Radiation Protection Research Articles

A first-time fusion of TiNbWMoZrOx high entropy oxide (HEO) with zinc-tellurite glass: Toward superior physical properties

While numerous oxide additives have traditionally been employed to enhance the radiation shielding capabilities of glasses, the unique attributes of high-entropy oxides (HEOs), a group of materials acclaimed in contemporary material science for their distinctive properties have remained unexamined in this specific area. This novel study explores the enhancement of radiation shielding properties in zinc-tellurite glasses through the integration of TiNbWMoZrOx High Entropy Oxides (HEO). Utilizing advanced synthesis techniques, including mechanical alloying and oxidation, the research successfully incorporates HEOs into glass matrices, aiming to improve gamma-ray and neutron attenuation. Characterization through X-ray diffraction (XRD), scanning electron microscopy (SEM), and X-ray photoelectron spectroscopy (XPS) confirms the uniform distribution and structural integrity of the HEOs within the glasses. The synthesis of glass samples with a base structure suitable for the molar composition of 25ZnO.75TeO2 (mol%) and glass samples doped with TiNbWMoZrOx (HEO) was carried out using the traditional high-temperature melting and annealing method. The outcomes demonstrate a concentration-dependent increase in shielding efficacy, particularly highlighting the superior performance of glasses doped with 4 mol% of TiNbWMoZrOx (HEC2–4), which exhibit significantly enhanced mass attenuation coefficients, lower half-value layers, and higher effective atomic numbers. This indicates the effective role of HEOs in boosting radiation protection capabilities. Comparative analysis with traditional shielding materials showcases the HEC2–4 glasses' competitive advantage, underlining their potential as a versatile shielding solution. It can be concluded that incorporating TiNbWMoZrOx high entropy oxides into zinc-tellurite glasses significantly augments their radiation shielding properties, offering a novel approach for enhancing protection against gamma-ray and neutron in various applications.

A framework for in-field and out-of-field patient specific secondary cancer risk estimates from treatment plans using the TOPAS Monte Carlo system

Objective. To allow the estimation of secondary cancer risks from radiation therapy treatment plans in a comprehensive and user-friendly Monte Carlo (MC) framework. Method. Patient planning computed tomography scans were extended superior-inferior using the International Commission on Radiological Protection’s Publication 145 computational mesh phantoms and skeletal matching. Dose distributions were calculated with the TOPAS MC system using novel mesh capabilities and the digital imaging and communications in medicine radiotherapy extension interface. Finally, in-field and out-of-field cancer risk was calculated using both sarcoma and carcinoma risk models with two alternative parameter sets. Result. The TOPAS MC framework was extended to facilitate epidemiological studies on radiation-induced cancer risk. The framework is efficient and allows automated analysis of large datasets. Out-of-field organ dose was small compared to in-field dose, but the risk estimates indicate a non-negligible contribution to the total radiation induced cancer risk. Significance. This work equips the TOPAS MC system with anatomical extension, mesh geometry, and cancer risk model capabilities that make state-of-the-art out-of-field dose calculation and risk estimation accessible to a large pool of users. Furthermore, these capabilities will facilitate further refinement of risk models and sensitivity analysis of patient specific treatment options.

The radiation protection behavior of medical workers: A scoping review protocol.

