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The activation of Lithium aluminum borate material with varying concentrations of transition metal of manganese was studied. The synthesis of the phosphor samples was achieved by employing the solid-state sintering technique. The study aimed to determine the structural property, optical property, and the effect of beta source (90Sr/90y) radiation on the thermoluminescence properties of the phosphor material. The analyzed structure of both doped and undoped samples was obtained to be from 52.17 to 67.13 nm as the crystallite size and 67.00–120.00 nm as the particle size respectively. The optical studies showed an increase in mole concentration of the doped samples resulted in an increase in absorbance and a decrease in the energy band gap from 4.45 to 4.00 eV. The thermoluminescence report measured showed that the Mn-doped sample on lithium aluminum borate has the most prominent peak at 78 °C (major peak) and 294 °C (minor peak) when exposed to radiation dose (90Sr/90y beta source) of 50 Gy. The acquired activation energy was resolved using some of the models which include the initial rise, deconvolution, and the heat rate techniques. The dose response was determined to be linear from the Mn-doped lithium aluminum borate. [Display omitted] • Manganese was used as a dopant on lithium aluminum borate. • An increase in the Mn2+ on Li 3 Al 3 (BO 3) 4 decreased the energy band gap. • Activation energy obtained using the kinetic parameter was found to be 0.54 ± 0.02. • Thermogravimetric analysis trend at higher temperatures shows break down of the chemicals. [ABSTRACT FROM AUTHOR]

The goal of this study is to compare the calibration factors obtained by the four calibration methods recommended by the standard ISO 8529-2. To do this, two Berthold LB6411 neutron monitors are calibrated applying the four methods using a 241Am-Be source and the calibration results are compared. Calibration factors obtained are coherent with each other considering their typical standard deviation and differ by less than 4% from each other. • Comparison of the standard calibration methods for neutron monitors. • Two different neutron monitors are calibrated. • Requirements of the standard ISO 8529-2 are met. [ABSTRACT FROM AUTHOR]

In this study, we investigated the radiation hardness of phosphate glasses doped with terbium (Tb) ions, having the composition 56 P 2 O 5 : 30 Na 2 CO 3 : 5 Al 2 O 3 : 8 Gd 2 O 3 : 1 Tb 4 O 7 , under proton and X-ray beam excitation. These glasses were synthesized using the melt and quench method. The dose distribution inside the volume of these samples was studied, and the absolute absorbed dose was calculated. The scintillation and optical properties, such as photoluminescence, transmission, absorption, etc., were studied and compared before and after exposure to irradiation. Under both types of irradiation, we observed two major emission peaks corresponding to the transitions 5 D 3 → 7 F 5 (at 480 – 510 nm, in the blue region) and 5 D 4 → 7 F 6 (at 535 – 565 nm, in the green region). The dominant green emission is attributed to the presence of Tb 3 + dopants. Notably, after X-ray irradiation, we observed a change in the sample's color, accompanied by a decrease in the intensity of all peaks. This suggests a potential limitation in the radiation hardness of Tb-doped phosphate glass. Similarly we checked the luminous intensity with 100 MeV proton beam. Furthermore, we conducted thermal annealing process to explore the possibility of radiation damage recovery and found out that sample does recover, its intensity recovered and its color change back to transparent from yellowish color. Our results highlight characteristics of Tb-doped phosphate glasses, which make them valuable for diverse applications such as radiation detection, dosimetry, radiography, biomedical imaging, and related fields. • Tb-doped phosphate glasses were prepared using the melt and quench method. • The sample was irradiated with X-rays and a 100 MeV proton beam. • At an absorbed dose of 90 Gy from X-rays, the sample changed to a yellowish color. • X-ray-damaged sample exhibited lower transmission compared to fresh sample. • Annealing restored X-ray-damaged sample to levels comparable with fresh samples. [ABSTRACT FROM AUTHOR]

Radiation grafting modification represents an eco-friendly approach to material alteration. In recent years, the application of electron beam radiation has seen substantial advancements due to its superior safety, controllability, and efficiency. Textiles, as vital human materials, are extensively employed in diverse sectors such as daily life, industrial production, medicine, and environmental protection. By undergoing physical and chemical modifications, textiles can gain additional functionalities and applications, thereby enhancing their effectiveness and broadening their usage scope. This paper offers a comparative analysis of the merits and drawbacks of plasma radiation, gamma radiation, and electron beam radiation for textile modification. It also provides an in-depth exploration of the impact of the electron beam radiation grafting modification method on textile fibers and fabric substrates. Additionally, this paper presents a comprehensive review of recent advancements in the application of electron beam radiation grafting methods in areas such as antibacterial textiles, flame retardant textiles, and hydrophilic/hydrophobic textiles. The current strengths, weaknesses, and development trends within this field are discussed, along with future prospects. • This study elucidates the impacts of electron beam radiation on textile materials and fibers. • Introduction to the principles of electron beam radiation grafting for textile modification. • Plasma, gamma and electron beam radiation modified textiles were compared. • Recent advances in the study of electron beam radiation graft-modified textiles are summarized. [ABSTRACT FROM AUTHOR]

In this work, we successfully prepared glasses with the composition 55 B 2 O 3 – (45-x) ZnO – x Na 2 O (x = 0, 5, 10, 15) using the traditional melt quenching procedure. We analyzed the influence of substituting ZnO with Na 2 O at different concentrations on the attenuation of ionizing radiation and the glass density. Different analytical tools, such as XRD, FTIR, and UV-VIS spectroscopy, were used to investigate the crystal structure and optical features of the produced samples. The partial replacement of ZnO by Na 2 O significantly reduces the density (from 3.36 to 2.87 g/cm3) and, in contrast, increases the molar volume of the glass (from 22.32 to 25.06 cm3/mol). The positions of the main peaks in the FTIR spectra remain relatively unchanged with increasing Na₂O content. The Fermi energy (E F) of the glasses increases from 3.16 to 3.45 eV with increasing Na 2 O concentration. Samples with higher Na 2 O exhibit a blue shift in the UV cutoff. The direct and indirect optical band gap energy values (E d /E in) increase from 3.42 to 3.62 eV and 2.87–3.23 eV, respectively, with increasing Na 2 O concentration. The radiation attenuation performance of these glass samples was examined through evaluation of various parameters like linear and mass attenuation coefficients (LAC/MAC), effective atomic number (Z eff), and half-value layer (HVL) and tenth-value layer (TVL) in the photon energy range of 10 keV–15 MeV. LAC and MAC values decrease with decreasing ZnO content. The two buildup factors, energy (EBF), and energy absorption (EABF) have been recorded for the different compositions at penetration depths up to 40 mean free paths. Samples with the highest ZnO concentration show the lowest HVL and TVL values at the lowest photon energy (≤2 MeV). Increasing Na 2 O concentration significantly increases both EBF and EABF, with their maxima occurring at 5 MeV. Increasing zinc oxide in the glass improves its radiation shielding ability, suggesting potential applications for zinc alkali borate glasses in radiation protection. • Glasses with varying compositions of B 2 O 3 , ZnO, and Na 2 O were prepared using the melt quenching. • The direct and indirect optical band gap energy values (E d /E in) increased. • LAC and MAC values decrease with decreasing ZnO content. • Increasing Na 2 O concentration significantly increases both EBF and EABF. [ABSTRACT FROM AUTHOR]

Radical intermediates derived from di-n-butyl N,N-diethylcarbamoylphosphonate (DBDECP), N,N-bis(2-ethylhexyl)butanamide (DEHBA), dioctyl phosphate (DOP), tributyl phosphate (TBP), N,N,N,N-tetraoctyl diglycolamide (TODGA), and octyl(phenyl)-N,N-diiso-butylcarbamoylmetliylphosphine oxide (CMPO), were examined by EPR spectroscopy at 77 K. In all cases, carbon-centered radicals originating from alkyl or amide compounds were consistently identified in the experimental spectra. The spectral assignment was based on the advanced quantum chemical calculation at the DFT(B3LYP)/L1a_3 level of theory allowing determination the approximate conformations of the radicals involved. The measured kinetics exhibit a linear accumulation of radicals up to an irradiation dose of 1 kGy. The relative yield of stabilized radicals in organic phosphates (TBP, DOP) is approximately three times higher than in amide (DEHBA) or carbamoyl phosphonate (DBDECP) samples. The proposed approach for estimating radiation stability can be expanded to other compounds or mixtures relevant to nuclear waste separation, as well as other substances of particular interest. • The radicals derived from DBDECP, DEHBA, DOP, TBP, and TODGA studied by EPR spectroscopy. • DFT calculations were used to confirm the spectral assignment of the resulting radicals. • The accumulation of radicals in DBDECP, DEHBA, DOP, and TBP is linear up to 1 kGy. • The radiation stability of phosphate ligands is higher than that of amide and phosphonate ligands. [ABSTRACT FROM AUTHOR]

