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This research examines the effects of varying titanium oxide (TiO 2) concentrations in glass formulations, denoted as [(53-x)B 2 O 3 –7MgO–20BaF 2 –20Na 2 O-xTiO 2 ] or BMBNTix, where x varies from 0 to 8 mol% in 2 % increments, on optical properties and radiation shielding effectiveness. Using MCNP5 (MC) Monte Carlo simulations and Phy-X software, this study assesses a range of photon energies from 0.015 to 15 MeV, focusing on key radiation shielding metrics such as the linear attenuation coefficient (μ), the half-value layer (HVL), and the tenth value layer (TVL). The results reveal a clear relationship between increased TiO 2 levels in the BMBNTix glasses and improved radiation shielding performance. Notably, the linear attenuation coefficient (μ) steadily climbs from BMBNTi0 to BMBNTi8, highlighting the beneficial effect of a TiO 2 addition to the material's ability to attenuate radiation. This trend is inversely mirrored in HVL values, which decrease from 0.010 cm for BMBNTi0 to 7.646 cm for BMBNTi8, reflecting enhanced shielding efficiency over the entire studied photon energy range. The effective atomic number (Z eff) also showcases a dynamic range from 40.793 to 15.101, suggesting a complex relationship between TiO 2 content and photon interaction. Moreover, the study indicates a slight but consistent increase in the fast neutron removal cross-section (Σ R) from 0.104 cm−1 for BMBNTi0 to 0.106 cm−1 for BMBNTi8, pointing to improved neutron shielding with greater Ti and oxygen content in the glass. These insights highlight the potential of TiO 2 -enriched magnesium borate glasses as superior options for effective photon and neutron shielding, particularly in nuclear medicine, emphasizing their role in enhancing radiation safety measures. [ABSTRACT FROM AUTHOR]

As the utilization of nuclear energy continues to expand, there is a growing focus on the development of lightweight and efficient nuclear shielding composites. In this paper, novel WB X /Al (x = 1, 2, 4) composites were designed based on shielding performance. The effects of reinforcement type, volume fraction, and material thickness on the 60Co and 137Cs γ-rays, fast and thermal neutron shielding performances were simulated. The results show that WB/Al composites offer better development potential compared to WB 2 /Al or WB 4 /Al composites. Additionally, a predictive model for the γ-ray shielding effectiveness of WB/Al composites, based on the areal density of tungsten, was proposed. The fabrication process involved mechanical ball milling and spark plasma sintering to fabricate 30 vol% WB/Al composites, with optimization of ball milling time, sintering temperature, and holding time. As a result, a novel nuclear radiation protection composite with uniform composition, a relative density of 97 %, and flexural strength of 527 MPa was acquired. [ABSTRACT FROM AUTHOR]

NASA HRP considers developing radiation protection for human space flight and surface habitation as one of the critical technologies for successful deep space exploration. Although the danger of radiation exposure is recognized as a potential show-stopper for deep space exploration, and radiation effects on humans are now understood better than before, shielding strategies for different stages of space flight and habitation are still not addressed in a fully comprehensive manner. Habitats and all space structures planning and design are guided by essential requirements and constraints associated with safety, manufacturing and assembly procedures, propellant and construction costs, maintenance, crew and/or passenger satisfaction. This paper reviews radiation shielding options for space habitats and discusses their feasibility in relation to habitability needs, including the potential for outside viewing in distinct types of space habitats. Typically, radiation protection depends on the thickness of the exterior structure that consists of a pressurized shell, multilayer insulation (MLI) and any applied radiation shielding material. The mass of the external protection shell is the primary factor of radiation shielding effectiveness. Nevertheless, using materials with low atomic numbers (e.g., Boron (5), Carbon (6), and H 2 O) helps to lower secondary radiation hazards. Water, which is rich in hydrogen and has the lowest atomic number, can also be used for other mission needs. Other materials, including biomaterials, can be considered when their inclusion in the structure is possible and appropriate. The paper presents a comprehensive strategy for radiation shielding selection that includes investigation of complications associated with a type of space habitat structure, mission needs, duration, destination, and crew requirements. The approach presented in the paper aims to establish an evaluation methodology for defining the feasibility of the integration of diverse radiation shielding types into habitat structures. The paper summarizes by reviewing radiation shielding proposals with selected case studies including water, regolith, hydrogen-rich polymers, biotechnology, polyethylene/boron nitride composites, and active strategies. • Case studies of different materials and methods used for radiation shielding purposes, • Pros and cons of using referenced materials and methods in habitat architectures • Criteria for evaluation and selection of appropriate radiation protection strategy • Comparisons of radiation shielding methods by space architecture categories • Comparisons of radiation shielding methods by structural integration options [ABSTRACT FROM AUTHOR]

This study evaluated the efficacy of a novel comprehensive shield designed to minimize radiation exposure (RE) to Physicians performing coronary and structural heart procedures. The Protego™ radiation shielding system (Image Diagnostics Inc., Fitchburg, Ma) is designed to provide comprehensive protection from RE and has been State certified sufficient to allow operators to perform procedures without orthopedically burdensome lead aprons. This single center two-group cohort study assessed the efficacy of this shield in a large number of cardiac procedures (coronary and structural), comparing operator RE compared to standard protection methods (personal lead apparel and "drop down" shield). The Protego™ system reduced operator RE by 99 % compared to Standard Protection. RE was significantly lower at both "Head" level by thyroid median dose 0.0 (0.0, 0,0) vs 5.7 (2.9, 8.2) μSv (p < 0.001), as well as waist dose 0.0 (0.0, 0.0) vs 10.0 (5.0, 16.6) μSv (p < 0.001). "Zero" Total RE was documented by Raysafe™ in 64 % (n = 32) of TAVR cases and 73.2 % (n = 183) of the coronary cases utilizing Protego™. In contrast, standard protection did not achieve "Zero" exposure in a single case. These dramatic differences in RE were achieved despite higher fluoroscopy times in the Protego™ arm (11.9 ± 8.6 vs 14.3 ± 12.5 min, p = 0.015). Per case procedural exposure measured by Dose Area Product was higher in the Protego™ group compared to standard protection (115.4 ± 139.2 vs 74.9 ± 69.3, p < 0.001). The Protego™ shield provides total body RE protection for operators performing both coronary and structural heart procedures. This shield allows procedural performance without the need for personal lead aprons and has potential to reduce catheterization laboratory occupational health hazards. • The catheterization laboratory predisposes to occupational health hazards. • Lead apron use underlies the prevalence of orthopedic maladies in interventionists. • Until recently, there have been few advances in catheterization laboratory protection technology. • Novel comprehensive shielding systems have been validated in early studies to provide excellent radiation protection. • Recent system refinements offer potentially even greater degrees of protection when compared to standard protection. [ABSTRACT FROM AUTHOR]

Background Purpose Methods Results Conclusion Historically, [131I]I has been a common isotope in radionuclide therapy, with [177Lu]Lu‐labelled radiopharmaceuticals now seeing a surge in use. These can include no‐carrier‐added or carrier‐added [177Lu]Lu with slight impurities of [177mLu]Lu with a significantly longer half‐life than [131I]I. Wastewater from therapy wards can contain a mixture of these radioisotopes. In some countries, national regulations require wastewater to be stored in dedicated systems before it is discharged into the public sewage system. To fulfill legal requirements, the nuclide specific activity concentration must be verified.We evaluate a method for determining the activity concentration of [177mLu]Lu /[177Lu]Lu at equilibrium and [131I]I in pure and mixed samples in order to prove that the determined values are reliably below the limits for release.We analysed the emitted energy spectrum of 1 L samples with a wastewater counter using an energy window‐based approach by evaluating measurements from two different time points.Based on the law of decay and the time and energy‐dependent measured values, equation systems were set up to calculate the count rates for [131I]I and [177mLu]Lu, which were converted into activity concentration using calibration factors.There is strong linear correlation between the nominal and determined activity concentrations (correlation coefficients R = 0.99; coefficient of determinations R2 = 0.99). We underestimate the actual activity concentration by a median of −1.4% for [177mLu]Lu and overestimate the activity concentration for [131I]I by a median of 7.1%.We show that an undercut of the clearance levels for material release is measurable. We analyse and determine activity concentrations of mixed samples consisting of [131I]I and [177mLu]Lu/[177Lu]Lu in equilibrium. The method is simple to implement using a conventional wastewater counter, however with a slightly increased effort, as two samples and measurements are required. The methodology can be adapted for the analysis of other nuclide mixtures. [ABSTRACT FROM AUTHOR]