Radiation exposure in medical settings stands as the primary source of artificial radiation, compounded by the yearly rise in healthcare worker numbers. Ensuring radiation protection is crucial for safeguarding their occupational health. Nevertheless, existing studies on radiation protection behavior exhibit considerable heterogeneity due to various factors. This scoping review aims to explore the current status of research on radiation protection behavior and identify research gaps, intending to guide future research directions. The scoping review will follow the Arksey and O'Malley framework and the Joanna Briggs Institute methodology. A systematic search will be conducted across English databases including PubMed, Web of Science, Embase, and Medline, as well as Chinese databases such as CNKI, Wanfang, VIP, and China Biomedical Literature Database. Two independent reviewers will screen the studies based on predefined eligibility criteria and extract the data. Any disagreements will be resolved through discussion by a third reviewer. The review will be reported according to the Preferred Reporting Items for Systematic Reviews and Meta-Analysis extension for Scoping Reviews. A stakeholder consultation will provide an opportunity to validate the findings and address any potential gaps in the article. In this scoping review, all types of studies will be considered. The effectiveness of the methodological quality of the included studies will not be reported, which may lead to some studies of poor quality being included. Only studies published in English or Chinese after 2010 will be considered in this review, potentially leading to the omission of relevant papers.

A critical assessment of the mechanical strength and radiation shielding efficiency of advanced Concrete composites and Vanadium Oxide-Glass container for enhanced nuclear waste management

The nuclear industry produces large quantities of low, intermediate, and high levels of radioactive waste, all of which require safe management during both transport and storage. This study evaluates the radiation shielding effectiveness and mechanical properties of four distinct container materials: Pb Composite Glass, 0.5 Cement-0.5 Bitumen, Concrete (Steel-Magnetite), and C9 (BCBV0.5) Vanadium Oxide-Glass. Using Monte Carlo simulations and theoretical methods, we determined the Transmission Factors (TF) and Half-Value Layers (HVL) for each material. The TF indicates the effectiveness of a material in attenuating radiation, calculated by the ratio of gamma rays exiting the material to those entering it. Lower TF values signify better radiation shielding. The HVL is the thickness of material required to reduce the intensity of gamma rays by half, with lower HVL values indicating more effective shielding. Concrete (Steel-Magnetite) demonstrated superior performance with the lowest TF values (e.g., 1.0 × 10-1 at 0.662 MeV and 1 cm thickness) and HVL values (e.g., 2.5 cm at 1.3325 MeV), alongside a high elastic modulus of 163.15 GPa, indicating its robustness for high-energy gamma-ray applications. Pb Composite Glass also showed strong performance with a TF of 9.5 × 10-2 at 0.662 MeV and 1 cm thickness, an HVL of 2.0 cm at 0.662 MeV, and an elastic modulus of 41.54 GPa. The C9 (BCBV0.5) Vanadium Oxide-Glass, with an elastic modulus of 73.79 GPa, outperformed the 0.5 Cement-0.5 Bitumen mixture in both TF (e.g., 1.15 × 10-1 at 0.662 MeV and 1 cm thickness) and HVL (e.g., 4.2 cm at 1.1732 MeV) measurements, highlighting its potential as a more effective alternative. It can be concluded that C9 (BCBV0.5) Vanadium Oxide-Glass presents promising properties for future advancements in radiation protection, warranting further research and optimization.

Looking at the Gender Disparity in Interventional Radiology: A Scoping Review.

The underrepresentation of women within Interventional Radiology (IR) is profound. This scoping review aims to evaluate the current literature on gender disparity within IR. To uncover relevant themes and research gaps to inform future research and to recommend changes aimed at increasing application and retention of women in IR. A review of MEDLINE, EMBASE and Web of Science was conducted. Specific inclusion and exclusion criteria were used to gather all relevant literature. Thematic analysis of included literature highlighted themes and commonalities between papers. Of 396 articles only 15 met the inclusion criteria. Many papers were excluded due to their lack of relevance to the topic. Thematic analysis identified six themes radiation exposure, mentorship, male dominance, work-life balance, research, and early exposure to IR. Recommendations relating to each theme have been made. Establishing a high-quality mentoring scheme, for medical students, is the priority. Followed by accurate information, regarding radiation safety and teaching opportunities provided by medical schools and placement trusts, to demonstrate the value of IR and the need for a representative workforce.