Glass matrices of Li 2 B 4 O 7 doped with Dy3+, Yb3+ and Cu were synthesized by melt quenching technique using different concentration of copper nanoparticles. The study and analysis are centered in shielding radiation. The samples amorphous nature was corroborated by X-Ray diffraction (XRD) and nanoparticles size distribution was obtained by transmittance electron microscopy (TEM). Optical characterizations used were absorbance and photoluminescence emission (PL). Radiation shielding theoretical properties: mass attenuation coefficient (MAC), half value layer (HVL), tenth value layer (TVL), mean free path (MFP) and effective atomic number (Zeff) are obtained using Phy-X/PSD software and analyzed for future applications in radiation security. • Nanoparticles size distribution immersed in the samples is between 1 and 50 nm obtained with TEM analysis. • The refractive index of all samples was calculated, which makes them suitable to use in optoelectronics systems. • The Mass Attenuation Coefficient (MAC) value enhances when the copper dopant increases. • The samples show a good radiation shielding capacity. [ABSTRACT FROM AUTHOR]

The study of luminescence phenomena by crystal-based radiation detectors is suitable for radiation dosimetry, once the light emitted by them enables the quantification of their deposited radiation energy. The light emission can be promoted when a material is illuminated with a certain wavelength and time interval, as in the optically stimulated luminescence (OSL) and photo-transferred OSL (PTOSL) processes. The objective of this work is to evaluate the OSL and PTOSL responses of commercial dosimeters (LiF:Mg,Ti, CaF 2 :Dy, CaF 2 :Mn and CaSO 4 :Dy) in order to study their luminescence and the possibility of use in radiation dosimetry with the PTOSL technique. OSL and PTOSL responses of LiF:Mg,Ti, CaF 2 :Dy, CaF 2 :Mn and CaSO 4 :Dy dosimeters, commercially sold as TLD-100, TLD-200, TLD-400 e TLD-900, respectively, by Thermo Fischer Scientific, were studied. The samples were irradiated with the 90Sr+90Y source of the TL/OSL reader system Risø, and the measurements were taken using the same system and blue LEDs. For the PTOSL signal, the dosimeters were irradiated, thermally treated and illuminated with LEDs with wavelengths between 265 nm and 420 nm. The most intense OSL signal occurred for TLD-100. Comparing the OSL and PTOSL results, it is possible to observe clearly the photo-transferred effect for TLD-100. For TLD-200 and TLD-400, no effects were noted. In the case of TLD-900, it presented a PTOSL signal in a small-scale when analyzing the curve integral. • OSL and PTOSL responses of LiF:Mg,Ti, CaF 2 :Dy, CaF 2 :Mn and CaSO 4 :Dy were studied. • All materials were exposed during the experiments to the 90Sr+90Y radiation. • Dosimetric characteristics as reproducibility response and DMD were evaluated. • PTOSL signal was analyzed after irradiation, PITT and illumination with LEDs. • LiF:Mg,Ti presented noticeable and intense photo-transfer effect. [ABSTRACT FROM AUTHOR]

Metal oxyhalides are potential candidates for fundamental and technological interest in pharmaceutical, biological, optical, photoluminance, sensing, energy, and photocatalyst applications. In this study, using first-principles density functional quantum computational approach, we investigate the electronic and optical properties of two members of bismuth oxyhalides, BiOX (X = I, Br). The study is mainly aimed to characterize and examine the light radiation energy-dependent optical properties of the compounds by using mBJ desnty functional with the full potential linearized augmented plane wave method. The oxyhalides show indirect bandgap semiconductor nature having bandgaps of 2.2 eV for BiOI and 3.5 eV for BiOBr. Besides, these are p-type materials owing to a large hole-like carrier density of states in the valence bands close to the Fermi level. The energy bands show considerable dispersion of particles. The increasing reflectivity at high light energy shows the potential of the materials as good reflectors in shielding screens or glasses to avoid damage from the ultraviolet radiation. • First-principles quantum computational analysis on optoelectronic properties of BiOI and BiOBr via mBJ method. • We predict that BiOI & BiOBr are p-type semiconductors. • The calculated indirect band gap is 2.2 eV for BiOI and 3.5 eV for BiOBr. • Optical properties include dielectric function, reflectivity, refractive index, absorption, energy loss function. • Results may find basic & applied applications in medical, nuclear reactors, catalysts, lighting, and energy technology. [ABSTRACT FROM AUTHOR]

This research investigates the possibility to simultaneously measure 137Cs and 90Sr/90Y content in water by Liquid Scintillation Counter Quantulus 1220. The method relies on the Cherenkov counting and does not require sample pre-treatment. During nuclear emergencies, a potential radioactive release should be promptly detected, and this technique ensures measurement results 2 h after the sample's arrival to the laboratory. 137Cs and 90Sr/90Y concentrations were determined with and without 1-butyl-3-methylimidazolium salicylate ionic liquid's addition, which increased detection efficiency via wavelength-shifting mechanism. The results of analysis were obtained with relative deviations up to 70% from the true activities without IL's addition, but their accuracy was improved (with relative deviations up to 40%) after the addition of 1 g of ionic liquid to the counting vials. • Simultaneous 137Cs-90Sr/90Y screening in water via Cherenkov counting is presented. • Liquid Scintillation Counter Quantulus 1220 was used for the measurements. • 1-butyl-3-methylimidazolium salicylate ionic liquid was used as wavelength shifter. • 137Cs-90Sr/90Y activities are obtained within 2 h with maximal deviation of 70%. • In nuclear emergencies, this method promptly detects potential radioactive release. [ABSTRACT FROM AUTHOR]

Lead, the conventional choice for wearable radiation shielding, faces growing health and occupational concerns. This prompts the search for a lighter, more flexible alternative. Nylon 6, prized for its mechanical prowess, emerges as a reinforcement in wearable composites. This study focuses on creating silicon rubber composites using Nylon 6 reinforcement and varying proportions of Bismuth oxide and aluminium fillers. Mechanical Parameters such as Tensile strength and Elongation at break, are studied and the quality of fabrication is assessed using a Scanning Electron Microscope. Studies on various combinations of nylon 6-based silicon rubber with varying percentages of bismuth oxide and aluminium fillers have been studied and radiation parameters have been assessed. TSN-4 (60% wt. bismuth oxide along with 50% wt. aluminium powder) showed the highest tensile strength of 25.13 MPa having 79.3% of elongation at break followed by TSN-1 & TSN-3. The results reveal good mechanical properties as well as satisfactory radiation attenuation properties. The combination of Nylon 6-based with 60% wt. bismuth oxide along with 50% wt. aluminium powder (TSN4) was considered optimal for the energy range from 140 keV to 511 keV with HVL of 2.06 cm, TVL 6.86 cm, and MAC of 0.093 gm/cm2 and also bearing good mechanical properties. Further, the fabricated samples can be compared with the Monte Carlo Simulation method for further improvements in the fabricated composites. The produced composites have the potential to be used as lead-free protective wearables and wearing devices in nuclear medicine following further investigation. • Research focuses on novel nylon-based silicon rubber composites with fillers from 140Kev gamma to 511 Kev Positron range. • 60% Bismuth oxide and 50% Aluminium powder as filler, exhibits excellent mechanical and radiation attenuating properties. • Novel Nylon-6-based silicon rubber composites emerge as a Potential lead-free option for wearable radiation shielding. • Avenues for nanocomposites of bismuth and aluminum additives to enhance radiation shielding advancing technology. [ABSTRACT FROM AUTHOR]

In this study, we investigated the degradation of surfactant sodium dodecyl benzene sulfonate (SDBS) in aqueous solution using electron beam radiation. The removal efficiency of SDBS approached nearly 100%, achieving a COD removal rate of 7–20% with an absorbed dose of 5.0 kGy. Upon irradiation, several notable changes in SDBS micelles were observed. The absolute value of zeta potential and the average diameter size decreased. SEM observations revealed that the clustered aggregates of SDBS micelles fragmented into irregular filamentous pieces. Moreover, the interfacial tension increased remarkably and approached the level of pure water at 2.5 kGy for SDBS in a pure water solution and 5.0 kGy for SDBS in a brine water solution. The foaming power disappeared for SDBS in pure water and decreased to 20 mm for SDBS in brine water at 10 kGy. The defoaming rate of SDBS solution increased incrementally from an initial range of 1–2 mm/min to 3.0–5.6 mm/min at 5.0 kGy. In summary, when SDBS is decomposed, new system is created with new properties. Electron beam radiation offers a clean and sustainable approach to degrade SDBS in wastewater. • Degradation of surfactant DBS was performed by electron beam radiation technology. • Removal efficiency of DBS and COD reached nearly 100% and 7–20% at 5.0 kGy. • Interfacial tension increased markedly and reached level of pure water at 2.5–5.0 kGy. • Foaming power reduced and defoaming rate of DBS solution increased after radiation. • Clustered aggregates of DBS micelles fragmented into irregular chains at 5.0 kGy. [ABSTRACT FROM AUTHOR]