The scarcity of research on the shielding properties of spinel ferrites underscores the necessity for more rigorous investigations. Consequently, this study introduces a facile synthesis method for Co, Cu, and Sm spinel nanoferrites (referred to as CCS nanoferrites) using the citrate combustion technique. The investigation focuses on their mechanical, dielectric, and gamma-ray shielding parameters. Gamma-ray shielding features are obtained theoretically via the Phy-X database. The particle size, nature, and distribution of the present CCS nanoferrites were analyzed using HR-TEM microscopy. HR-TEM results reveal both the spherical shapes and the aggregation of nanoparticles. These observations can be attributed to the interplay of high surface energy and magnetic interactions among the components of the CCS nanoferrites. The Co 0.5 Cu 0.5 Sm 0.15 Fe 1.85 O 4 nanoferrite exhibits an optimal dielectric constant value of 4587, with an enhanced ratio of 1618% compared to the pristine CCS0 sample. Additionally, it demonstrates an optimal conductivity of 38.59 μ (Ω·m)−1, with an enhanced ratio of 1105%. Furthermore, the loss is reduced to 2.65, showing an improvement ratio of 54% compared to the pristine nanoferrite at room temperature and 50 Hz. Moreover, the longitudinal modulus, shear modulus, Young's modulus, and bulk modulus of the nanoferrite Co 0.5 Cu 0.5 Sm 0.15 Fe 1.85 O 4 were increased from 1.79 to 4.96 GPa, 0.32–0.93 GPa, 0.88–2.56 GPa, and 1.37–3.73 GPa, respectively, when compared to the pristine sample. The comparative study of half-value layers at 0.662 MeV revealed that CCS nanoferrites exhibit smaller half-value layers than common radiation shielding materials. Additionally, the study highlighted the enhanced radiation shielding performance of the nanoferrites. Concerning the dielectric, mechanical, and ionizing radiation shielding properties of the CCS spinel nanoferrites, the CCS5 (with the highest Sm content) has the optimum ionizing radiation shielding ability with the highest dielectric and mechanical parameters compared to the other samples. The implications of these findings extend to potential applications in biomedicine, radiation protection, and the optimization of electronic devices operating in radiation fields. [ABSTRACT FROM AUTHOR]

Fluoroscopy-guided gastrointestinal procedures, including gastrointestinal stenting, balloon-assisted endoscopy (BAE), endoscopic retrograde cholangiopancreatography (ERCP), and endoscopic ultrasound (EUS), are essential for diagnosis and treatment in gastroenterology. Such procedures involve radiation exposure that necessitates strict safety measures to protect patients, doctors, and medical staff. The April 2020 update to Japan's Ionizing Radiation Injury Prevention Regulations for occupational exposure reduced the lens exposure dose limit to approximately one-seventh of its previous level. This change highlights the need for improved safety protocols. Without adaptation, the sustainability of fluoroscopy-based endoscopic techniques could be at risk due to the potential to exceed these new limits. This review examines the current state of medical radiation exposure in the field of gastroenterology in Japan and discusses the findings of the REX-GI study. [ABSTRACT FROM AUTHOR]

The measurements of radon concentrations in drinking water sources in and around the Main Central Thrust (MCT) region in Garhwal Himalaya, India, were carried out using the scintillation detector-based SMART RnDuo technique for radiation protection purposes. Radon values in the analyzed samples were observed between 1.1 and 183.9 Bq L−1 (AM = 19.7 Bq L−1). Radon values in 94% of the samples were found well below the World Health Organization (WHO) reference limit. The estimated radiation doses for different age groups were found higher than the WHO safe limit of 100 µSv y−1 (from all sources including radon) except for the age groups of 0–12 months infants and 1–3 years children. The results of this study may be useful for future studies on epidemiology, examining hidden faults, uranium exploration etc. [ABSTRACT FROM AUTHOR]

This study proposing an environmentally friendly and lead (Pb)-free alternative in the form of electrospun mats of Bi2O3/WO3/PVA for X-ray shielding. By varying Bi2O3 filler loading (0–20 wt%) while keeping WO3 filler constant at 10 wt%, the study examined density, thickness, and mass attenuation coefficient (µ) of the fabricated mats. X-ray attenuation was evaluated across different X-ray energy levels (16.61–25.27 keV) using X-ray fluorescence (XRF) unit. Meanwhile, the surface morphology and nanoparticle dispersion within the PVA nanofiber mat were observed through Field Emission Scanning Electron Microscope (FESEM). Results demonstrated improved X-ray attenuation with increased Bi2O3 filler loadings, except for mats containing 20 wt% Bi2O3 and 10 wt% WO3 (mat B5) due to coagulation and porosity issues. The electrospun mat with 15 wt% Bi2O3 and 10 wt% WO3 (mat B4) exhibited the highest X-ray attenuation. Thus, electrospun mat B4 is proposed as a promising candidate for environmentally friendly X-ray shielding material. [ABSTRACT FROM AUTHOR]

A high‐Z metal‐quercetin complex‐based material is developed by combining Hf, Ta, and Eu with quercetin (Qu) from a flavonoid series to apply to radiation protection materials. To demonstrate radiation energy absorbance, we utilize a polymer blend composed of carboxymethyl cellulose (CMC) and polyvinylpyrrolidone (PVP) as a matrix. This eco‐friendly film can be easily prepared by simply mixing it with the M‐Qu complex and the CMC‐PVP polymer blend. The possibility of radiation energy absorbance by the M‐Qu complex is confirmed through an analysis of the X‐ray energy absorption dose change rate. In addition, the radiation resistance characteristics of each film sample are measured using high‐energy electron‐beam irradiation. The results show that the Ta‐containing Qu complex has a high capability for UV energy downshift, X‐ray radiation absorption, and stability against electron‐beam radiation. This indicates that the material in question has the potential to serve as a superior radiation protection material for broad‐spectrum radiation energy. Also, it could effectively offer remarkable stability making it a compelling option for radiation‐resistant applications. [ABSTRACT FROM AUTHOR]

Introduction: To minimise the risks associated with ionising radiation, it is necessary for all staff involved to employ specific techniques to reduce radiation exposure of the patient. These techniques include using compression during examinations of the pelvic region and lumbar spine, using a gonad shield, and asking women if they are pregnant. However, some staff do not use these techniques consistently. Increasing compliance requires determining why staff are non‐compliant. Thus, this study aims to qualitatively investigate why radiographers do not use these techniques. Methods: This qualitative study is based on a cross‐sectional electronic survey with open‐ended questions. The data were analysed using an inductive qualitative content analysis with quantification of the findings. In total, 111 radiographers from 20 hospitals in Sweden participated. Results: Three categories appear related to barriers that could obstruct the radiographer from using compression, gonad shields and asking about pregnancy: patient characteristics, interaction between the patient and the radiographer and issues related to the situation and examination. Conclusions: The barriers to not using radiation protection measures varied depending on the specific measure. However, the barriers were mainly related to the patient experiencing pain, communication difficulties and cultural reasons. In addition, the lack of adequate and user‐friendly equipment was seen as a barrier to applying compression and using gonad shielding. [ABSTRACT FROM AUTHOR]

Summary: In recent years, natural pigments in living organisms have attracted increased interest as an excellent biological material for the development of new biotechnological approaches. Melanin, a large polymeric pigment, has important functions in cells, including free radical scavenging and radiation protection, making this molecule attractive for medical and nutritional purposes. The variety of forms of melanin in organisms requires the use of various approaches to its purification. In this study, we have developed a simple yet unique and effective method for extracting melanin from six plant sources. The melanin yield was in the range of 6.7–21.5% for the plant sources used. The advantage of using grape skin waste as a raw material is shown, which is of great importance for obtaining cheap and functional melanin. The activity of purified melanin in scavenging 2, 2‐diphenyl‐1‐picrylhydrazyl radical is IC50 3.2–99.0 mg L−1. This remarkable feature highlights the attractiveness of grape melanin for further use as a natural antioxidant in medicine. The ability of grape melanin to adsorb heavy metal ions highlights its attractiveness for the food industry and for the development of other biotechnological applications. Smoke, after passing through a cigarette filter charged with melanin, is significantly enriched with reducing agents, which is a phenomenon for the health of smokers. [ABSTRACT FROM AUTHOR]