Evaluation of Some Heavyweight Minerals as Sustainable Neutron and Gamma-Ray Attenuating Materials: Comprehensive Theoretical and Simulation Investigations

AbstractThis study comprehensively evaluates the radiation attenuation efficiencies of hematite and barite, commonly used materials in radiation shielding, using theoretical and simulation investigations. The MCNP-5 code was used to obtain the linear attenuation coefficient (LAC) within the energy range of 0.015–15 MeV, with validation by the XCOM program. Based on these LAC values, various gamma-ray shielding parameters were determined: mass attenuation coefficient, half-value layer, radiation protection capacity, mean free path, transmission factor, and equivalent thickness to lead (ETPb). Additionally, effective atomic number (Zeff) and electron density (Neff) were calculated, including both single-energy and energy-dependent forms for photon absorption and interaction. Furthermore, MCNP-5 simulations and NGCal program calculations were used to assess thermal neutron attenuation, while the NXcom program determined fast neutron behavior. This analysis revealed superior γ-ray shielding for barite compared to hematite. Similarly, the NXcom program indicated better fast neutron shielding for barite. However, interestingly, simulations validated a 210% higher effectiveness in thermal neutron attenuation for hematite. Finally, comparing the studied materials with other shielding materials demonstrated promising potential as environmentally friendly alternatives for effective shielding against various radiation types.

Safety evaluation of electromagnetic exposure for compact wireless charging stations of electric vehicles

ABSTRACT The spatial electromagnetic field of electric vehicle (EV) wireless charging stations may experience a superposition effect, which will increase the electromagnetic radiation. To assess the safety of electromagnetic exposure from wireless charging stations, this study employs a finite element simulation software to construct an electromagnetic environment model for a compact wireless charging station. The model is utilized to compute the superposition effect of spatial electromagnetic fields resulting from the simultaneous charging of multiple wireless chargers. Furthermore, the model assesses the levels of electromagnetic exposure on human models at eight observation points situated within the charging station. Results indicate that the volume average values of spatial magnetic induction strength ( B ) and electric field strength ( E ) are higher when multiple EVs are charged simultaneously than when a single EV is charged, and the electromagnetic radiation received by a human standing between two vehicles is greater than that near one vehicle. At the 22 kW charging power level, the maximum values of B , E and current density at the eight observation points of the charging station are all below the International Commission on Non-Ionizing Radiation Protection limit, demonstrating that the human body is safe in compact wireless charging stations at this power level.

Let's talk about radiation dose and radiation protection in children.

Children are more sensitive to ionizing radiation than adults. Even though the risk is very low, exposure from radiological examinations can possibly cause them long-term side effects. Recent large epidemiological studies involving children and young adults have added evidence suggesting that even small doses of radiation, such as those from computed tomography scans, might slightly increase the risk of developing cancer later in life. Therefore, even though radiologic studies are essential for an accurate diagnosis and management of various conditions, it is crucial to minimize radiation exposure. This article addresses radiation protection for children in the medical use of ionizing radiation and it is set in the context of the European legislative framework regarding radiation protection. It advocates for a holistic approach to paediatric radiological tests. This approach includes the key principles of radiation protection, such as the justification of imaging procedures supported by referral guidelines, as well as the optimization of techniques (according to the ALARA principle) and effective communication with parents about the benefits and the risks of radiologic procedures. Protecting children from unnecessary radiation is not only a technical challenge, but also a moral obligation and a legal requirement.

Impact of Bi2O3 on prepared nano (SiO2-Na2O-CaO-B2O3) glass as radiation shielding material

Melt quenching technique was used to create Bismuth Boro-Silicate nano glasses with compositions of 45SiO2-10CaO- 25Na2O- xBi2O3- (20-x) B2O3 (where x is 0, 5, 10, 15, and 20 mol %). Standard point sources AM-241, Ba-133, Co-60, Cs-137, and Eu-152 were used in the radiation experiment to evaluate the attenuation coefficients spanning the energy range of 59.51 keV to 1048.01 keV. The findings show that adding Bi2O3 in place of B2O3 increases the following: radiation protection efficiency (RPE%), transmission factor (TF%), absorption buildup factor values (ABF), exposure buildup factor values (EBF), mass attenuation coefficients (MACs), linear attenuation coefficients (LACs), and radiation protection efficiency (RPE%). In comparison to lead glass, these findings demonstrate the potential of nano Bismuth Boro-Silicate glass as a radiation shielding material.