In an attempt to mitigate the increasing number of waste Cathod Ray Tube (CRT) glass in the environment, provide a safe, cheaper, and environmentally attractive recycling route for the glasses, and provide an alternative material for gamma radiation absorption applications, this study investigated the influence of adding Na 2 CO 3 on the density, and gamma photon-absorbing prowess of CRT glass. Using the powder metallurgy process, CRT-NCx glasses consisting of CRT glass powder mixed with two distinct weight concentrations (20% (CRT-NC20 and 40% (CRT-NC40)) of Na 2 CO 3 powder were prepared. The mass attenuation coefficients (μ ρ) of the prepared glasses were obtained using FLUKA simulations for 15 keV–15 MeV photons. The density of CRT, CRT-NC20, and CRT-NC40 were 3.117 g/cm3, 2.987 g/cm3, and 2.894 g/cm3, respectively. The range of μ ρ for CRT, CRT-NC20, and CRT-NC40 corresponded to 0.0326–45.5236 cm2/g, 0.030–35.0662 cm2/g, and 0.0278–26.9813 cm2/g, respectively. The half-value layer and mean free path was found to vary within the range 0.005–6.822 cm and 0.007–9.842 cm for CRT; 0.007–7.748 cm and 0.010–11.178 cm for CRT-NC20; and 0.009–8.633 cm and 0.013–12.455 cm for CRT-NC40. The minimum and maximum values of μ e n ρ were 0.0216 and 37.7566 cm2/g for CRT, 0.0202 and 29.1167 cm2/g for CRT-NC20, and 0.01921 and 22.4430 cm2/g for CRT-NC40. CRT-rich glass showed higher radiation absorbed doses for the same beam energy and glass thickness. Na 2 CO 3 -rich glasses had lower buildup factors BFs, hence preferable in broad beam transmission scenarios. The investigated CRT-NCx glasses are more attractive for radiation protection functions in contrast to some well-known radiation shielding materials considering their lower mean free paths. The present glass system provides and alternative and effective gamma radiation shield, and also proffers a way of upcycling waste CRT glasses. • Radiation protection of recycled CRT/Na 2 CO 3 composites. • Experimental work is carried out. • Monte Carlo simulations are employed. • Na 2 CO 3 -rich glasses had lower buildup factors. • The studied system has a potential use in nuclear and medical applications. [ABSTRACT FROM AUTHOR]

The presented work demonstrates the placement of new 60Co gamma sources at the irradiation complex situated within the Institute of Radiation Problems, Ministry of Science and Education of the Republic of Azerbaijan. Additionally, it highlights the preparation of the source's radioactivity power table using novel dosimetry methods. The gamma irradiation complex consists of the Gamma Facility for Radiation Research Cobalt-25, Gamma Facility Radiation Chemical Continuous Action-20000 (GFRCCA-20000), and Modern Radiation Chemical Facility Gamma-25 (MRCFG-25). The calculations are mainly based on the accurate calculation of the dose power and the dose absorbed by the material in the modernized "Modern Radiation Chemical Facility Gamma-25" facility. Monte Carlo N-Particle code (MCNP) calculations give the distribution kinetics of the photon quantity on the surface of the material depending on the energy of the gamma source. • Research work on a complex of new Co60 gamma sources. • The activity and the dose rate reduced to 4001 Ci, 142.3280 Rad/sec, respectively. • Device exhibited a daily decay of 0.05 Rad/sec, decay factor of 0.999715, and activity decay of 1.5 Ci. [ABSTRACT FROM AUTHOR]

Interpolation techniques such as Piecewise Cubic Hermite Interpolating Polynomials (PCHIP) and Cubic Splines (CS) were used to estimate the mass attenuation coefficient values (MAC) and the effective atomic number values (Z eff) of borosilicate glasses doped with PbO and BaO. The mathematical models were used to obtain a function between the parameters and the energy of the incoming photons, to provide a better understanding of the glass system. The glasses had a composition of 10Na 2 O–15PbO-(65-x)B 2 O 3 –10SiO 2 -xBaO, where x = 5, 10, 15, 20, and 25 mol%. The derived values were compared against theoretical data obtained from Phy-X, to determine the accuracy of the mathematical models. The results demonstrate that both the CS and PCHIP methods are useful tools that can accurately be used to determine the MAC and Z eff values of the investigated samples. For instance, at certain energies such as 0.103 MeV, the relative difference between the MAC values obtained through PCHIP and through Phy-X is as low as 0.07, demonstrating the effectiveness of the PCHIP model at these energies. The same is true for the Z eff values, where the same relative difference at 0.384 MeV is as low as 0.0002. Therefore, both the mathematical models demonstrate an effective ability at interpolating the MAC and Z eff values of the investigated glass system. • PCHIP and Cubic Splines (CS) were used to estimate the MAC for borosilicate glasses. • CS and PCHIP methods are in good agreement with Phy-X data. • CS and PCHIP can be used as well to derive the Z eff for the glasses. • At 0.103 MeV, the MAC values obtained using PCHIP and Phy-X differ by 0.07. • At 0.384 MeV, the Z eff values obtained using PCHIP and Phy-X differ by 0.0002. [ABSTRACT FROM AUTHOR]

Glasses with neutron shielding properties are extremely important for nuclear industries. Neutron interactions with ten different neutron shielding glass types were simulated by using GEANT4 Monte Carlo simulation toolkit. Simulation results were evaluated in terms of shielding performances, deposited energy properties and produced secondary radiation. Important evaluations were made in view of radiation safety, especially on secondary particles and radioactivity resulting from interactions between neutrons and glass samples. All simulated glass samples were found to emit risky secondary particles and radioactive nuclei after interacting with fast neutrons. • Secondary radiation emissions were studied for neutron shielding glasses. • GEANT4 Monte Carlo simulation code was used to estimate secondaries. • Produced particles and radioactive nuclides, after interactions, were reported. • It was suggested that secondary risk should be taken into account in shield design. [ABSTRACT FROM AUTHOR]

This study investigates the nuclear radiation attenuation characteristics of bioactive glasses with the system (26-x)Na 2 O-xBaO-29CaO–45P 2 O 5 , where x represents the molar percentage of BaO (0, 5, 10, 15). For this purpose, several parameters of shielding gamma radiation, such as the mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), effective atomic number (Z eff), effective electron density (N eff), atomic cross-section (ACS), electronic cross-section (ECS), equivalent atomic number (Z eq), and transmission factor (TF) were calculated. The calculations were performed across different photon energy ranges (0.015–15 MeV) using Phy-X/PSD software and validated using the WinXCOM program. The results obtained from both the software platforms exhibited a high degree of agreement. Among the investigated glasses, the BNCP-15 glass, which had the highest BaO concentration, demonstrated the highest values for MAC, LAC, Z eff , N eff , ACS, ECS, and Z eq , while displaying the minimum values for HVL, TVL, MFP, and TF. For example, the LAC values at 15 MeV were found to be 0.056, 0.063, 0.070, and 0.077/cm for BNCP-0, BNCP-5, BNCP-10, and BNCP-15, respectively. Consequently, the BNCP-15 glass exhibited superior radiation attenuation performance in comparison to the other BNCP glasses examined in this study. • Four bioactive glasses (Na 2 O–BaO–CaO–P 2 O 5) are investigated for radiation attenuation purposes. • Phy-X/PSD and WinXCOM program are employed for shielding parameters. • Significant influence of BaO content on radiation attenuation characteristics is observed. • High-BaO bioactive glasses are recommended for diverse radiation attenuation uses. [ABSTRACT FROM AUTHOR]

In the present research paper, we present the gamma shielding characterization and the optical properties of a tellurite glass system chemically defined as 64TeO 2 –15Na 2 O–5BaO-xBi 2 O 3 -(15-x)WO 3 –1Yb 2 O 3. The study also focused on the evolution of gamma attenuation and optical parameters as the chemical definition of the glass system changed. The optical constants estimated and analyzed include the molar refractivity (R m) , molar polarizability (α m o l ), reflectance loss, optical transmission, metallization criterion, static dielectric constant, and optical dielectric constant. The values of the mass attenuation coefficient (μ ρ) other basic shielding quantities were also calculated and analyzed in order to reveal the relative shielding effectiveness of the glasses and their potential for radiation safety applications. For TNY-W/Bi1, TNY-W/Bi2, and TNY-W/Bi3, having Bi 2 O 3 molar concentrations of 0, 5, and 10 mol%, respectively, the density was 5.42 g/cm3, 5.56 g/cm3, and 5.67 g/cm3, while the molar volume had values of 29.119 cm3/mol, 30.491 cm3/mol, and 31.964 cm3/mol, respectively. The R m and α m o l increased from 17.72 to 19.68 cm3/mole and 7.03 × 10−24 cm3 to 7.81 × 10−24 cm3, respectively. All other estimated optical parameters vary according to glass composition and the refractive index. The values of μ ρ fluctuated between 0.0344 and 56.4869 cm2/g for TNY-W/Bi1, 0.0351 and 59.3506 cm2/g for TNY-W/Bi2, and 0.0368 and 61.8444 cm2/g for TNY-W/Bi3. For a glass thickness of 10 mm and at 15 keV, the absorbed dose rates in TNY-W/Bi1, TNY-W/Bi2, and TNY-W/Bi3 were 50 μR/h, 52 μR/h, and 53 μR/h, respectively. The increase in Bi 2 O 3 content improved the photon and energy absorption capacities of the TNY-W/BiX glasses. The replacement of WO 3 with Bi 2 O 3 in the glass system increased photon buildup factors in the glasses as well. The present glasses showed better photon absorption capacities than light and heavy concrete, standard shielding glasses, alloys, and rock samples. • Gamma attenuation of TeO 2 /Bi2O 3 /WO 3 glass system is reported. • Radiation shielding performance is estimated. • Monte Carlo simulations are employed. • A good agreement between the theory and the simulation. • TNY-W/Bi3 system has a potential use in nuclear and medical applications. [ABSTRACT FROM AUTHOR]