Background: Plane‐parallel ionization chambers are the recommended secondary standard systems for clinical reference dosimetry of electrons. Dosimetry in high dose rate and dose‐per‐pulse (DPP) is challenging as ionization chambers are subject to ion recombination, especially when dose rate and/or DPP is increased beyond the range of conventional radiotherapy. The lack of universally accepted models for correction of ion recombination in UDHR is still an issue as it is, especially in FLASH‐RT research, which is crucial in order to be able to accurately measure the dose for a wide range of dose rates and DPPs. Purpose: The objective of this study was to show the feasibility of developing an Artificial Intelligence model to predict the ion‐recombination factor—ksat for a plane‐parallel Advanced Markus ionization chamber for conventional and ultra‐high dose rate electron beams based on machine parameters. In addition, the predicted ksat of the AI model was compared with the current applied analytical models for this correction factor. Methods: A total number of 425 measurements was collected with a balanced variety in machine parameter settings. The specific ksat values were determined by dividing the output of the reference dosimeter (optically stimulated luminescence [OSL]) by the output of the AM chamber. Subsequently, a XGBoost regression model was trained, which used the different machine parameters as input features and the corresponding ksat value as output. The prediction accuracy of this regression model was characterized by R2‐coefficient of determination, mean absolute error and root mean squared error. In addition, the model was compared with the Two‐Voltage (TVA) method and empirical Petersson model for 19 different dose‐per‐pulse values ranging from conventional to UDHR regimes. The Akiake Information criterion (AIC) was calculated for the three different models. Results: The XGBoost regression model reached a R2‐score of 0.94 on the independent test set with a MAE of 0.067 and RMSE of 0.106. For the additional 19 random data points, the ksat values predicted by the XGBoost model showed to be in agreement, within the uncertainties, with the ones determined by the Petersson model and better than the TVA method for doses per pulse >3.5 Gy with a maximum deviation from the ground truth of 14.2%, 16.7%, and −36.0%, respectively, for DPP >4 Gy. Conclusion: The proposed method of using AI for ksat determination displays efficiency. For the investigated DPPs, the ksat values obtained with the XGBoost model were in concurrence with the ones obtained with the current available analytical models within the boundaries of uncertainty, certainly for the DPP characterizing UDHR. But the overall performance of the AI model, taking the number of free parameters into account, lacked efficiency. Future research should optimize the determination of the experimental ksat, and investigate the determination the ksat for DPPs higher than the ones investigated in this study, while also evaluating the prediction of the proposed XGBoost model for UDHR machines of different centers. [ABSTRACT FROM AUTHOR]

To evaluate if real-time dose visualisation during computed tomography (CT)-guided interventions leads to a reduction in radiation dose to participating radiologists. The individual radiation dose radiologists are exposed to during CT interventions was measured using dedicated dosimeters (RaySafe i2-system, Unfors RaySafe GmbH, Billdal, Sweden) worn over the usual radiation protective apron. Initially, only the total radiation dose was measured, without visualisation (control group). In the following study period, the radiation dose was shown to participants on a live screen in real-time (experimental group). In both groups, the dose was recorded in 1-second intervals. The results collected were evaluated by comparison using descriptive statistics and mixed-effect models. In particular, the variables experience, gender, role, and position during the intervention were analysed. In total, 517 measurements of 304 interventions (n= 249 with and n= 268 without live screen) performed by 29 radiologists acting as interventionalists or assistants were analysed. All CT-guided interventions were performed percutaneously, the majority of which (n= 280) were microwave ablations (MWA). Radiation doses in the group without visualisation were comparable with usual dose rates for the corresponding intervention type. The mean total radiation dose was reduced by 58.1% (11.6 versus 4.86 μSv) in the experimental group (p= 0.034). The highest reduction of 78.5% (15.55 versus 3.35 μSv) was observed in radiologists with the role of assistant (p= 0.002). Sub-analysis showed significant dose reduction (p< 0.0001) for the use of live screen in general; considering all variables, the role "assistant" alone had a statistically significant influence (p= 0.002). The real-time visualisation of active radiation dose during CT interventions leads to a relevant reduction in radiation dose to participating radiologists. • Real-time dose visualisation leads to dose reduction on participating radiologists. • Most significant dose reduction was seen in radiologists in the role of "assistant". • Interventionalist's experience influences active radiation dose during interventions. [ABSTRACT FROM AUTHOR]

In recent years, the intersection of the academic and medical domains has increasingly spotlighted the utilization of biomaterials in radioactive disease treatment and radiation protection. Biomaterials, distinguished from conventional molecular pharmaceuticals, offer a suite of advantages in addressing radiological conditions. These include their superior biological activity, chemical stability, exceptional histocompatibility, and targeted delivery capabilities. This review comprehensively delineates the therapeutic mechanisms employed by various biomaterials in treating radiological afflictions impacting the skin, lungs, gastrointestinal tract, and hematopoietic systems. Significantly, these nanomaterials function not only as efficient drug delivery vehicles but also as protective agents against radiation, mitigating its detrimental effects on the human body. Notably, the strategic amalgamation of specific biomaterials with particular pharmacological agents can lead to a synergistic therapeutic outcome, opening new avenues in the treatment of radiation- induced diseases. However, despite their broad potential applications, the biosafety and clinical efficacy of these biomaterials still require in-depth research and investigation. Ultimately, this review aims to not only bridge the current knowledge gaps in the application of biomaterials for radiation-induced diseases but also to inspire future innovations and research directions in this rapidly evolving field. [Display omitted] [ABSTRACT FROM AUTHOR]

Objectives: To assess cumulative effective dose (CED) over a 4-year period in patients undergoing multimodality recurrent imaging at a major hospital in the USA. Methods: CED from CT, fluoroscopically guided intervention (FGI), and nuclear medicine was analyzed in consecutive exams in a tertiary care center in 2018–2021. Patients with CED ≥ 100 mSv were classified by age and body habitus (underweight, healthy weight, overweight, obese), as per body mass index percentiles < 5th, 5th to < 85th, 85th to < 95th, and ≥ 95th (age 2–19 years), and its ranges < 18.5, 18.5–24.9, 25–29.9, and ≥ 30 (≥ 20 years), respectively. Results: Among a total of 205,425 patients, 5.7% received CED ≥ 100 mSv (mean 184 mSv, maximum 1165 mSv) and their ages were mostly 50–64 years (34.1%), followed by 65–74 years (29.8%), ≥ 75 years (19.5%), 20–49 years (16.3%), and ≤ 19 years (0.29%). Body habitus in decreasing occurrence was obese (38.6%), overweight (31.9%), healthy weight (27.5%), and underweight (2.1%). Classification by dose indicated 172 patients (≥ 500 mSv) and 3 (≥ 1000 mSv). In comparison, 5.3% of 189,030 CT patients, 1.6% of 18,963 FGI patients, and 0.19% of 41,401 nuclear-medicine patients received CED ≥ 100 mSv from a single modality. Conclusions: The study of total dose from CT, FGI, and nuclear medicine of patients with CED ≥ 100 mSv indicates major (89%) contribution of CT to CED with 70% of cohort being obese and overweight, and 64% of cohort aged 50–74 years. Clinical relevance statement: Multimodality recurrent exams are common and there is a lack of information on patient cumulative radiation exposure. This study attempts to address this lacuna and has the potential to motivate actions to improve the justification process for enhancing patient safety. Key Points: • In total, 5.7% of patients undergoing multimodality recurrent imaging (CT, fluoroscopically guided intervention, nuclear medicine) incurred a dose of ≥ 100 mSv. • Mean dose was 184 mSv, with 15 to 18 times contribution from CT than that from fluoroscopically guided intervention or nuclear medicine. • In total, 70% of those who received ≥ 100mSv were either overweight or obese. [ABSTRACT FROM AUTHOR]

