This study investigates the use of Electric Arc Furnace Steel Slag (EAFSS) in radiation shielding concrete, focusing on the combined effects of replacement level, particle size, and curing duration on mechanical behavior, gamma-ray attenuation, and environmental and economic performance. The results indicate that partial replacement of coarse aggregates with EAFSS significantly improves compressive strength, reduces water absorption, and enhances radiation shielding, whereas full replacement of sand or simultaneous substitution of cement and aggregates lead to considerable performance losses. Prolonged curing from 7 to 90 days further increased strength and improved shielding efficiency. From a sustainability perspective, partial cement replacement offered the greatest benefits, including reductions in energy consumption, CO emissions, and overall costs. These findings highlight that an optimized balance in the type and level of replacement can produce concrete with high mechanical strength, effective radiation protection, and improved environmental performance. The study underlines the industrial potential of EAFSS as a sustainable substitute for conventional materials in shielding concrete applications.

This study assessed the radioprotective efficacy of an ethanolic extract from the walnut kernel internal septum (Juglans regia L.) in Wistar rats exposed to a lethal X-ray dose of 6.73 Gy. The extract was administered at 400, 1600, or 6400 mg/kg, either 2 h before (pre-treatment, n = 7 per group) or after (post-treatment, n = 9 per group) irradiation, with survival monitored over 30 and 60 days. In pre-treated rats, the high dose (6400 mg/kg) consistently provided full protection, surpassing radiation-only controls which showed significant mortality (42.9 ± 7 % at 30 days and 28.5 ± 7 % at 60 days survival rates). Low dose (400 mg/kg) showed reduced efficacy, especially over time. Post-treatment groups also benefited from the high dose, maintaining 100 % survival, whereas radiation-only controls had higher mortality (77.8 ± 6 % at 30 days and 22.2 ± 6 % at 60 days survival rates). Medium and low doses post-treatment yielded partial benefits, with survival ranging from 22.2 % to 44.4 % by day 60. These dose-dependent effects suggest that antioxidants, likely phenolics or flavonoids, mitigate radiation-induced oxidative damage, with 6400 mg/kg providing a critical threshold for efficacy. Safe up to this dose, the extract outperforms other walnut components and synthetic radioprotectors in tolerability and potency. However, lower-dose variability and lack of chemical profiling highlight areas for further research. This novel septum extract emerges as a promising, natural radioprotector for applications in medical radiation safety and emergency scenarios, warranting investigation into its active compounds and mechanisms.

Naturally occurring radionuclides are fundamental contributors to terrestrial radioactivity and play a crucial role in determining background radiation levels and associated health risks. This study evaluates the distribution of Ra-226, Th-232, and K-40 in soils of the Union Territory of Ladakh and assesses the potential radiological hazards to its inhabitants. Seventy soil samples collected using a 10 × 10 km grid network were analyzed using a NaI(Tl) gamma-ray spectrometer, calibrated with IAEA-standard reference sources. The activity concentrations of Ra-226, Th-232, and K-40 ranged from 10.8 to 128, 14.7-150, and 73.5-968 Bq kg, respectively, with mean values exceeding global averages. Spatial heterogeneity reflected the complex geology of the Ladakh Batholith and associated volcanic and sedimentary formations. Radiological parameters, including radium equivalent activity, hazard indices, absorbed dose rates, and age-dependent annual effective doses, were computed to assess exposure risks. The mean radium equivalent was 161.8 Bq kg, while indoor and outdoor absorbed dose rates averaged 139.5 nGy h and 73.9 nGy h, both higher than UNSCEAR global means. Infants and children exhibited higher organ-specific doses, particularly in the bone surface and red bone marrow. Although average hazard indices were below the recommended limits, localized zones exhibited elevated values, indicating potential radiological concerns. Continuous monitoring of radionuclide levels is recommended due to spatial variability and heightened sensitivity of younger age groups to radiation exposure.

Anthropogenic Iodine-129 (I) is a critical long-lived radionuclide for tracing ocean circulation and environmental contamination. However, its measurement is costly and yields spatially sparse data, limiting comprehensive environmental assessment. This study proposes a novel, integrated machine learning framework to predict the concentrations of not only anthropogenic I but also stable I and their isotopic ratio (I/I) in the South China Sea using readily available oceanographic parameters. A Bayesian Neural Network (BNN) was developed as the core predictive model to provide robust uncertainty quantification for each estimate. The BNN's complex hyperparameters were systematically optimized using the Improved Snow Goose Algorithm (ISGA), a powerful metaheuristic method designed to efficiently navigate complex search spaces. The optimized ISGA-BNN framework demonstrated high predictive accuracy for all three targets when evaluated on an independent test set. The models achieved R values of 0.9623 for I, 0.9286 for the I/I ratio, and 0.8148 for I. Diagnostic analysis confirmed that the BNN provided well-calibrated uncertainty intervals, accurately capturing the confidence level of each prediction. This framework represents an advancement by providing accurate, multi-target predictions with vital uncertainty estimates, holding potential for enhancing environmental monitoring and optimizing future sampling campaigns.

With the intention of investigating the impact of AlO replacement by CdO on the physical, structural, and optical properties of sodium barium phosphate glasses with chemical compositions of 20NaO-25BaO-(15-x) AlO-xCdO-40PO were created using the traditional melt-quenching technique with coded as Cdx depending on cadmium amount, where (x = 0, 2.5, 5, 10, 15 mol%). Shielding parameters against gamma rays were also reported for the modified glass samples. A shot-range of amorphous nature was detected by the XRD analysis. The value of the density (ρ) increased linearly with CdO content, from 3.24 to 3.87 g/cm. On the other hand, an opposing behavior was observed for the molar volume (V) and crystalline volume, (V). FTIR spectra were carried out and confirmed the structure changing by replacing AlO by CdO. Optical absorption spectra show a valuable difference at both energy gap and Urbach energy by increasing the CdO content. Radiation shielding parameters such as MAC, LAC, HVL, MFP, and Zeff, were calculated using Phy-X/PSD. We found that the CdO/AlO replacement enhanced all the shielding parameters. The obtained results indicated that the increasing in CdO content modifying the structural properties and improves the shielding abilities of the studied samples. Therefore, the prepared glasses could be considered as promising as shielding materials.

Animal species are traditionally identified using biological methods, such as chromosome analysis. In this study, however, the identification of rabbit species (Oryctolagus cuniculus) was approached radiologically using two techniques: measurement of the mass attenuation coefficient (μ) of X-rays in rabbit teeth, and determination of elemental concentrations in the teeth of six different rabbit species using X-ray fluorescence (XRF). This study demonstrates the practical potential of using radiological properties to differentiate between rabbit species. Specifically, it evaluates the elemental composition and X-ray mass attenuation coefficients of tooth samples. XRF analysis revealed consistent concentrations of several essential elements across all six species such as Ca, P, K, Mg, S, Ar, Al, Si, Cl, Sr, Zn, Fe, Ti, Cr, Mn, and Cu. In contrast, elements like Au, Br, Pb, Fr, Sn, Sb, and Cd showed significant variation among species and exhibited strong discriminatory power in distinguishing them, particularly when measured in parts per million (ppm). This radiological method presents a novel alternative to traditional biological techniques for species identification, offering a non-destructive and potentially more accessible approach.

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.

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.

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.

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.

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.

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 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.

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 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.

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 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.

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.