In order to protect the health of radiation workers, scientific management of radiation workplace protection is implemented, and occupational health risks of radiation workplaces in Gansu Province, China are identified and evaluated through monitoring. The basic situation of occupational health management of radiological workers in 1366 radiological diagnosis and treatment institutions was investigated, and 596 monitoring hospitals were selected for occupational health monitoring. Using a 2-IN∗2-in NaI (Tl) scintillation spectrometer and its supporting software, internal thyroid irradiation monitoring was performed. Fifty-one underground workers in a deep mine iron mine were selected to monitor the effect of high radon exposure. 11 (6%) monitored hospital interventional radiology staff detected lead outside the aprons between 5 mSv and 20 mSv during a single monitoring period; In nuclear medicine, radiation monitoring in the thyroid detected 3(15%) people with doses between 5 mSv and 20msv.The chromosome aberration rate and Detection rate of posterior pole subcapsular opacification of interventional radiation group and nuclear medicine group was higher than that of conventional radiation group, and the difference between interventional radiation group and conventional medicine group was statistically significant. Abnormal detection of tumor markers in serum after sustained radon exposure accounted for 39.2% of NSE(neuron-specific enolase), 22.5% of SCC(squamous cell carcinoma associated antigen), and 5.9% of CyFRA21-1(cytokeratin 19 fragment), respectively, chest low-dose CT showed plaque and stripe shadow in 21 cases (41.2%) and nodules in 16 cases (31.4%). Individual dose monitoring found that radiation workers engaged in interventional radiology were exposed to higher doses and had higher occupational risks. The results of occupational health examination show that there is a certain degree of radiation injury in interventional radiology and nuclear medicine workers. Nuclear medicine radiation monitoring results show that some workplaces have radioactive contamination. The radon exposure of deep mine miners has a higher occupational risk of lung cancer caused by high radon.The analysis of chromosome aberration is an important index of occupational health monitoring of radiation workers. • Dic + r can be used as a sensitive index of radiation injury in low-dose radiation workers. • A simple method for monitoring internal thyroid irradiation. • There is a certain degree of radiation injury in interventional radiology and nuclear medicine workers. • The radon exposure of deep mine miners has a higher occupational risk of lung cancer caused by high radon. • There is radioactive contamination in some workplaces of the nuclear medicine department. [ABSTRACT FROM AUTHOR]

The results of the implementation and study of the radiation characteristics of high-energy electron (e-), gamma (γ-), and neutron (n-) radiation fields of the M-30 microtron with a maximum energy of 18.5 MeV are presented. Dosimetric characteristics were studied using the method of thermally stimulated luminescence (TSL) and using samples TLD-100H (LiF: Mg,Cu,P) and TLD-500K (Al 2 O 3 :C). Three e-, γ-, and n-experiments were performed at the same M-30 electron flux; the dosimetric indicators Y γ,n;e = D γ,n /D e , where D γ,n is the intensity of the dosimetric peaks of TSL after γ- or n-irradiation, and D e is, respectively, e-irradiation. We discuss the relative stability of these dosimeters' Y γ,e parameters at gamma irradiations and the presence of a partial correlation of Y n,e values in neutron fields. The latter is associated with the peculiarity of radiation defect formation in the material of dosimeters when interacting with nuclear particles of different types. The research results confirm the general ideas about the physics of electron radiation conversion into beams of nuclear particles of different natures. The data obtained are important in developing methods for dosimetric support of radiation technologies that use beams of mixed high-energy nuclear radiation, particularly for radiation therapy. • Only e-, γ-, and n-radiation fields (18.5 MeV) were created on the M-30 microtron. • Standard TLD 100H (LiF: Mg,Cu,P) and TLD 500K (Al 2 O 3 :C) dosimeters were used. • New dosimetric indicators Y γ,n;e of e-, γ-, n-fields of irradiation were proposed. • Dosimetry of neutron fields with TLD 100H samples requires additional calibration. • The results are important for the tasks of modern radiation therapy. [ABSTRACT FROM AUTHOR]

Application of radiation with highly energetic electrons and ions can be an alternative method to modify structures of crystalline materials. This radiation can potentially induce phase transformations while preserving some physical characteristics and morphology of the materials, hence impacting their useful properties. Here, we report the impacts of e-beam and gamma radiation on the structures and electrochemical performance of SiO 2 /C anodes for Li-ion batteries (LIB) obtained from rice husk ash (RHA). The effects of radiation sources on structural and physical properties are investigated using X-ray diffraction (XRD), Fourier transform infrared spectroscopy (FTIR), X-ray fluorescence spectrometry (XRF), electron microscopy, and Raman spectroscopy. After irradiation-induced processes using e-beam and gamma radiation at 1000 kGy, the mean diameters of the SiO 2 particles were around 30 ± 10 and 27 ± 10 nm, respectively, while retaining their round-shaped particle morphology. Both radiation sources induce formation of disordered carbon structure as indicated by the higher I D /I G Raman peaks ratios than the pristine sample. Electrochemical properties were studied using half-coin type cells. The modified structure of SiO 2 /C anodes caused by irradiation showed improved electrochemical performance, compared with pristine material. • Gamma and electron beam radiation were used to modify structures of SiO 2 /C composite anodes for Li-ion batteries. • Irradiations alter the SiO 2 structure by stretching and changing the angle of the Si–O–Si bond. • Irradiations alter the carbon structure by generating surface defects. • Crystallinity and particle size of SiO 2 /C remained unalter after energetic electrons and ions irradiations. • The modified SiO 2 /C composite anodes for Li-ion batteries demonstrated enhanced electrochemical performance. [ABSTRACT FROM AUTHOR]

Characterizing radiation measurement systems, such as diagnostic radiology systems for RQR and RQA, is essential for ensuring reliable results in standardized instrument calibration laboratories. Quality control of dosimetry devices, such as patient dose calibrators (PDCs), a reference meter, is crucial for ensuring accurate measurements. This study demonstrates the use of spectrometry and ionization chambers to characterize a set of semi-automated 3D prototyping filter holder systems, developed in a previously project, designed for applications such as Kerma-Area Product (KAP) meter calibration. The set of 3D prototypes were adjusted to a filter wheel and characterized using an X-ray spectrometer, followed by an ionization chamber, according to international standards. The characterization of radiation qualities from 50 to 150 kV in diagnostic radiology was performed using the substitution method: first with an ionization chamber, then with a PDC. The PDC was calibrated for KAP and Air Kerma quantities, considering the conditions of the X-ray system and factors such as temperature, humidity, and pressure. Spectrometric analysis and the use of an ionization chamber were effective in determining these parameters. Spectral characterization allowed for accurate measurements to establish proper quality control, then it is possible to use the PDC calibrated for calibration procedures for KAP meters. Future studies intend to compare these results with computational simulations using the TOPAS Monte Carlo code to validate the calibration method. • Dosimetry in diagnostic radiology is crucial to ensure the accuracy standards. • The PDC calibration method is conducted using spectrometry and ionization chambers. • Spectral characterization ensures precise measurements for good quality control. • The calibrated system is used for PDCs in KAP meter calibration procedures. [ABSTRACT FROM AUTHOR]

This study investigates the mechanical as well as shielding properties of 70P 2 O 3 –5Al 2 O 3 -(25-x)Na 2 O-xPbO, while using advanced MCNPX simulations code and Phy-X software. Advanced MCNPX coding simulation and online Phy-X software are used to compare the properties of three aluminum lead phosphate glasses named S1, S2 and S3 with PbO concentrations 0, 10, and 20 mol%, respectively. Various shielding parameters were calculated in the photon energy ranging from 0 to 15 MeV. These parameters include mass attenuation coefficient, effective atomic number, half-value layer, tenth-value layer, mean free path and linear attenuation coefficient. Our comparative analysis of the results from MCNPX and Phy-X in the case of mass attenuation coefficient indicates a high level of agreement, differing by less than 2% from each other. The half-value layer for S3 was found at 0.003 cm, 1.709 cm, and 5.984 cm at energies of 0.01 MeV, 0.5 MeV, and 15 MeV, respectively, while for S1 these values were found at 0.010 cm, 3.35 cm, and 13.96 cm in the same energy spectra. The results show that S3, with 20% PbO, is more likely to attenuate the gamma and X-ray photons; due to their minimum values of tenth value layer, half value layer, mean free path, and greater mass attenuation coefficient, effective atomic number as compared to S1 (undoped) and S2 (10% doped with PbO). The mass attenuation coefficient for S3 was found between 67.95 cm2/g to 0.030 cm2/g, while for undoped S1, these values varied between 27.64 cm2/g to 0.021 cm2/g in the energy range of 0–15 MeV. Furthermore, the Makishima-Mackenzie model is utilized to evaluate the mechanical behavior of our glass samples, influenced by factors such as energy of dissociation and packing density related to components of oxide. The mechanical features encompass various moduli, Poisson's coefficient and microhardness. The introduction of PbO in glass samples S2 and S3 increased all these properties, excluding Poisson's coefficient which decreases with the addition of PbO. Our findings provide valuable insights into the shielding and mechanical parameters of these glasses, suggesting probable applications in fields such as optics and nuclear physics. • The MCNPX simulations code and Phy-X program gave the same result. • The Shielding properties of the studied samples improved with the increasing PbO content. • The increasing PbO content resulted in enhanced mechanical properties of the investigated glass systems. [ABSTRACT FROM AUTHOR]