Radiation protection adherence and associated factors among radiology personnel.

The aim of the study was to investigate radiation protection adherence among radiology personnel and associated factors. In light of the increasing integration of ionizing radiation in medical diagnostics and treatment-specifically in areas such as computed tomography, fluoroscopy, and therapeutic radiology-it is vital for radiology personnel to consistently uphold rigorous radiation protection standards. This cross-sectional study employed a self-administered questionnaire to collect demographic data and assess various aspects of radiation protection adherence among radiology personnel. The gathered data were entered into SPSS 16 for statistical analysis. Among the 119 participants, 72 (60.5%) worked in the radiology department, and 88 (77.9%) were married. Significant associations were observed between adherence levels and marital status, age groups, years of experience, and department type. Study findings showed a significant association between several demographic factors and radiation protection adherence. Furthermore, our results highlight the value of implementing radiation protection courses to enhance adherence among personnel.

X-ray spectrometry for calculating conversion coefficients from air kerma to operational quantities in radiation protection

This study explores the conversion coefficients from air kerma to operational quantities for radiation protection, using x-ray spectrometry for the narrow-beam qualities below 300 keV as defined by ISO 4037-1. By employing custom spectral correction algorithms combined with modern cadmium telluride (CdTe) semiconductor detectors, we effectively corrected spectral distortions caused by detection processes, ensuring more reliable measurements. These measurements are crucial for meeting radiation protection standards. The study also analyses the sources of uncertainty associated with the determination of conversion coefficients, thereby providing improved accuracy and reproducibility in photon dosimetry.

Optimizing Regulatory Reviews for Clinical Protocols that Use Radiopharmaceuticals: Findings of the University of Pennsylvania Radiation Research Safety Committee.

Institutional radiation safety committees review research studies with radiation exposure. However, ensuring that the potential patient benefit and knowledge gained merit the radiation risks involved often necessitates revisions that inadvertently delay protocol activations. This quality-improvement study analyzed protocols, identified factors associated with approval time by a radiation safety committee, and developed guidelines to expedite reviews without compromising quality. Clinical protocols submitted to the University of Pennsylvania's Radiation Research Safety Committee (RRSC) for review between 2017 and 2021 were studied. Protocol characteristics, review outcome, stipulations, and approval times were summarized. Statistical analysis (Spearman's rho) was used to investigate stipulations and approval time; rank-sum analysis (Kruskal-Wallis or Wilcoxon) was used to determine whether approval time differed by protocol characteristics. One hundred ten (110) protocols were analyzed. Approximately two-thirds of protocols used approved radiopharmaceuticals to aid investigational therapy trials. Twenty-three percent (23%) of protocols received RRSC approval, and 73% had approval withheld with stipulations, which included requests for edits or additional information. Submissions had a median of three stipulations. Median and mean RRSC approval times were 62 and 80.1 d, and 41% of protocols received RRSC approval after IRB approval. RRSC approval time was positively correlated with stipulations (Spearman's rho = 0. 632, p < 0.001). RRSC approval time was longer for studies using investigational new drugs (median 80 d) than approved radiopharmaceuticals (median 57 d, p = 0.05). The review process is lengthy and may benefit from changes, including publishing standardized radiation safety language and commonly required documents and encouraging timely response to stipulations.