The following glass system 35Pb3O4- 60SiO2-(5-x) ZnO- xY2O3 (x = 0, 1, 2, 4, 5) mol.% is fabricated by the classic melt-quench method. Amorphous status was confirmed by XRD analysis techniques. Structure features were influenced by yttrium oxide doping like density(5.91 to 6.97 g/cm3), molar volume (47.39 to 41.22 cm3), oxygen packing density(17.88 to 14.99 cm3), internuclear distance and number of ions (0.69 to 3.7 × 1021). Linear and non-linear optical properties are taking place. The energy gap was found to be increased from 2.59 to 2.72 eV with supplying of yttrium ions until 5 mol.% while the index of refraction decreases from 2.55 to 2.51. The nonlinear susceptibility (χ(3)) and refractive (n2) index decrease with increased yttrium concentration and have the values 0.396 to 0.351 × 10–12 (esu), 5.85 to 5.28 × 10–12 (esu) respectively. Molar refraction (12.3 to 12.32 cm3/mol.), Metallization(0.36 to 0.362), Electronegativity (0.696 to 0.704), Transmission coefficient (0.679 to 0.682) and steepness (0.097 to 0.103) were increased while the Molar polarizability (12.03 to 10.43 Ao3), Reflection loss (0.64 to 0.638), electronic polarization (2.873 to 2.866), Optical Basicity (1.352 to 1.348) and Static, Dielectric constant decreased with introduced yttrium ions. The radiation shield protection parameters like LAC (0.702 and 0.909 cm−1), MFP (1.425 and 1.1 cm),ECS (3.41 × 10−25 and 3.56 × 10−25), ACS (1.07 × 10−23 and 1.23 × 10−25), Neff (3.48 × 1023 and 3.67 × 1023), Zeff (31.25 and 34.56), R (0.66 and 0.59) and FNRCS (0.099 and 0.123) are investigated the provided values at 0.5 MeV for ZPSY0 and ZPSY5 respectively. The results indicate that Y2O3 growing in the network of glass modifies and improves the quality of present glasses against gamma radiation and fast neutrons. The superior glass sample in the present study is ZPSY5 which has 5 mol.% of Y2O3. The ZPSY5 sample can be used as a γ shield or neutrons collide in nuclear applications. [ABSTRACT FROM AUTHOR]

This manuscript explores the relationship between the economic awareness (as a part of energy awareness) of Polish households and their sustainable energy consumption practices. Sustainable consumption is measured by the frequency of behaviors such as turning off electrical devices when not in use, removing mobile device chargers from sockets, switching off lights when leaving a room, preferring showers over baths, using washing machines and dishwashers only when full, and purchasing energy-efficient appliances and light bulbs. Economic awareness is gauged through variables such as knowledge of electricity tariffs, understanding of electric bill components, awareness of electricity prices, exact knowledge of electricity expenses, electricity usage in kWh, knowledge of effective energy-saving methods, and familiarity with the energy efficiency classes of appliances and light bulbs. This study presents profiles of households with high and low economic awareness regarding their electricity expenditures and examines how these profiles differ in their sustainable energy consumption behaviors. This research is based on a survey of 1407 Polish households conducted online in 2023. Data collected from the survey were subjected to statistical analysis and are presented in tables and graphs. The findings are discussed in the context of the existing literature in the field, highlighting the implications of economic awareness on sustainable energy consumption practices. This research contributes to understanding how economic knowledge influences energy-saving behaviors among Polish households, providing insights for policymakers and energy conservation initiatives. One of the key findings of this paper is the significant association between economic awareness, energy-saving knowledge, and the adoption of sustainable energy consumption behaviors among Polish households. This study reveals that households with higher levels of economic awareness demonstrate a notably higher frequency of practices related to sustainable energy consumption compared to those with lower economic awareness. Similarly, households equipped with greater knowledge about energy-saving techniques exhibit a higher propensity to adopt energy-efficient behaviors. This underscores important roles of economic literacy and education in fostering behavioral changes towards more sustainable energy practices, highlighting the importance of targeted interventions and educational campaigns aimed at enhancing economic awareness and promoting energy-saving knowledge among consumers. [ABSTRACT FROM AUTHOR]

Radon, a radioactive inert gas that comes from the decay of naturally occurring radioactive species, poses a substantial health risk due to its involvement in lung cancer carcinogenesis. This work proposes a metrological approach for determining radon exhalation rates from diverse building materials. This methodology employs an electrostatic collection chamber for alpha spectrometry of radon isotopic decay products. Experimental evaluations were conducted particularly focusing on volcanic gray tuff from Sant'Agata de' Goti (Campania region, Italy), a material commonly utilized in construction, to assess radon exhalation rates. The study aligns with Legislative Decree 101/2020, a transposition of European Directive 59/2013/Euratom, highlighting the need to identify materials with a high risk of radon exhalation. Moreover, this work supports the goals of the Italian National Radon Action Plan related to the aforementioned decree, aiming to develop methodologies for estimating radon exhalation rates from building materials and improving radioprotection practices. [ABSTRACT FROM AUTHOR]

With the development of society and technology, machinery and equipment have enhanced our work efficiency but have also introduced various hazards, such as electromagnetic radiation, medical, industrial, and agricultural rays. The harms these radiations inflict on human health are significant, with severe cases leading to cancer, disability, or even life-threatening situations. Therefore, effective protective measures in some fields are crucial. This paper firstly summarized the basic principles of radiation protection for different rays, then systematically introduced the widely used manufacturing methods for flexible radiation shielding materials, including weaving with metal fibers, fiber blending, silver-plated fibers, and so on. Subsequently, the paper reviewed the testing methods of radiation-protective clothing materials. Finally, it comprehensively concluded the discussions on flexible radiation shielding materials and offered a perspective on their future development trends. [ABSTRACT FROM AUTHOR]

Background: In the rapidly evolving field of nuclear medicine, the paramount importance of radiation protection, safety, and quality systems cannot be overstated. This document provides a comprehensive analysis of the intricate regulatory frameworks and guidelines, meticulously crafted and updated by national and international regulatory bodies to ensure the utmost safety and efficiency in the practice of nuclear medicine. Methods: We explore the dynamic nature of these regulations, emphasizing their adaptability in accommodating technological advancements and the integration of nuclear medicine with other medical and scientific disciplines. Results: Audits, both internal and external, are spotlighted for their pivotal role in assessing and ensuring compliance with established standards, promoting a culture of continuous improvement and excellence. We delve into the significant contributions of entities like the International Atomic Energy Agency (IAEA) and relevant professional societies in offering universally applicable guidelines that amalgamate the latest in scientific research, ethical considerations, and practical applicability. Conclusions: The document underscores the essence of international collaborations in pooling expertise, resources, and insights, fostering a global community of practice where knowledge and innovations are shared. Readers will gain an in-depth understanding of the practical applications, challenges, and opportunities presented by these regulatory frameworks and audit processes. The ultimate goal is to inspire and inform ongoing efforts to enhance safety, quality, and effectiveness in nuclear medicine globally. [ABSTRACT FROM AUTHOR]

Simple Summary: External dose rate measurements for I-125 permanent radioactive source implantation brachytherapy for prostate cancer requires standardized external dose rate measurements and radiation safety procedures. We developed predictive models for external dose rates to ensure compliance with radiation safety guidelines. We used Monte Carlo simulation and experimental measurements to construct an external dose rate model. The model's accuracy was validated against external dose rate measurements from clinical patients. This model facilitates the calculation and minimization of family members' radiation dose, aiding in the development of personalized radiation protection strategies. This study uses Monte Carlo simulation and experimental measurements to develop a predictive model for estimating the external dose rate associated with permanent radioactive source implantation in prostate cancer patients. The objective is to estimate the accuracy of the patient's external dose rate measurement. First, I-125 radioactive sources were implanted into Mylar window water phantoms to simulate the permanent implantation of these sources in patients. Water phantom experimental measurement was combined with Monte Carlo simulation to develop predictive equations, whose performance was verified against external clinical data. The model's accuracy in predicting the external dose rate in patients with permanently implanted I-125 radioactive sources was high (R2 = 0.999). A comparative analysis of the experimental measurements and the Monte Carlo simulations revealed that the maximum discrepancy between the measured and calculated values for the water phantom was less than 5.00%. The model is practical for radiation safety assessments, enabling the evaluation of radiation exposure risks to individuals around patients with permanently implanted I-125 radioactive sources. [ABSTRACT FROM AUTHOR]

AbstractPurposeConclusionThe Organisation for Economic Co-operation and Development (OECD) Adverse Outcome Pathway (AOP) Development Programme is being explored in the radiation field, as an overarching framework to identify and prioritize research needs that best support strengthening of radiation risk assessment and risk management strategies. To advance the use of AOPs, an international horizon-style exercise (HSE) was initiated through the Radiation/Chemical AOP Joint Topical Group (JTG) formed by the OECD Nuclear Energy Agency (NEA) High-Level Group on Low Dose Research (HLG-LDR) under the auspices of the Committee on Radiological Protection and Public Health (CRPPH). The intent of the HSE was to identify key research questions for consideration in AOP development that would help to reduce uncertainties in estimating the health risks following exposures to low dose and low dose-rate ionizing radiation. The HSE was conducted in several phases involving the solicitation of relevant questions, a collaborative review of open-ended candidate questions and an elimination exercise that led to the selection of 25 highest priority questions for the stated purpose. These questions were further ranked by over 100 respondents through an international survey. This final set of questions was judged to provide insights into how the OECD’s AOP approach can be put into practice to meet the needs of hazard and risk assessors, regulators, and researchers. This paper examines the 25 priority questions in the context of hazard/risk assessment framework for ionizing radiation.By addressing the 25 priority questions, it is anticipated that constructed AOPs will have a high level of specificity, making them valuable tools for simplifying and prioritizing complex biological processes for use in developing revised radiation hazard and risk assessment strategies. [ABSTRACT FROM AUTHOR]