To calibrate thermal neutron detectors, State Key Laboratory of NBC Protection for Civilian plans to establish thermal neutron reference radiation field (TNRRF) based on the existing 7.4 × 1011 Bq 241Am-Be source. An 82 cm (L) × 50 cm (W) × 50 cm (H) moderator was designed through Monte Carlo simulation to thermalize fast neutrons. Each component was determined to optimize thermal neutron fluence rate φ , proportion of thermal neutrons ρ , and uniformity factor μ of the radiation field. A 3He proportional counter was used to evaluate the fabricated moderator. Results show that surrounding reflector is the main origin of thermal neutrons. D 2 O tank can promote ρ and its length can be utilized to adjust φ. Homogenizing lens will improve μ and reduce φ. Experimental φ , cadmium ratio η , and μ at the reference position are 1808.82 ± 85.96 cm−2 s−1, 315.80, and 5.29 %, respectively, which are consistent with simulated results. Next, TNRRF will be established after long-term stability testing. • A compact moderator was designed to establish thermal neutron reference radiation field. • Thermal neutron fluence rate can be adjusted through the length of D 2 O tank. • The Homogenizing lens can remarkably improve the field's uniformity. • Experimental thermal neutron fluence rate and uniformity are 1808.82 ± 85.96 cm−2 s−1 and 5.29%, respectively. [ABSTRACT FROM AUTHOR]

The present study investigated the effects of gamma-ray, electron beam, and X-ray radiation on polymers in EVA/EVOH/EVA multilayer films. Spectroscopic methods, including FTIR and UV–Vis, were employed in conjunction with chemometric treatments such as PCA, SIMPLISMA treatments, and PLS models. The feasibility of dose prediction on multilayer film, given a known dose, is attainable across various irradiation technologies. Both gamma ray and X-ray exhibit comparable effects on the multilayer film, and it is feasible to anticipate the dose released on the film by utilizing UV–Vis spectra or infrared spectra for gamma ray or X-ray of a predetermined dose. • First time achieving dose modelling using spectrophotometric data. • First time achieving dose modelling using infrared data. • Comparison of gamma, e-beam and X-ray radiation technologies impact on multilayers films. [ABSTRACT FROM AUTHOR]

The radiation sensitivities of Aspergillus niger in several energy X-rays and gamma rays were investigated. Experiment and simulation were conducted to evaluate the X-ray energy spectra and depth dose distributions. The result showed that the microbicidal effectiveness of Aspergillus niger could depend only on the dose regardless of photon energy. It should be noted that the depth dose of low-energy X-rays, including characteristic X-rays of tungsten (L Ⅲab -ray and L α -ray of 8.4 keV and 10.2 keV, respectively) is variable even at 1 mm. • Radiation sensitivity of Aspergillus niger in several energy X-rays and gamma rays. • X-ray energy spectra and depth dose distributions of low-energy X-rays. • Dose contribution of characteristic X-rays of tungsten (L Ⅲab -ray and L α -ray of 8.4 keV and 10.2 keV, respectively). [ABSTRACT FROM AUTHOR]

indent Nanoparticles (NPs) of calcium ferrite doped with Zinc in the range of 10–50 mol % were successfully synthesized using solution combustion method. Neem leaves extract played a crucial role as a reducing agent in the synthesis process, followed by calcination at 500 °C. The comprehensive characterization of these nanoparticles confirmed the formation of orthorhombic calcium ferrite, and distinct Bragg reflections were observed due to Zinc doping. Notably, the nanoparticles displayed irregular shapes and varying sizes, along with the presence of pores and voids within their morphology. The optical energy band gap, determined using Wood and Tauc's relation, fell within the range of 2.85 to 2.96 eV. Interestingly, as the zinc substitution increased, the energy band gap increased while the crystallite size decreased. The evaluation of radiation protection capacity included an in-depth examination of shielding parameters, encompassing the mass attenuation coefficient and its derivatives like mean free path, half-value layer, and effective atomic number. Additionally, variations in the energy-absorbing buildup factor across different energy regions were thoroughly investigated. The research also explored neutron shielding and bremsstrahlung radiation parameters, taking into account the zinc concentration in calcium ferrite nanoparticles. This aspect is particularly crucial in the field of radiation dosimetry, emphasizing the importance of understanding how these nanoparticles, with varying zinc concentrations, influence radiation absorption and dosimetric outcomes. • Zinc doping boosts radiation shielding of calcium ferrite nanoparticles. • Green extract approach used for eco-friendly nanoparticle synthesis. • Promising potential for reducing radiation exposure in various applications. • Zinc incorporation influences the structural properties positively. • Findings support the development of optimized radiation-shielding materials. [ABSTRACT FROM AUTHOR]

In this study, albedo parameters are experimentally measured to determine radiation scattering features of some thermoluminescent dosimetry materials (TLD 100, TLD 100h, TLD 200 and TLD 400). In experimental setup, it was used scattering angle of 168°, 59.54 keV gamma rays and HPGe detector. The effective atomic numbers of the investigated materials were determined from the coherent to Compton scattering intensity ratio. Also, the mass attenuation coefficient, the mass energy absorption coefficient and kerma relative to air and ICRU tissue were calculated for the TLD materials. It was observed that TLD 100h is the best tissue equivalent material among other TLD materials and best reflects 59.54 keV gamma rays. • The effective atomic numbers of some thermoluminescent dosimetry materials were obtained from scattering ratios. • The effective atomic number and albedo parameters are obtained for 59.54 keV photon energy. • TLD 100h is the material that best reflects 59.54 keV gamma rays. [ABSTRACT FROM AUTHOR]

Since polyallyl diglycol carbonate (PADC), viz. CR-39 has been widely used for radiation detection and measurement in various complex radiation fields, therefore, a systematic study has been carried out in this work to demonstrate the significant effect of linear energy transfer (LET) of heavy ions on the optical, structural and chemical (etching) properties of the detector. The PADC samples were exposed to heavy ions (7Li, 12C, 16O and 19F) of different energies to study the effect of LET from 76 to 1002 keV/μm. Samples were chemically processed to develop the latent tracks induced by heavy ions. Image analysis showed an increase in the damaged track size with the LET as well as the etching time. Having same energy, the track sizes of two different ions were found to be different because of the differences in their LET values. Similarly, for one particular ion, the track sizes were found to be smaller for higher energy due to low LET than that of the lower energy corresponding to high LET. Hence, this criterion is successfully demonstrated for particle identification by using PADC. Furthermore, spectrophotometric studies (UV–vis, FTIR) have been carried out to determine the changes in opacity, Urbach's energy, optical bandgap, molecular vibrations and red shift of the cut off wavelength with the increase in LET values. • High LET radiation effect on physico-chemical properties of PADC polymer has been investigated. • The bulk etch rate determined through gravimetric method was found to increase with the LET of ions. • The optical band gap decreased whereas opacity and Urbach's energy increased with the increase in the LET of ions. • The FTIR investigation showed the rate of loss of C–O–C bond with respect to the LET was the highest. [ABSTRACT FROM AUTHOR]

The metal-oxide semiconductor-based structures are among the most prominent optoelectronic devices that can be used in several application fields. The performance of these structures is strongly dependent on the local radiation dose. In this study, we examined the sample structures with and without radiation. The electrical parameters of the studied samples such as ideality factor, series resistance, saturation current, barrier height, and zero-bias barrier height were obtained by performing the forward bias I–V data analyses. The values of n indicate that the irradiation emission mechanism is dominated. Also, this value depends on the evaluation method of the device. According to the Cheung method, while the ideality factor was found to be 5.72 before irradiation, it was found to be 7.04 after irradiation with 30 kGy. According to the TE method, on the other hand, the value of the ideality factor was found to be 6.337 before irradiation while it was found to be 5.016 after irradiation. The high figures of n were considered to be the result of the interface states of the metal/oxide/semiconductor, i.e. the device, and the barrier height's image force lowering. The obtained dielectric parameters do not have to be absolutely correct, especially when there is radiation on the device. It was found that the value of Rs extremely depended on the particular current transport mechanism's contributions to the total current. The non-ideality factor n increases with the 30 kGy irradiation according to the Cheung method while it does not according to the TE theory. At the same time, the forward bias I–V characteristics and their logarithmic plots reveal two distinct linear sections in the entire linearly increasing voltage. • The gamma-ray irradiation affects the electrical properties of metal oxide-semiconductors. • In the Au/SnO 2 /n-Si structure, the values of n , φ b , R s , and I strongly depend on radiation. • The behavior of n according to the Cheung method is completely different from the results of the TE theory method. • Both of the series resistances calculated by using the Cheung and TE theory increase with the 30 kGy irradiation. [ABSTRACT FROM AUTHOR]