Radiation safety of dentomaxillofacial radiology in Finland: Reported abnormal irradiation-related incidents during 2012–2022

IntroductionThis study evaluates adverse events (AEs) in dentomaxillofacial radiology (DMFR) in Finland, including their quantity, nature, and outcomes. It also compares reporting activity between public and private healthcare organizations, as they share same legal obligations to report AEs. Two-thirds of dental images are taken in public, the rest in private healthcare. MethodsIn Finland, radiation-related AEs are reported to the Radiation and Nuclear Safety Authority (STUK). We categorized DMFR-related AEs by nature, outcome, and imaging modality. We also submitted a questionnaire to STUK to gather information on their observations and remarks made during inspections of establishments providing dental imaging services. ResultsDuring 2012–2022, STUK received reports of 1343 DMFR-related AEs, mostly causing patient harm (92.9%) leading almost always to excessive radiation doses (99.7%). Private healthcare reported most AEs (65.2%), with municipal institutions reporting the remainder (34.8%). Intraoral-related AEs (20.0%) slightly outnumbered panoramic-related ones (18.7%), but the majority (56.7%) didn't specify the imaging modality. CBCT-related incidents were least reported (4.5%). During STUK's inspections, remarks mostly concerned deficiencies in practical quality assurance (31.3%) or technical quality assurance (32.9%). ConclusionDMFR-related AEs may be underreported despite legal obligations, with most stemming from human error, highlighting the need to enhance patient safety culture. There's a notable reporting gap between private and public healthcare providers relative to the number of dental radiographs conducted. Organizational deficiencies in practical and technical quality assurance underscore the importance of ongoing education, as well as monitoring by STUK. Implications for practiceEnhancing patient safety culture in dentistry, including dentomaxillofacial radiology, demands customized multiprofessional development, as unaltered patient safety procedures from medicine and secondary care may not align with dentistry's requirements.

Optimization of protection in pediatric interventional radiology in Latin America and the Caribbean: participation and challenges for Colombia

Optimization of protection in pediatric interventional radiology in Latin America and the Caribbean: participation and challenges for Colombia

Design of a multichannel vacuum ultraviolet spectroscopy system for SPARC.

The design of a vacuum ultraviolet spectroscopy system has been performed to monitor and provide feedback for impurity control in SPARC. The spectrometer, covering a wavelength range of 10-2000Å through a flat-field configuration with diffraction gratings, incorporates five survey lines of sight. This allows for comprehensive impurity analysis across the core and four divertor regions (inner/outer and upper/lower). Its compact modular design facilitates vertical stacking of each spectrometer unit, significantly reducing space in the tokamak hall, where a dedicated radiation shielding bunker will be built. Safety features include a secondary helium enclosure to mitigate tritium permeation risks during deuterium-tritium (D-T) operations and shielding within the beamlines for enhanced radiation protection. The silicon carbide mirror design for divertor observation ensures its survivability in the in-vessel environment of SPARC, validated by thermal and electromagnetic analysis. Signal modeling and data acquisition testing results show that an exposure time of a few milliseconds is appropriate considering photon flux reaching the detector, demonstrating the system's capability for discharge control that includes disruption avoidance.

Ambient dosimetry in pulsed neutron fields with LINrem detectors

The status of the LINrem project is presented, focusing on the development of innovative neutron dosimeters with enhanced energy sensitivity, time resolution, and portability. Designed to meet the technical demands of radiation protection in modern particle and nuclear facilities, these dosimeters are discussed in detail. Results from experimental campaigns showcasing their efficacy in pulsed fields generated by fusion plasmas and high-intensity pulsed lasers are presented. Additionally, prospects and future plans for the LINrem project are outlined.

Modern Radiation Safety in the Cardiology Catheter Laboratory, Are We Doing Enough?

Modern Radiation Safety in the Cardiology Catheter Laboratory, Are We Doing Enough?

Radiotolerant endophytic bacteria and analysis of the effects of 137Cesium on the metabolome of Pantoea sp.