Synthetic sunscreen offers protection against excessive exposure to ultraviolet (UV) radiation from the sun, and protects the skin from possible damage. However, they have low efficacy against the formation of reactive oxygen species (ROS), which are highly reactive molecules that can be generated in the skin when it is exposed to UV radiation, and are known to play a role in oxidative stress, which can contribute to skin aging and damage. Thus, there is an ongoing search for sunscreens that do not have these negative effects. One promising source for these is natural products. Therefore, the current patent review summarizes topical formulations made from natural compounds that have antioxidant properties and can be used as photoprotective or anti-aging agents, either using a single natural extract or a combination of extracts. The review reports basic patent information (applicant country, type of applicant, and year of filing) and gives details about the invention, including its chemical composition, and the in vitro and in vivo tests performed. These patents describe natural products that can be used to protect the skin and validate their efficacy, and safety, in addition to standardizing their formulations. The compositions described illustrate the consistent innovation in the use of natural products to protect against UV damage and photoaging disorders, a promising field which is receiving growing global recognition. [ABSTRACT FROM AUTHOR]

Background: Development of resistance upon exposure to small doses of ionizing radiation followed by higher doses is known as radiation-induced adaptive response (RIAR). Traditionally, the induction of the RIAR phenomenon at the cellular level has been examined in cell lines, animal models, and epidemiological studies where people live in high natural background radiation. Summary: The primary intention of the earlier studies was to corroborate the existence of RIAR and the mechanism involved in mediating the response surveyed by exposure to a low dose of radiation (<500 mGy) as priming dose toward the radiation protection point of view. However, the investigation has shifted the focus to understand the relevance of this phenomenon at clinically relevant set-ups (high doses in the order of Gy) and can be exploited during radiotherapy as RIAR is considered a mechanism for the development of radioresistance. Although the knowledge of molecular mechanisms at the cellular level has evolved significantly in multi-fractionated radiotherapy regimes, its relevance in developing radioresistance at low doses remains elusive. The authors recapitulate the existing knowledge on RIAR at cellular levels, specifically after low-dose exposure as an adaptive dose, and discussed its potential implications in clinical radiotherapy outcomes. Key Messages: Recent studies have contributed to understand the signaling molecules, pathways, and inhibitors to mitigate RIAR-mediated radiation resistance and persistent radio-tolerance at the cellular level. Monitoring the disease progression in tumor samples or liquid biopsies before, during, and after therapy with suitable biomarkers has been proposed as a strategy to translate the phenomena into clinical scenario. [ABSTRACT FROM AUTHOR]

Radiation-induced DNA double-strand break (DSB) is the most serious type of DNA damage, which can trigger a series of DNA damage response (DDR) signaling, such as cell cycle arrest, DNA repair, apoptosis, etc. As an important process of DDR, cell cycle arrest is considered to provide sufficient time for DNA damage repair before cell division to prevent the damage DNA delivered to daughter cells. PLK1, CDK1 and CDK4/6 are important kinases of controlling cell cycle progression, and the inhibitors of these kinases can block cell cycle at certain phases. Whether they have radioprotective effect needs to be further explored. In this study, human cervical cancer HeLa cells, human normal breast MCF-10A cells and human umbilical vein epithelial cells (HUVEC) were used to determine the radioprotective effects of PLK1 inhibitors Rigosertib, Volasertib, CDK4/6 inhibitor Palbocilib and CDK1 inhibitor Ro-3306, and the related mechanisms were investigated. Flow cytometry assay demonstrated that Rigosertib, Volasertib, and Ro-3306 blocked cells in G2 phase (P < 0.05, P < 0.01, or P < 0.001), and Palbocilib blocked cells in G1 phase (P < 0.05, P < 0.01, or P < 0.001). Immunofluorescence staining assay demonstrated that Rigosertib, Volasertib, and Ro-330 significantly reduced the number of γH2AX foci after γ-ray irradiation (P < 0.001), suggesting that the above agents could promote DNA repair efficiency. HR and NHEJ reporter assays confirmed that Rigosertib and Ro-3306 promoted DNA repair via both pathways of DSBs repair simultaneously efficiency (P < 0.05 or P < 0.001), and Palbocilib and Volasertib could promote HR efficiency. From the above results, the PLK1 inhibitor Rigosertib was preferentially selected for further study. It was found that Rigosertib significantly reduced radiation-induced apoptosis (P < 0.05 or P < 0.01). CCK-8 and colony formation assays demonstrated that Rigosertib promoted the proliferation and viability of irradiated cells (P < 0.05, P < 0.01 or P < 0.001). In summary, we analyzed and compared the effects of four agents, Rigosertib, Volasertib, Palbocilib and Ro-3306, on the radiosensitivity of cells, among which Rigosertib protects the cells from radiation damage most efficiently. We provide a new strategy and experimental bases for the development of radiation protection drugs. [ABSTRACT FROM AUTHOR]

This paper thoroughly examines lanthanum-doped lead titanate (PbLaxTi(1−0.75x)O3), a perovskite-based ceramic material, focusing on its structural properties, vibrational behavior, and radiation shielding capabilities. Using advanced techniques like X-ray diffraction (XRD), Fourier transform infrared (FTIR) spectroscopy, and transmission electron microscopy (TEM), we explore the intricate relationship between lanthanum doping levels and material properties. Additionally, we assess its radiation shielding potential through metrics. Computational approaches employing the FLUKA code help evaluate theoretical values. Our findings reveal that increasing lanthanum concentration alters crystal atom arrangement, influences vibrational patterns, and enhances radiation shielding effectiveness. Increasing lanthanum concentration resulted in a maximum 7.55% rise in the mass attenuation coefficient (MAC) at 0.059 MeV. The half-value layer (HVL) decreased by 4.68% at 1.33 MeV, and the mean free path (MFP) decreased by 5.78% at 1.41 MeV with increased lanthanum ratio. Moreover, the radiation protection efficiency (RPE) increased from 30.7779 to 32.67442% at 0.059 MeV as lanthanum content increased. These findings offer valuable insights into material characteristics and suggest potential applications in enhancing radiation shielding for medical and industrial purposes. This comprehensive analysis provides practical insights for potential applications, particularly in medical or industrial radiation protection. The data-driven approach here paves the way for future research at the intersection of data science and material science, advancing material design and understanding doped perovskite materials. [ABSTRACT FROM AUTHOR]

To characterize an electron beam, visible synchrotron light is often used and dedicated beamlines at synchrotron sources are becoming a more common feature as instruments and methods for the diagnostics are, along with the accelerators, further developed. At KARA (Karlsruhe Research Accelerator), such a beamline exists and is based on a typical infrared/visible-light configuration. From experience at such beamlines no significant radiation was expected (dose rates larger than 0.5 µSv h-1). This was found not to be the case and a higher dose was measured which fortunately could be shielded to an acceptable level with 0.3 mm of aluminium foil or 2.0 mm of Pyrex glass. The presence of this radiation led to further investigation by both experiment and calculation. A custom setup using a silicon drift detector for energy-dispersive spectroscopy (Ketek GmbH) and attenuation experiments showed the radiation to be predominantly copper K-shell fluorescence and is confirmed by calculation. The measurement of secondary radiation from scattering of synchrotron and other radiation, and its calculation, is important for radiation protection, and, although a lot of experience exists and methods for radiation protection are well established, changes in machine, beamlines and experiments mean a constant appraisal is needed. [ABSTRACT FROM AUTHOR]