• Tissues and QA devices activation is studied under clinical conditions. • Effective dose received from activation by staff are far from exceeding dose limits. • Albeit 92 μSv/h were measured in contact with patients, no restrictions are needed. [ABSTRACT FROM AUTHOR]

Sulfonamide and quinolone antibiotics are widely used worldwide for disease prevention and treatment, which are ubiquitous in aquatic environments, soil, and animal waste because they are difficult to be removed in conventional wastewater treatment processes. Antibiotic residues in the environment can lead to the development of bacterial resistance, posing a potential hazard to humans and ecosystems. Ionizing radiation (γ-ray and high-energy electron beam), as an emerging advanced oxidation technology, has received increasing attention in antibiotics' treatment because of its reliable, safe operation and excellent degradation capability. This paper mainly summarized and analyzed the recent advances in the radiation-induced degradation of sulfonamide and quinolone antibiotics in aqueous solution, focusing on the influencing factors (such as absorbed dose, initial concentration of antibiotics, pH, inorganic anions and water matrices) and degradation pathways, which could provide references for the optimization of experimental conditions and mechanism studies on the treatment of these two types of antibiotics in actual wastewater and further practical application by ionizing irradiation. • Sulfonamide and quinolone antibiotics are ubiquitous in the environments. • Radiation-induced degradation of sulfonamide and quinolone antibiotics was reviewed. • The influencing factors and pathways of antibiotics degradation were discussed. • Radiation technology is effective for the degradation of antibiotics in aqueous solution. [ABSTRACT FROM AUTHOR]

The attenuation capability of tellurite glasses with composition of (100-x)TeO 2 –5La 2 O 3 -xWO 3 where x = 10, 15, 20, and 25% was analyzed. Radiation attenuation parameters such as mass, linear attenuation coefficients (MAC, LAC) and effective atomic number were determined at various energies. The S4 glass sample, which contains the highest WO 3 content and smallest TeO 2 concentration, has the greatest MAC at all energies. The glasses with the highest densities also have the highest LAC values, with greater WO 3 content leading to greater density in the glass system. The half value layer (HVL) values of the samples are positively proportional with the energy of the incoming radiation, greatest at the highest tested energy. The ratio between the tenth value layer (TVL) values for S1 and S4 are greater than one at all energies, which means that S1's TVL, the glass with the smallest WO 3 content, is higher than S4's TVL. The mean free path values were shown to have an inverse trend with the WO 3 content in the samples. The S4 sample, the glass with the highest WO 3 content and lowest TeO 2 content, has the greatest Z eff at all energies. • We reported the attenuation factors for TeO 2 –La 2 O 3 -WO 3 glass systems. • The S4 glass sample, which contains the highest WO 3 content has the greatest MAC. • The HVL values of the samples are positively proportional with the energy. [ABSTRACT FROM AUTHOR]

Monitoring the level of radioactive contamination and the type of radiation in the environment is very important for the protection of facilities, employees, and people. Phoswich detector is one of the useful tools to identify different radiations and separate them from each other using different scintillating crystals. However, their design can be very diverse based on the type of particles analyzed and various parameters of scintillating crystals and needs optimization to have maximum efficiency. This work aims to optimize the scintillating crystal layers for the design of the three-layer alpha-beta-gamma phoswich detector based on Monte Carlo radiation transport calculations. The selection of the appropriate model for the type and thickness of each layer is based on the optimization of parameters such as energy accumulation, produced scintillation optical photons, attenuation of optical photons, and scintillation decay time. The results showed that the three scintillating layers of ZnS(Ag), CaF 2 (Eu), and LYSO(Ce) with optimal thicknesses of 25.01 μm, 3.50 mm, and 2.54 cm, respectively, have more suitable optical outputs for detecting common alpha-beta-gamma radionuclide emitters. • Different scintillating crystals were investigated for various radiations. • Modeling of three-layer scintillating crystal layers was carried out. • An optimal configuration for a phoswich detecting alpha-beta-gamma was obtained. • Monte Carlo calculation was used to investigate phoswich parameters. [ABSTRACT FROM AUTHOR]

In this paper, the synthesis and gamma-radiation shielding attributes of xMgO-(30-x)BaO-69.5B 2 O 3 -0.5Fe 2 O 3 glasses are reported. The aim is to ascertain the optimum chemical structure of the glass system for gamma radiation shielding applications and dosimetry. The simple melt and quench method was adopted for the synthesis of the xMgO-(30-x)BaO-69.5B 2 O 3 -0.5Fe 2 O 3 glasses, where for x = 0, 5, 10, 12, and 15 mol% represented MBBFe-0, MBBFe-1, MBBFe-2, MBBFe-3, and MBBFe-4, respectively. The mass attenuation coefficients μ / ρ of the glasses were evaluated using the XCOM and FLUKA simulations for the photon energy range of 15 keV–15 MeV. The differences between the values of μ / ρ evaluated with FLUKA and XCOM were within 0.96%. The mass attenuation coefficients of MBBFe-0, MBBFe-1, MBBFe-2, MBBFe-3, and MBBFe-4 ranged from 0.0288 to 28.6205 cm2/g, 0.0279–25.6462 cm2/g, 0.0268–22.2712 cm2/g, 0.0260–20.4073 cm2/g and 0.0251–18.4086 cm2/g, respectively. The corresponding values of the half-value layer at 15 MeV are 7.06 cm, 7.64 cm, 8.25 cm, 8.70 cm, and 9.53 cm for MBBFe-0, MBBFe-1, MBBFe-2, MBBFe-3, and MBBFe-4, respectively. The specific gamma constant values of MBBFe-X glasses are in the range 11.289–264.417 Rm2/Cihr, 10.871–236.716 Rm2/Cihr, 10.386–205.282 Rm2/Cihr, 9.931–187.921 Rm2/Cihr and 9.444–175.515 Rm2/Cihr for MBBFe-0, MBBFe-1, MBBFe-2, MBBFe-3, and MBBFe-4, respectively. The substitution of BaO with MgO therefore, depreciated the gamma shielding efficacy, photon energy absorption abilities, and interaction per unit mass of the MBBFe-X glasses. This study concludes that MBBFe-0 is the best gamma absorber among the studied glasses and has the potential to be a good gamma-radiation shield with an efficiency that supersedes many traditional and modern shielding materials such as concrete, metal alloys, polymers, rocks, commercial glass shields, and other shielding glasses. • New glassy system are reported for radiation uses. • Gamma shielding performance is studied for the new system. • Monte Carlo simulations are carried out. • A good agreement between the theory and the simulation. • MBBFe-X has a potential use in shielding applications. [ABSTRACT FROM AUTHOR]

In this work, novel efficient epoxy resin based shielding materials enhanced with BN powder against nuclear radiation was proposed. The composites were prepared by using epoxy resin E51, polyamide resin 651 and BN powder. Neutron shielding performance was analyzed by using Evaluated Nuclear Data File, partial density method and a moderated 241Am–Be neutron source. In addition, gamma ray shielding performance and mechanical property were tested by a137Cs gamma ray source and an electronic universal testing machine, respectively. The results indicate that the addition of BN powder could improve the shielding performance for thermal neutron, fast neutron and gamma ray. Neutron shielding performance of prepared composite materials is nearly the same with the variation of densities. Nuclear shielding performance is better than commercial shields (SWX-213, SWX-201 and SWX-261). And the bending strength is greater than 12.78 MPa. In addition, shielding attenuation mechanism for neutron at 10−5–2 × 108 eV is mainly contributed by elastic scattering attenuation interaction produced by H and C from epoxy resin matrix, and absorption attenuation interaction produced by B from BN powder at 10−5–102 eV. • Novel efficient neutron shielding composites were prepared by BN and epoxy resin. • A new perspective of shielding performance analysis was proposed. • Shielding mechanism for neutron shielding was revealed in the paper. • Shielding ability of the prepared composites were better than commercial shields. • Bending strength of the prepared composite materials was greater than 12.78 MPa. [ABSTRACT FROM AUTHOR]

Seven bioactive glasses in the system (50-x) B 2 O 3 –4P 2 O 5 –26CaO–20Na 2 O-xZnO: (x = 0–15 mol%) have been produced using melt quenching route. The prepared samples coded as BG1-BG7. The physical properties, average optical basicity, electronegativity, electronic polarizability, and radiation attenuation competence of the BG1-BG7 glasses have been examined. Non-crystalline state of samples confirmed via the XRD measurements. Density increased from 2.6274 g/cm3 to 2.9406 g/cm3 for BG1 to BG7 samples. The average optical basicity (˄ t h ) changed from 0.748 to 0.838, electronic polarizability, (α 0 − 2 ) enhanced from 1.812 to 2.008, while electronegativity, (χ a v ) reduced from 2.352 to 2.245 as ZnO increased from 0 to 15 mol%. The BG1 sample possessed the lowest values of both mass (MAC) –linear (LAC) -attenuation coefficients, while BG7 possessed the highest values. The sample contains higher ratio of ZnO (BG7) possessed the lowest values of half-value layer (HVL) and mean free path (MFP) among all BG-samples. Also, the HVL and MFP of all BG-samples were less than that of ordinary concrete (OC). The proposed bioactive samples can apply for several of medical applications. • B 2 O 3 –P 2 O 5 –CaO–Na 2 O–ZnO bioactive glasses have been synthesized. • Density was increased from 2.6271 to 2.9406 g/cm3. • Optical basicity, electronegativity, and electronic polarizability have been investigated. • Suggested glasses can be applied for several applications. [ABSTRACT FROM AUTHOR]

