remained unexposed. The compared track parameters included bulk etch rate, track diameter, and detector sensitivity. Eighteen samples (9 for Ni and 9 for ff) were exposed for 1, 2, and 3 h to UVA, UVB, and UVC. Chemical etching of PADC under standard conditions (50 °C, 6.25 M NaOH) for 6 h initially produced tracks on both sides of the detector. After etching, the samples were re-exposed to UVA, UVB, and UVC, and subsequently etched for 3 h. This process was repeated 12 times. The track parameters were measured on both the exposed and unexposed sides. It was observed that the bulk etch rate and track diameter on the UV-exposed side increased; however, PADC sensitivity on the UV side declined. All these parameters were compared to those on the unexposed side. The relative differences between the track parameters on the UV-exposed side and the corresponding ones on the unexposed side were estimated and analyzed. UVA showed little effect on the track parameters, UVB demonstrated a medium effect, while a significant effect was noted with UVC. Recommendations are provided for the optimal use of UV pre-exposure to sensitize detectors and enhance the readability of chemically etched tracks.

In this work, the sorption and selectivity behaviour of Cs(I), Co(II), and Fe(III) from aqueous solutions onto cerium tungstate (CeW) and cerium zirconium tungstate (CeZrW) was studied using the batch technique. CeW and CeZrW have been synthesized and characterized using different analytical tools, including XRD, FT-IR, XRF, TGA, and DTA. XRF data confirm that CeW and CeZrW have the chemical formulas CeWO.4HO and CeZrWO.5.4HO, respectively. For the sorption process, some parameters, including the influence of shaking time, sorbent dose, ionic strength, capacity, desorption, and recycling, were studied. The results showed that the sorption of the studied cations is independent of ionic strength and dependent on sorbent dose. Also, CeW and CeZrW are suitable for the separation of studied cations from aqueous solutions with the selectivity sequence: Fe(III) > Co(II) > Cs(I). Desorption of the studied cations from the loaded CeW and CeZrW was done by different concentrations of HNO as eluent. The recycling results showed that CeW and CeZrW could be recycled for up to 12 and 8 cycles of sorption-desorption regeneration, respectively, with a low decrease in the % uptake. CeW and CeZrW are effective sorbents for the sorption of Cs(I), Co(II), and Fe(III) from aqueous solutions, as evidenced by the excellent recycling results.