Key Clinical Message: A patient presented with cardiogenic shock, requiring the implantation of a left ventricular assist device (LVAD), and acute myeloblastic leukemia. This necessitated total body irradiation (TBI) while balancing dose reduction to the LVAD components to avoid potential radiation damage. Here we outline our treatment approach and dose estimates to the LVAD. This case report discusses the delivery of TBI to a patient with an LVAD. This treatment required radiation‐dose determinations and consequential reductions for the heart, LVAD, and an external controller connected to the LVAD. The patient was treated using a traditional 16MV anterior posterior (AP)/posterior anterior (PA) technique at a source‐to‐surface‐distance of 515 cm for 400 cGy in two fractions. A 3 cm thick Cerrobend block was placed on the beam spoiler to reduce dose to the heart and LVAD to 150 cGy. The external controller was placed in a 1 cm thick acrylic box to reduce neutron dose and positioned as far from the treatment fields as achievable. In vivo measurements were made using optically stimulated luminescence dosimeters (OSLDs) placed inside the box at distances of 2 cm, 8.5 cm, and 14 cm from the field edge, and on the patient along the central axis and centered behind the LVAD block. Further ion chamber measurements were made using a solid water phantom to more accurately estimate the dose delivered to the LVAD. Neutron dose measurements were also conducted. The total estimated dose to the controller ranged from 135.3 cGy to 91.5 cGy. The LVAD block reduced the surface dose to the patient to 271.6 cGy (68.1%). The block transmission factors of the 3 cm Cerrobend block measured in the phantom were 45% at 1 cm depth and decreased asymptotically to around 30% at 3 cm depth. Applying these transmission factors to the in vivo measurements yielded a dose of 120 cGy to the implanted device. The neutron dose the LVAD region is estimated around 0.46 cGy. Physical limitations of the controller made it impossible to completely avoid dose. Shielding is recommended. The block had limited dose reduction to the surface, due to secondary particles, but appropriately reduced the dose at 3 cm and beyond. More research on LVADs dose limits would be beneficial. [ABSTRACT FROM AUTHOR]

Experiments have assessed various polymer composites for radiation shielding in diverse applications. These composites are lighter and non-toxic when compared to lead (Pb), making them particularly effective in diagnostic imaging for shielding against low-energy photons. This study demonstrates the fabrication of four composites by combining a base material, specifically a high-density polyethylene (HDPE) polymer, with 10% and 20% silicon (Si) and silicon carbide (SiC), respectively. Additionally, 5% molybdenum (Mo) was incorporated into the composites as a heavy metal element. The composites obtained were fabricated into 20 disks with a uniform thickness of 2 mm each. Discs were exposed to radiation from a low-energy X-ray source (32.5–64.5 keV). The chemical and physical properties of composites were assessed. The shielding ability of samples was evaluated by determining the linear and mass attenuation coefficients (μ and μm), radiation protection efficiency (RPE), half-value layer (HVL), and mean free path (MFP). According to our findings, supplementing HDPE with additives improved the attenuation of beams. The μm values showed that composite X-ray shielding characteristics were enhanced with filler concentration for both Si and SiC. Polymer composites with micro-molecule fillers shelter X-rays better than polymers, especially at low energy. The HVL and MFB values of the filler are lower than those of the pure HDPE sample, indicating that less thickness is needed to shield at the appropriate energy. HC-20 blocked 92% of the incident beam at 32.5 keV. This study found that increasing the composite sample thickness or polymer filler percentage could shield against low-energy radiation. [ABSTRACT FROM AUTHOR]

Radiation shielding plays a crucial role in safeguarding human health, and ongoing research is exploring alternative materials for this vital purpose. Herein, physical and radiation-shielding features of the manufactured glasses via melt-quenching technique doped with ZrO2 within a glassy system, (100-x-y)[SrTiO3]-x[2B2O3·SiO2]-y(ZrO2), (39 ≤ x ≤ 40, and 0 ≤ y ≤ 4 mol % ZrO2) were studied. The density (ρ) and field-strength (Fs) values of the synthesized glasses were found to be in an increasing order of 2.6068–3.0720 g/cm3 and 5.2401–14.2399 Å−2 respectively. The study also encompassed an exploration of the radiation shielding properties such as mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), half value length, tenth value length, mean free path, effective atomic number (Zeff), and effective electron-density (Neff) of the synthesized glasses, employing the freely available 'Phy-X/PSD' software within the energy range of 0.015–15 MeV. The highest values of MAC, LAC, and Neff at 0.02 MeV were found to be 25.275 cm2/g, 77.644 cm−1, and 8.42 × 1023 electrons/g for SrTZ4 (x = 39 and y = 4) glass respectively. Notably, among all the fabricated glasses, SrTZ4 emerged as the standout performer, demonstrating superior gamma-radiation protecting abilities along with effective physical properties. Thus, the fabricated SrTZ4 glass with its remarkable radiation shielding properties holds promising applications for the development of radiation protection equipment. [ABSTRACT FROM AUTHOR]

Purpose: Intraoperative fluoroscopy use is essential during spinal fusion procedures. The amount of radiation dose should always be minimized. This study aimed to determine the feasibility of halving the frame rate from 12.5 to 6.25 frames per second (fps) and to quantify the reduction in the risk of developing radiation-induced cancer. Methods: This pilot study included 34 consecutive patients operated for open lumbar posterolateral fusion (PLF) with or without transforaminal lumbar interbody fusion (TLIF). C-arm modes were changed from half-dose (12.5 frames per second (fps), group I) to quarter-dose (6.25 fps, group II). Age, body mass index, surgical procedure, number of treated levels, and complications were collected. Kerma area product (KAP), cumulative air kerma (CAK), and fluoroscopy time were compared. Effective dose and radiation-induced cancer risk were estimated. Results: Eighteen and 16 patients were, respectively, included in group I and II. Demographic, surgical data, and fluoroscopy time were similar in both groups. However, CAK, KAP, and effective dose were significantly lower in group II, respectively, 0.56 versus 0.41 mGy (p = 0.03), 0.09 versus 0.06 Gy cm2 (p = 0.04), and 0.03 versus 0.02 mSv (p = 0.04). Radiation-induced cancer risk decreased by 47.7% from 1.49 × 10–6 to 7.77 × 10–7 after optimization. No complications were recorded in either group. Conclusion: This study demonstrates the feasibility of setting 6.25 fps for TLIF with and without PLF. By halving the fps, radiation-induced cancer risk could be almost divided by two, without compromising surgical outcome. Finally, after optimization, the risk of developing radiation-induced cancer was less than one in a million. [ABSTRACT FROM AUTHOR]

How to maximize the extraction of heat by infrared radiation while reducing the thermal conductivity to prevent heat transfer is the main challenge of radiative thermal management for emerging industrial and aerospace applications. Herein, we reported a high-temperature broadband high emissivity (Y 0.5 Lu 0.5) 2 SiO 5 ceramic with emissivity above 0.9 at room temperature and above 0.61 at elevated temperature of 1200℃ across the entire range of wavelength (1–14μm). Lu-doped rare earth monosilicate with high lattice entropy has a more complex electronic structure, boosting the emissivity of near-infrared wavelength (1–3 μm), as well as enhanced emissivity in the MIR range (3–14 μm) is derived from the lattice distortion and extra multi-mode vibrations induced by the substitutional doping of Lu3+ into the host lattice. Moreover, based on Stephen-Boltzmann law and energy conservation law found that the emissivity of rare earth monosilicate-based ceramics is negatively correlated with temperature, which may be due to the fact that rising temperature increases damping of phonon vibration of the ceramic lattice, reducing the ability of infrared absorption. This doped rare earth monosilicate ceramic has a high emissivity at high temperatures above 1200 °C, revealing immense potential in the radiation thermal protection field. [ABSTRACT FROM AUTHOR]

Traditional research has suggested that external environmental regulations and internal executive attitude are important factors. However, no in-depth study has yet to be conducted on the interaction between internal and external factors. This study constructs a model of the relationship between the different driving factors of eco-innovation from internal and external perspectives. By analyzing survey data covering 214 enterprises, this study explores the impact of environmental regulations on eco-innovation and further analyzes the moderating effect of the environmental awareness and commitment of top managers. Results show that, first, formal and informal environmental regulations and the environmental awareness and commitment of top managers have significant positive effects on eco-innovation. Second, the environmental awareness of top managers has no significant moderating effect on the relationship between environmental regulations and eco-innovation. Third, the environmental commitment of top managers has a significant positive moderating effect on the relationship between formal environmental regulations and eco-innovation. However, such environmental commitment has no significant moderating effect on the relationship between informal environmental regulations and eco-innovation. Finally, based on the empirical results, this study provides relevant managerial implications and policy suggestions. [ABSTRACT FROM AUTHOR]