The physical, structural, mechanical, and radiation (gamma photon and neutron) shielding properties of CRT screen glass and Bi 2 O 3 mixtures are presented in this study with the aim of adopting them as cheap, transparent, and environmentally safe glass shields for radiation protection purposes. Bi 2 O 3 -doped CRT screen glass samples are prepared by the ball milling and cold press methods and coded as TVS, TVS-Bi10, and TVS-Bi20, representing glass-ceramics containing 0, 10, and 20 wt% of Bi 2 O 3 , respectively. Vickers hardness values are 493, 534, and 564 HV for TVS, TVS-Bi10, and TVS-Bi20, respectively. Also, the values of densities are measured and recorded as 2.61, 2.78, and 3.06 g/cm3 for the TVS, TVS-Bi10, and TVS-Bi20. The values of the mass attenuation coefficients computed using FLUKA simulations and XCOM agree within an error margin of 1%. The values of the estimated photon shielding parameters show that shielding efficiency follows the order TVS < TVS-Bi10 < TVS-Bi20. In addition, the introduction of Bi 2 O 3 has a positive impact to increase the ability of TVS to moderate fast neutrons The total cross-section for thermal neutrons in TVS, TVS-Bi10, and TVS-Bi20 is 1.1294, 1.1198, and 1.1932 cm-1, respectively. The best photon, fast, and thermal neutron absorber is TVS-Bi20 among the TVS-BiX glass-ceramics. The TVS-Bi20 sample can function better than some commercially available glass shields, light and heavy concrete, and other categories of composite materials such as glasses, rocks, and polymers. The TVS-Bi20 is thus recommended as an eco-friendly and efficient radiation shielding material. • Bi 2 O 3 doping powders are synthesised from CRT-screen waste glass. • Radiation shielding properties are studied. • Physical and structure features are investigated. • Nuclear security performance is estimated. • TVS-Bi20 is recommended as an eco-friendly and efficient shielding material. [ABSTRACT FROM AUTHOR]

High energetic gamma rays are used in different fields and thus it may cause high risks for public if it is absorbed over limited dose. In order to be protected from these hazardous effect of radiation, the shielding is an effective ways and this requires shielding materials. For this purpose the gamma radiation shielding parameters for four different types glasses which was formulated as (25-x)CaF 2 -xAl 2 O 3 –15Bi 2 O 3 –59B 2 O 3 –CuO (x = 3,6,9,12 mol%) have been investigated. For this purpose, the linear absorption coefficients (LAC, μ) were calculated using Phy-X/PSD within the gamma ray energy range of 10−3-105 MeV. From using the equivalent atomic number (Z eq) and Geometric progression (G–P) method, the exposure buildup factor (EBF) and energy absorption buildup factor (EABF) values were evaluated at 0.015 MeV–15 MeV gamma rays. The values of EBF and EABF were calculated for 1, 5, 10, 20, 30, and 40 cm mean free path (mfp). • The gamma radiation shielding parameters for four different types glasses have been obtained. • The samples were formulated as (25-x)CaF 2 -xAl 2 O 3 –15Bi 2 O 3 –59B 2 O 3 –CuO (x = 3,6,9,12 mol%). • The linear absorption coefficients (LAC, μ) were calculated using Phy-X/PSD within the photon energy range 10−3-105 MeV. • The exposure buildup factor (EBF) and energy absorption buildup factor (EABF) values were evaluated at 0.015 MeV–15 MeV. [ABSTRACT FROM AUTHOR]

In this journal, a paper discussing reviewing progress in radiation technology was published twenty years ago. The paper has been cited over 100 times. Nowadays written review paper is following the structure adopted in the mentioned first publication. It is a critical appraisal of the progress in the engineering of radiation sources, processing systems, technology application for sterilization, food irradiation, material modifications, and synthesis, and environmental pollution control. The achievements and difficulties in the development of this technical and research discipline, important for industry and science, were analyzed. The analysis and observed trends are an indication of the suggested future activities to be carried out in the R&D and industrial sectors and may be useful for scientists and professionals in their work. • Radiation processing continues to advance in several sectors of the global economy. • Development of radiation sources and radiation technologies is discussed. • Future activities to be carried out in the R&D and industrial sectors are predicted. [ABSTRACT FROM AUTHOR]

MC-based computerized TPS is an essential tool for improving treatment quality in external radiation therapy chains. However, incorporating these systems into clinical TPS is challenging due to their long computation time. To address this problem, Phase Spaces (PhSp) can be utilized, which reduce the computation time of such simulations while maintaining accuracy levels comparable to full simulations. Since PhSps can only generate a finite number of particles, recycling the same PhSp several times during a simulation will increase statistical uncertainty. To carry out this disadvantage, the present study employs a numerical reconstruction model to develop a novel generation of MC Fast Dose Engine (MC-FDE) that relies on the Cyberknife linac parameters publicly available in the IAEA database. The MC-FDE model's performance is evaluated based on the precision of the reconstructed parameters and the accuracy of dose calculation in the 3D BEAMSCAN water phantom and patient CT datasets. In contrast to the recently published Wasserstein Generative Adversarial Networks (WGAN), the MC-FDE reconstruction model produces significant agreement with measured data, IAEA PhSp files and TPS Accuray, as determined by marginal distributions, correlation metrics, 2-3D gamma indexes and the Dose Volume Histogram (DVH) test. Regarding calculation speed, MC-FDE has a very fast process and can generate an infinite number of particles, unlike the limited number of particles recorded in IAEA PhSp files. According to the findings of this study, the proposed MC-FDE model is considered suitable for use as part of clinical TPS. • TPS based on MC are essential for improving treatment quality in external radiotherapy chains. • A numerical model 'MC-Fast Dose Engine' was created using publicly available Cyberknife linac data. • The MC-FDE model is assessed for precision in reconstructed parameters and 2D–3D dose accuracy. • The MC-FDE reconstruction model shows substantial agreement with measured data, IAEA, and Accuray TPS. • Based on findings, the proposed MC-FDE model is considered suitable for use as part of clinical TPS. [ABSTRACT FROM AUTHOR]

In this study, poly(3-acrylaminophenylboronic acid) modified graphene oxide (GO-PAAPBA) has been prepared by polymerization of 3-acrylaminophenylboronic acid (AAPBA) on the surface of GO. The –O · free radical was formed by γ-ray radiation, which initiated the polymerization of AAPBA. Fourier transform infrared spectroscopy, X-ray photoelectron spectroscopy and Raman spectroscopy were employed to characterize the structure of GO-PAAPBA. The grafting density of poly(3-acrylaminophenylboronic acid) is increased with increasing of the absorbed dose. The GO-PAAPBA was added into vinyl-terminated polydimethylsiloxane (Vi-PDMS) to prepare room temperature cured silicon rubber composites (SR/GO-PAAPBA). The GO-PAAPBA exhibits better dispersion performance than pure GO, which is contribute to improve thermal conductivity and mechanical properties. Significantly, with grafting density of PAAPBA increasing, the comprehensive performances of SR/GO-PAAPBA are more remarkable. SR/GO-PAAPBA-1.88 with outstanding thermal and mechanical abilities exhibits beat neutron shielding property. The neutron transmission of SR/GO-PAAPBA-1.88 is 10% lower than that of SR. The SR nanocomposite with efficient thermal conductivity and neutron shielding ability has a promising prospect to be applied as advanced flexible shielding material. • Boronic acid with vinyl group was polymerized on GO by γ-ray radiation. • GO-PAAPBA was blended with Vi-PDMS to prepare SR/GO-PAAPBA at room temperature. • SR/GO-PAAPBA-1.88 exhibited outstanding beat neutron shielding property. [ABSTRACT FROM AUTHOR]

Establishment of first gamma radiation facility for sterilization of medical products under auspices of UNDP by the Department of Atomic Energy (DAE) in the year 1974 gave a big boost to radiation related applied research activities in India. Today radiation related research is not confined to DAE units but it is being carried out in many universities and other institutes of India. A very positive outcome of this has been that, many industries are adopting radiation technologies. Presently 18 electron beams and 24 gamma processing plants are commercially operating in India. Radiation applications are being explored for radiolysis based advanced oxidation processes (AOPs) for treatment of waste water and treatment of dry sewage sludge, synthesis of grafted membranes for separation and energy storage purpose, synthesis of high recovery shape memory polymers, synthesis of chemi-resistive, electromechanical and peizo-resistive sensors and other applications. The article briefly describes various activities being presently being pursued or have been completed in recent past. Efforts have been put to guesstimate the direction of the near future activities in-view of the present activities. • Radiation-based research initiated in India as early as 1940's. • Setting-up of medical sterilization plant and 7 MeV LINAC were watershed moments. • BARC, universities and institutes now involved in the research in radiation field. • Indian industry has come-ahead to setup gamma and EB facilities. [ABSTRACT FROM AUTHOR]