Some bacteria have developed mechanisms to withstand the stress caused by ionizing radiation. The ability of these radioresistant microorganisms to survive high levels of radiation is primarily attributed to their DNA repair mechanisms and the production of protective metabolites. To determine the effect of irradiation on bacterial growth, we propose to compare the metabolites produced by the irradiated isolates to those of the control (non-irradiated isolates) using mass spectrometry, molecular networking, and chemometric analysis. We identified the secondary metabolites produced by these bacteria and observed variations in growth following irradiation. Notably, after 48h of exposure to radiation, Pantoea sp. bacterial cells exhibited a significant 6-log increase compared to non-irradiated cells. Non-irradiated cells produce exclusively Pyridindolol, 1-hydroxy-4-methylcarbostyril, N-alkyl, and N-2-alkoxyethyl diethanolamine, while 5'-methylthioadenosine was detected only in irradiated cells. These findings suggest that the metabolic profile of Pantoea sp. remained relatively stable. The results obtained from this study have the potential to facilitate the development of innovative strategies for harnessing the capabilities of endophytic bacteria in radiological protection and bioremediation of radionuclides.

Optimization of Radiation Protection for Companions in Pediatric Chest Radiography

Aims: The objective of this study is to optimize the positioning of the companion during pediatric chest radiographic exams by analyzing the scattered radiation dose measured with an ionization chamber. Place and Duration of Study: The experimental study was conducted between February 2024 and April 2024, in the radiodiagnosis laboratory belonging to the Medical Physics and Radiology Technology courses at the Franciscan University (UFN) in the city of Santa Maria, Rio Grande do Sul. Methodology: A fixed conventional X-ray device and a phantom (simulating object) filled with 15 cm of water to represent a pediatric chest were used. The parameters of voltage (kV) and the product of current and time (mA.s) were kept constant. Measurements of the air KERMA (KAIR) were performed by positioning the dosimetric system at four points around the phantom (0º, 90º, 180º, and 270º), simulating the exposure conditions of the companion. Results: The results showed that the lowest radiation dose received by the companion at the gonadal level occurred at 90º around the table (cathode side), while the lowest dose at the lens level was at 270º (anode side). The highest dose at the gonadal level was observed at 180º, and the highest dose at the lens level was at 90º. Conclusion: It was concluded that the companion should position themselves on the anode side (270º), as the lens does not have lead protection, while protection is available for the rest of the body. This recommendation aims to optimize radiological safety for the companion.

Comprehensive study for radiation shielding features for Bi2O3–B2O3–ZnO composite using computational radioanalytical Phy-X/PSD, MCNP5, and SRIM software

The current study uses zinc oxide doping nanoparticles to investigate the radiation shielding properties of bismuth borate glass. Fourier transform infrared (FTIR) and X-ray diffraction (XRD) examined the structural characteristics of the current samples. In contrast, the optical properties were determined based on the absorption spectrum for current samples. Appraisal studies are carried out depending on the simulation capabilities of Phy-X/PSD software in conjunction with MCNP5 to achieve this goal. In addition, the neutron and charged particle shielding properties were evaluated theoretically. All glasses are amorphous, as confirmed by the XRD data, and the FTIR data showed several vibration bands and functional groups. The density showed rising from 5.981 to 6.433 g/cm3 with adding ZnO. The band gap values reduced from 2.831 to 2.091 eV for direct and 3.024 to 2.218 eV for indirect with adding ZnO. The investigations' findings demonstrate a strong agreement between the theoretical and simulation-derived estimates of the mass attenuation coefficient. The relative difference of MAC results lie in the range 0.106–2.941% for BBZ0, 0.105–4.348% for BBZ1, 0.105–3.398% for BBZ2, and 0.105–2.032% for BBZ3. The study's findings are valuable insights from thoroughly examining these parameters, which can potentially improve the radiation protection abilities of Bi2O3–B2O3–ZnO glasses. This study represents a significant step in developing more efficient and safer materials for gamma radiation shielding applications.