During the decommissioning process of nuclear facilities, workers are exposed to radiation and face the risk of exceeding safe dose limits. Ensuring the safety of personnel requires not only enhancing radiation protection measures but also optimizing work paths to minimize exposure time and avoid high-radiation areas. This paper proposes a nested optimization algorithm that combines an ant colony optimization (ACO) with an improved A* algorithm for the decommissioning of a nonradiation source. The algorithm aims to minimize the total radiation dose and transforms the original path optimization problem into an equivalent traveling salesperson problem. The improved A* algorithm is employed in the inner layer to calculate the path with the lowest radiation dose for any given sales order. The ACO operates in the outer layer to determine a set of optimal working paths that traverse all target points. The provided solution example demonstrates that the proposed path optimization algorithm effectively integrates the radiation field and obstacles. It successfully identifies a sequence for dismantling with the lowest dose and corresponding optimal work path while ensuring the completion of the dismantling task. These findings are expected to offer valuable insights for optimizing personnel work paths during the subsequent decommissioning process of nuclear facilities. [ABSTRACT FROM AUTHOR]

Moon is an auspicious environment for the study of Galactic cosmic rays (GCR) and Solar Particle Events (SEP) due to the absence of magnetic field and atmosphere. The same characteristics raise the radiation risk for human presence in orbit around it or at the lunar surface. The secondary (albedo) radiation resulting from the interaction of the primary radiation with the lunar soil adds an extra risk factor, because neutrons are produced, but also it can be exploited to study the soil composition. In this paper, the design of a comprehensive radiation monitor package tailored to the lunar environment is presented. The detector, named LURAD, will perform spectroscopic measurements of protons, electrons, heavy ions, as well as gamma-rays, and neutrons. A microdosimetry monitor subsystem is foreseen which can provide measurements of LET(Si) spectra in a wide dynamic range of LET(Si) and flux for SPE and GCR, detection of neutrons and biological dose for radiation protection of astronauts. The LURAD design leverages on the following key enabling technologies: (a) Fully depleted Si monolithic active pixel sensors; (b) Scintillators read by silicon photomultipliers (SiPM); (c) Silicon on Insulator (SOI) microdosimetry sensors; These technologies promise miniaturization and mass reduction with state-of-the-art performance. The instrument's design is presented, and the Monte Carlo study of the feasibility of particle identification and kinetic energy determination is discussed. [ABSTRACT FROM AUTHOR]

Gels are soft materials composed of hydrophilic polymers cross-linked in water by physical or chemical bonds. Due to their lightweight and water-rich nature, these materials find application in various fields, including the space environment, for radiation protection purposes. In fact, thanks to their high hydrogen content, gels exhibit significant radiation stopping power, resulting in reduced fragmentation of incident particles. This suggests their potential utility in shielding electronic devices and safeguarding astronauts' health. In this work, cross-linked gels based on poly(vinyl alcohol) (PVA) and boric acid (BA) were fabricated and their properties were investigated using different experimental and modeling techniques. The effect of parameters, such as time and temperature, used for fabricating the PVA/BA gels is assessed. Fourier transform infrared spectroscopy (FTIR) was employed to evaluate the ability of BA to form hybrid interpolymeric bonds with PVA macromolecules. To understand the thermo-mechanical properties and viscoelastic behavior of these gels, dynamic mechanical analysis (DMA) in compression mode was performed. The shielding properties were evaluated in different space radiation environments considering galactic cosmic rays, solar particle events, and low earth orbit radiation using deterministic transport codes. The High charge (Z) and Energy TRaNsport (HZETRN) code was employed to create different cross sections as first output for the selected materials, and then, propagate and transport the ionizing radiation inside the materials. The results highlight several advantages of PVA/BA gels fabricated at room temperature without heat treatments. Firstly, the incorporation of BA allows for a slight increase in water content compared to gels produced without the crosslinker. Additionally, an examination of elastic moduli reveals improved mechanical properties exhibiting approximately twice the elastic modulus of PVA gels. Moreover, the analysis of dosimetry quantities suggests that the radiation protection effectiveness of these gels is comparable to that of pure water, while heat-treated PVA/BA gels exhibit a reduced water content resulting in decreased shielding properties and decreased flexibility. Consequently, PVA/BA gels realized at room temperature appear to be the optimal material between PVA gels and the heat-treated counterparts, making them well-suited for integration into astronaut personal protective equipment. [Display omitted] • Cross-linked gels made of poly(vinyl alcohol) matrix and boric acid crosslinker are realized. • The coordinative bonds between boric acid and poly(vinyl alcohol) are determined by the Fourier transform infrared spectroscopy. • Boric acid greatly increases the mechanical properties of gels in terms of storage modulus. • The effectiveness of gels in radiation shielding has been demonstrated by numerical simulation carried out using HEZTRN2020 • Gels of poly(vinyl alcohol) and boric acid can be used in spacesuits of astronauts as personal protective equipment. [ABSTRACT FROM AUTHOR]

Background: In order to ensure adequate radiation protection of critical groups such as staff, caregivers and the general public coming into proximity of nuclear medicine (NM) patients, it is necessary to consider the impact of the radiation emitted by the patients during their stay at the hospital or after leaving the hospital. Current risk assessments are based on ambient dose rate measurements in a single position at a specified distance from the patient and carried out at several time points after administration of the radiopharmaceutical to estimate the whole-body retention. The limitations of such an approach are addressed in this study by developing and validating a more advanced computational dosimetry approach using Monte Carlo (MC) simulations in combination with flexible and realistic computational phantoms and time activity distribution curves from reference biokinetic models. Results: Measurements of the ambient dose rate equivalent Ḣ*(10) at 1 m from the NM patient have been successfully compared against MC simulations with 5 different codes using the ICRP adult reference computational voxel phantoms, for typical clinical procedures with 99mTc-HDP/MDP, 18FDG and Na131I. All measurement data fall in the 95% confidence intervals, determined for the average simulated results. Moreover, the different MC codes (MCNP-X, PHITS, GATE, GEANT4, TRIPOLI-4®) have been compared for a more realistic scenario where the effective dose rate Ė of an exposed individual was determined in positions facing and aside the patient model at 30 cm, 50 cm and 100 cm. The variation between codes was lower than 8% for all the radiopharmaceuticals at 1 m, and varied from 5 to 16% for the face-to face and side-by-side configuration at 30 cm and 50 cm. A sensitivity study on the influence of patient model morphology demonstrated that the relative standard deviation of Ḣ*(10) at 1 m for the range of included patient models remained under 16% for time points up to 120 min post administration. Conclusions: The validated computational approach will be further used for the evaluation of effective dose rates per unit administered activity for a variety of close-contact configurations and a range of radiopharmaceuticals as part of risk assessment studies. Together with the choice of appropriate dose constraints this would facilitate the setting of release criteria and patient restrictions. [ABSTRACT FROM AUTHOR]

Introduction: Tuberculosis remains one of the top ten causes of mortality globally. Children accounted for 12% of all TB cases and 18% of all TB deaths in 2022. Paediatric TB is difficult to diagnose with conventional laboratory tests, and chest radiographs remain crucial. However, in low-and middle-income countries with high TB burden, the capacity for radiological diagnosis of paediatric TB is rarely documented and data on the associated radiation exposure limited. Methods: A multicentre, mixed-methods study is proposed in three countries, Mozambique, South Africa and Spain. At the national level, official registry databases will be utilised to retrospectively compile an inventory of licensed imaging resources (mainly X-ray and Computed Tomography (CT) scan equipment) for the year 2021. At the selected health facility level, three descriptive cross-sectional standardised surveys will be conducted to assess radiology capacity, radiological imaging diagnostic use for paediatric TB diagnosis, and radiation protection optimization: a site survey, a clinician-targeted survey, and a radiology staff-targeted survey, respectively. At the patient level, potential dose optimisation will be assessed for children under 16 years of age who were diagnosed and treated for TB in selected sites in each country. For this component, a retrospective analysis of dosimetry will be performed on TB and radiology data routinely collected at the respective sites. National inventory data will be presented as the number of units per million people by modality, region and country. Descriptive analyses will be conducted on survey data, including the demographic, clinical and programmatic characteristics of children treated for TB who had imaging examinations (chest X-ray (CXR) and/or CT scan). Dose exposure analysis will be performed by children's age, gender and disease spectrum. Discussion: As far as we know, this is the first multicentre and multi-national study to compare radiological capacity, radiation protection optimization and practices between high and low TB burden settings in the context of childhood TB management. The planned comparative analyses will inform policy-makers of existing radiological capacity and deficiencies, allowing better resource prioritisation. It will inform clinicians and radiologists on best practices and means to optimise the use of radiological technology in paediatric TB management. [ABSTRACT FROM AUTHOR]