In this work, pulverized grape seeds were irradiated with varying doses of 60Co gamma radiation, and the effect of radiation for each dosage value was determined using Electron Spin Resonance (ESR) spectroscopy and microbiological analysis. Through dose-response and kinetic investigations, the dose dependence and stability of the radiation induced cellulose-like radicals were determined, respectively. The effect of irradiation on aerobic bacteria was demonstrated for the first time by microbiological analysis and the inactivating dose value was identified. The obtained findings are beneficial for irradiated food detection investigations. • Radiation produced cellulose-like radicals whose structure was proposed as ·C–CH 2. • The radical was linearly radiosensitive and enough stable for detection. • Radiation was found effective for inactivation of the bacterial load in grapes. • ESR was used for directly examining the radicals formed by irradiation. [ABSTRACT FROM AUTHOR]

In this research, the synthesis, optical parameters, and radiation absorption quantities of 50TeO 2 –15Na 2 O—(20-x)PbO—15ZnO—xEu 2 O 3 glasses were reported. The glasses were prepared by the well-known melting and quenching method using high purity chemicals. The glasses were coded as TPEu-0, TPEu-1, TPEu-2, and TPEu-3 for glasses containing 0, 1, 2, and 3 mol% of Eu 2 O 3 , respectively. The density of the glasses was determined by the Archimedes method. The optical parameters of the glasses, such as the refractive index n , molar refractivity R m , molar polarizability α m , reflection loss R L , optical transmission T, metallization criterion M, static dielectric constant εstatic, and optical dielectric constant εoptical were estimated by theoretical methods. The stopping powers and range of electrons, protons, α-particles, and carbon ions in the TPEu-X glasses for particle kinetic energies between 15 keV and 15 MeV were computed using the ESTAR, PSTAR, ASTAR, and STRIM software. In addition, the fast neutron (FN) removal cross section (FNRCS), thermal neutron (TN), and total cross-section (σ t o t) for the prepared glasses were evaluated theoretically using established models. The estimated optical parameters showed strong relationship with the chemical content of the glasses. Glass density and molar volume increased as Eu 2 O 3 content increased. The R m , α m , R L , εstatic, and εoptical vary from 16.24 to 17.20 cm3/mol, 6.44 × 10−24 cm3‒17.20 × 10−24 cm3, 0.17–0.19, 5.71–6.55, and 4.71–5.55 respectively, with TPEu-0 and TPEu-1 having the maximum and minimum values, respectively. Generally, the increase in Eu 2 O 3 concentration increased the charged radiation shielding ability of the glasses. The increment in the Eu 2 O 3 content of the glasses brought about an improvement in the thermal and fast neutron absorption probabilities of the glasses. • Radiation shielding capacity of tellurite glassy composites is estimated. • Optical properties are experimentally evaluated. • A good agreement between the theory and the simulation. • TPEu-3 glass system has a potential use in nuclear applications. [ABSTRACT FROM AUTHOR]

We theoretically explore the physics of even and odd harmonics generation and radiation in undulators of single pass free electron lasers (FELs). Planar undulators are studied as a most common design. The results are obtained analytically and some of them also numerically. In the analytical form the contributions of various factors to the harmonic generation are distinguished and their effect is analyzed. The results are verified with numerical simulations and compared with reported experimental data; the data for best documented FELs in terms of harmonic generation, LEUTL and LCLS, is analyzed. The reasons for even harmonic generation are identified; we show that they differ for the spontaneous undulator radiation and for the stimulated FEL radiation. Comparative analysis is performed with various theoretical models for the FEL harmonic powers. The advantages and possibilities of amplification and radiation the second FEL harmonic in the LCLS-II FEL with variable deflection parameter is demonstrated for the harmonic lasing self-seed (HLSS) FEL design. The possibility to suppress the radiated second harmonic in a FEL by a guiding field of a weak second harmonic of the main undulator field with negative phase is shown. This can be used to reduce the reflected signal of the second harmonic generation (SHG) when the nonlinear harmonic response of the mater is investigated. • Analytical tool for estimation of radiated FEL harmonic powers is given. • The physics of the even harmonics in X-ray and other FELs is revealed. • Regulation of the second FEL harmonic by weak second undulator field harmonic is proposed. • Theoretical calculations validated with LCLS FEL data. • Second harmonic amplification at LCLS-II is considered. [ABSTRACT FROM AUTHOR]

This paper introduces a practical study to evaluate and analyze the effectiveness of radiation detection systems used to measure the equivalent dose of the workers involved in Gemstones (Topaz) colour treatment process at Egypt Second Research Reactor (ETRR-2). Typically, thermoluminescence dosimeters (TLDs) are used to record the accumulated radiation dose equivalent to the periodic assessment of the health and safety of reactor workers. The accuracy of using TLDs has been evaluated in the International Atomic Energy Agency's Radiological Dosimetry Laboratory as they can be used in various nuclear environments such as nuclear reactors. This paper proposes the use of a gas-filled radiation detector, a Geiger-Muller (GM) tube, to assess the intervention of workers in handling Topaz irradiation boxes and preparing them for regular irradiation at the reactor. A comparison was made between the TLDs and the GM tube detectors and the difference in their readings and their dependence on the radiation dose rate were assessed. The difference in sub-linearity phenomena of both detectors and its effect on the GM tube values and the effect on the operator's performance to complete the filling and preparing Topaz boxes for irradiation were investigated. The difference in recording dose for both the TLD and the GM tube was taken into account based on the equation shown. • Evaluate the equivalent dose of the ETRR-2 reactor workers involved in Topaz irradiation process. • Comparison between TLDs and GM tube detector. • Calculation of the ratio between the TLD reading and the GM tube. • This practical study can be used as a reference to optimize the workers intervention in Topaz color treatment in RRs. • The effect of sub-linearity in both detectors on the ratio to estimate the performance of GM. [ABSTRACT FROM AUTHOR]

Using fully relativistic multiconfiguration Dirac-Fock (MCDF) wavefunctions in the active space approximation, the energy levels, lifetimes, radiative rates, and oscillator strengths are determined for transitions in Mn-like W L ion. For the calculations, Breit interaction (BI) and quantum electrodynamics (QED) corrections to the levels are estimated in extensive relativistic configuration interaction (RCI) procedure, and results are reported for all electric dipole (E1), electric quadrupole (E2), magnetic dipole (M1), and magnetic quadrupole (M2) transitions among the lowest 121 levels, belonging to the 3 s 2 3 p 6 3 d 7 , 3 s 2 3 p 5 3 d 8 , 3s3 p 6 3 d 8 , 3 s 2 3 p 4 3 d 9 , and 3s3 p 5 3 d 9 configurations. Comparisons are made with similar data obtained with FAC (Flexible Atomic Code) to assess the accuracy of the results. The present results are also assessed by comparison with the data compiled by the Atomic Spectra Database (ASD) of National Institute of Standards and Technology (NIST) and other existing theoretical/experimental ones for few levels in literature showing an overall good agreement. i.e., the energies agree within 0.5% with the experimental results, and the M1 transition rates agree within 5% with other theoretical results. Beside the ground configuration, almost all atomic parameters presented in this work are calculated for the first time and thus significantly increases the amount of accurate data for W L ion. Our results should be beneficial in future for identification of spectral lines, in plasma modelling, and in fusion plasma research. [ABSTRACT FROM AUTHOR]

Radiation stability of methoxypillar[5]arene (1) and n-butoxypillar[5]arene (2) was studied by an electron accelerator with dose up to 14 MGy in air at room temperature. The radiolysis products and the possible radiolytic mechanism were also proposed. The structures of both irradiated and unirradiated pillar[5]arenes samples were comparatively characterized by Micro-FTIR NMR, UV-vis, MALDI-TOF-MS and HPLC measurement. The results showed that the skeleton of the pillar[5]arenes was stable to a great extent when the dose was lower than 100 kGy, indicating excellent radiation stability of alkylated pillar[5]arenes. When the dose was more than 300 kGy, all compounds showed different degrees of radiation damage, leading to the radiolysis products via breakage of appending arms and the bond between α-carbon and β-carbon of appending arms of pillar[5]arenes. With increasing the dose, the degree of radiation damage from electron beam irradiation to pillar[5]arenes skeleton experienced a gradual rise. As the dose reached 2000 kGy, the compounds 1 and 2 decomposed by 21% and 33%, respectively, as a result of radiolytic degradation. Furthermore, the side chain length of alkyl groups will also significantly affect the irradiation stability of pillar[5]arenes, particularly at the dose beyond 2000 kGy. These results provide reliable data support for the radiation stability of alkylated pillar[5]arenes in a wide range of irradiation dose. • Radiation stability of methoxypillar[5]arene and butoxypillar[5]arene is explored. • The skeleton of the two pillar[5]arenes is stable at the dose lower than 100 kGy. • Longer chains promote marke radiolytic degradation compared to shorter ones. • Possible radiolytic pathway involving phenolic, quinone and methoxy group species is proposed. [ABSTRACT FROM AUTHOR]