The present study deals with fabricating and characterizing glass fiber reinforced epoxy composites with heavy mineral filler (magnetite particles) for potential low-energy radiation shielding applications. The composite materials were fabricated by the hand layup method. Glass/epoxy composite was used as control sample, and radiation shielding composites were manufactured by mixing 20 and 30% (by weight) magnetite particles with epoxy resin. It was revealed that the tensile properties of the magnetite-modified composites were increased, and the composites containing 30% filler exhibited maximum improvement than the control ones. Further assessment of the composite samples was performed by DMA (Dynamic Mechanical Analysis), TGA (Thermogravimetric Analysis), FTIR (Fourier-Transform Infrared) spectroscopy, water uptake (%), and SEM (Scanning Electron Microscopy) testing. The radiation shielding ability of the control and filler-modified composites was assessed by using a gamma (γ) radiation source (60Co). Then, the shielding efficiency was characterized by radiation-reduced intensity (%), LAC (Linear Attenuation Coefficient), MAC (Mass Attenuation Coefficient), HVL (Half Value Layer), TVL (Tenth Value Layer), and SVL (Sixteenth Value Layer). It was revealed that the 30% magnetite filler content composite experienced relatively good attenuation performance against γ-ray than other studied composites. [ABSTRACT FROM AUTHOR]

The article endeavours to examine and analyse the geostrategic significance and impact of complex economic and political processes on current national social and legislative models, as well as the trend of deglobalization. The authors present the fundamental meanings and conclusions derived from the analysis. It is argued that in the context of deglobalization, the creation, revision, and potential re-evaluation of legal norms should prioritize moral and social considerations. This assertion holds true irrespective of the geopolitical influences related to human rights protection and social development within a state. [ABSTRACT FROM AUTHOR]

This work is devoted to calculating the rate of radiation damage production in a uranium target irradiated with high-energy electrons with an energy of 100 MeV. The Monte Carlo program MCNPX was used to perform a complete mathematical modeling of a complex of processes occurring in a uranium target when irradiated with high-energy electrons: the development of an electromagnetic shower, the production of photoneutrons, the transport of particles in the target and the creation of radiation damage in it. The analysis showed that fragments of U-238 photo-fission give the main input into the rate of damage production in a uranium target which reaches the value of 100 dpa/year. The expected service life of a uranium target under irradiation is 3 years of operation at full accelerator power. [ABSTRACT FROM AUTHOR]

This paper provides a legal analysis of the direct line in the legislation of the European Union. The direct line, serving as a legal instrument to implement off-grid solutions, plays a crucial role in amplifying competition within the energy market. Compared to other instruments introduced by the First Liberalization Package in 1992, the direct line is not a subject commonly brought about by legal literature. The core part of legal analyses is divided into two parts, which focus on different approaches of direct line, i.e., European Union and selected Member States (Estonia, Latvia, Lithuania, and Poland). The motives of the Union in establishing the direct line instrument was to support opening the energy market to increase energy generating units. During the transposition of the direct line into national laws, analysed countries have directed the usage of this mechanism to promote renewable energy sources. The presented case studies create a rare pattern of how the Member States form their own interpretations and hence use the Union law in practice, which differs from the direction established in the Union forum. The research focused on legal dogmatic examining of regulations at both European and national levels, with a particular emphasis on the definition part while figuring a crucial role in shaping the direct line concept. The paper also presents other convoluted legal schemes, such as the permit issuance process for direct line construction. The conclusions assess the modifications in the European Union regime, but also their impact on electricity prices and green investments. [ABSTRACT FROM AUTHOR]

Introduction: The potential damage of radiation has encouraged the creation of dose optimization programs; however, its performance has been poorly assessed in Mexico. Objective: To compare the effective dose calculated in a conventional tomograph against a different equipment with a dose optimizer. Method: Observational, analytical, comparative and crosssectional study. DLP records were collected from a conventional scanner (T1) and from another with the software iDose® (T2) of the High Specialty Hospital of Veracruz in the period 2018-2020. Results: 658 patients were recorded; 323 (49%) were obtained from T1, 335 (51%) from T2. The mean age was 35.2 ± 23.8. 400 (60.8%) represented men, 258 (39.2%) for women. The average effective dose was 2.42 mSv ± 1.2 and 2.4 mSv ± 0.94 for T1 and T2 respectively. The iDose® program was applied on 169 patients, namely 25.6% of the T2 records, and 29.7% of the total sample. The use of iDose® resulted in an OR: 0.684 (95%CI: 0.48-0.97). Conclusion: The employment of dose optimization programs is a protective factor against high radiation levels. It is advisable to promote the utilization of these systems in imaging centres. [ABSTRACT FROM AUTHOR]

Glass is a versatile material with diverse structures and technological applications depending on composition and attributes. In the present study, the optical, physical, and radiation-interaction-response parameters of 70B2O3: 10Na2O: 15PbO: (5-x)Tb2O3: xBi2O3, with x = 2, 3, 4, 1nd 5 mol% glasses prepared using the melt-and-rapidly cool method were assessed and studied. The mass attenuation coefficients ( μ / ρ ) were evaluated for 0.2, 0.662, and 1.25 MeV photons with the aid of XCOM. The density of the glass system increased from 3.61 g/cm3 to 3.70 g/cm3 as the molar ratio of Bi2O3 relative to Tb2O3 increased from 0.67 to 5. Also, the molar volume of the glasses increased from 29.958 cm3/mol to 35.973 cm3/mol for the same molar ratio increase. The refractive index of the BNPBTx glasses increased from about 2.22 to 2.5. The molar refractivity and polarizability increased with Bi2O3 content within the range of 16.98–20.69 cm3/mol and 6,74 × 10–24–8.21 × 10–24 cm3, respectively. Other estimated optical parameters showed variations in contrast to glass chemical content. The μ / ρ vary within the range 0.0566–0.4720 for BNPBT1; 0.0568–0.4898 for BNPBT2; 0.0570–0.5074 for BNPBT3; and 0.0572–0.5246 cm2/g for BNPBT4. The increase in the Bi2O3/Tb2O3 concentration ratio improved the gamma photon and neutron interaction prowess of BNPBT glasses. The investigated glasses showed better radiation shielding abilities compared to existing shielding glasses. They are thus recommended for radiation control and optical applications. [ABSTRACT FROM AUTHOR]

With the continuous development of medical technology, the application of optical sensors in the medical field is gradually increasing. However, in some special surgeries, prolonged exposure of patients to radiation may have adverse effects on their health, so a new type of protective surgical support is needed to reduce the damage caused by radiation to patients and medical staff. By conducting research on the application of existing optical sensors in the medical field and considering the radiation exposure during radiation surgery, a new type of protective surgical support plate has been designed. In clinical experiments, this article uses 1 upper baffle, 3 upper baffle, 1 hand support protective plate, and 2 hand support protective plates to observe and compare the peripheral dose equivalent rates of the head, chest, abdomen, lower limbs, and feet at the first and second surgical positions, and analyze the radiation protection effects of the four types of protective hand support plates. The experimental results indicate that the new protective surgical support plate can effectively reduce the radiation exposure of patients during radiation surgery. The monitoring data of optical sensors shows that the radiation exposure level of patients using new pallets is significantly lower than that of patients using traditional pallets. [ABSTRACT FROM AUTHOR]

This paper proposes a circularly polarized ultra-thin flexible antenna with a flexible rectifier and power management unit (PMU) for smartwatch/wristband applications. The flexible antenna is compact (0.17λ0 × 0.20λ0 × 0.0004λ0) and has a stepped ground plane. A parasitic element is used at the substrate bottom to reduce the specific absorption rate (SAR) and enhance the gain up to 3.2 dBi, at the resonating frequency of WLAN/Wi-Fi (2.45 GHz). The SAR of the proposed design is also analysed at the resonating frequency, and it satisfies the guidelines of the International Commission on Non-Ionizing Radiation Protection (ICNIRP) and IEEE C95.1–2019 human safety standards. An impedance matching circuit is used between the antenna and the RF energy harvester to improve conversion efficiency. Polarization mismatch is avoided with the help of circular polarization, achieved by tuning stubs of size 0.02λ0 × 0.044λ0. The integration of the antenna and rectenna results in a good conversion efficiency of 78.2% at − 5 dBm of input power with a load resistance of 2 KΩ. The availability of RF signals allows the user to charge the smartwatch/wristband by connecting the PMU circuit with the RF energy harvester. [ABSTRACT FROM AUTHOR]