This study aims to determine effective energy and scattered radiation distributions in an interventional cardiology department. Additionally, the protective effectiveness of ceiling-suspended shielding was investigated. Optically stimulated luminescence dosemeters were attached to mica rods to determine effective energy and scattered radiation at numerous points in the catheterization laboratory. The effective energy of the scattered beam ranged from 40 to 50keV, with the beam scattered to the eye position reaching an effective energy of 45keV. Radiation was distributed nonuniformly at different locations and heights. Ceiling-suspended shielding reduced the dose to the head and neck region but did not significantly affect other regions. The combination of a suitable standing position and ceiling-suspended shielding can notably diminish the staff's eye dose by >93%.

This study evaluated radiation dose to the eye lens and the shielding efficacy of a radiation-protective eye mask (E-Mask) during repeated chest and abdomen computed tomography (CT) scans. Dose measurements were obtained using an anthropomorphic phantom and an optically stimulated luminescence dosemeter (Model TOPAZ, LANDAUER, USA). A 5-y follow-up scenario for Hodgkin lymphoma was simulated by assuming one scan per quarter, with the single-scan dose multiplied by 20 to represent four scans annually over 5-y. Despite the use of low-dose protocols based on national diagnostic reference levels issued by the Korea Disease Control and Prevention Agency, unshielded cumulative lens doses reached 363.89mSv (right) and 424.84mSv (left). Using an E-Mask reduced these doses to 243.96mSv and 240.13mSv, corresponding to reductions of 32.96% and 43.48%, respectively. These findings support the use of the E-Mask in radiosensitive populations to reduce lens exposure during long-term CT follow-up.

The study investigated the maximum range of 90Sr-90Y sources in different shielding materials and assessed β-directional dose equivalent rates and γ ambient dose equivalent rates across varying thicknesses of shielding. Results indicated: (1) Significant differences in 90Sr-90Y source ranges among materials, with the shortest β-ray range observed in tungsten alloy (0.00 to 0.50mm) and high-purity lead (0.5 to 1.0mm). (2) Generally, there was good agreement between experimental and simulation data, except at a thickness of 0.5mm for high-purity lead, where a deviation of 51.4 per cent in β-directional dose rates was observed, likely due to errors in the lead cross-section data. (3) Comparative analysis demonstrated that combinations such as "304+W" or "304+Pb" offer enhanced shielding effectiveness against 90Sr-90Y sources. This study provides valuable insights for selecting β-radiation shielding materials and structures.

This study evaluates the dosimetric performance of GD-302M radiophotoluminescent glass dosemeters (RPLGDs) under high-energy X-rays (6-15MV) as a potential alternative to thermoluminescent dosemeters for radiotherapy audits in China. Key properties-dose linearity, uniformity, reproducibility, energy response, fading, build-up effects, and signal depletion-were systematically assessed using a medical linear accelerator under reference conditions. The results demonstrated excellent dose linearity (R2=0.9987, 1-4Gy), uniformity (coefficient of variation=0.9%), and reproducibility (standard deviation=0.42%). Energy-dependent variations remained within 1.3%, while fading effects showed a cumulative signal loss of 3% over 110d. Unpreheated RPLGDs retained 98% of preheated signals after 30d, with minimal signal depletion per readout (0.016%). A water-to-solid phantom conversion coefficient of 0.998 was established. The total experimental uncertainty was 2.4%. These findings validate RPLGDs as a stable, reproducible, and cost-effective tool for enhancing radiotherapy quality assurance in resource-constrained settings.

This study aimed to identify factors that increase radiation dose to computed tomography (CT) imaging assistants and to propose measures to minimize their effective dose, thereby improving radiation safety. Nine healthcare professionals (five intensivists and four radiological technologists) had their Hp(10) measured during 112 diagnostic CT procedures involving tasks categorized by proximity to the gantry: gantry proximal (e.g. bag-valve-mask (BVM) ventilation) and gantry distal (e.g. patient observation). Multiple regression analysis identified dose-length product (DLP) and tube current as significant predictors of effective dose of CT imaging assistants. The highest effective dose, 26μSv, occurred during gantry proximal tasks. Intensivists received higher effective doses (35μSv) than radiological technologists (19μSv) because the CT imaging procedures they assisted with had higher DLP values. To reduce the effective dose, it is recommended to implement low-dose imaging protocols, optimize imaging coverage, and use radiation protection clothing, such as lead aprons, which significantly reduce Hp(10).

In 1989, following a workplace conflict, a worker activated an industrial radiography generator exposing a colleague to a significant amount of ionizing radiation. To our knowledge, this is the only documented case where an X-ray machine was used to commit a criminal act. Since the incident, 35 years have passed. Using the scientific information gathered at the time, we have attempted to create the clearest possible picture of this event. Although scientific knowledge has advanced since then, the overall assessment remains unchanged. An important lesson to be drawn from this crime is the significance of taking early actions to identify the level of exposure and ensure timely intervention to minimize the consequences for the victim. Another takeaway from this event is the numerous challenges the worker faced in having his situation acknowledged by both law enforcement authorities and various government agencies, given the unique nature of the incident.

Exposure to Galactic Cosmic Rays (GCR) presents significant health risks to astronauts during long-duration deep space missions. Although existing studies have examined dose and particle energy spectra under GCR exposure scenarios, there is still a lack of studies covering various shielding quantities, especially regarding the self-shielding transmission characteristics of the human body. In this study, we used Monte Carlo simulations with the PHITS codes, coupled with the ICRP male reference phantom, to evaluate the performance of shielding materials against GCR. We comprehensively analyzed several physical quantities, including organ dose equivalent, absorbed dose, effective dose equivalent, and the flux and dose of secondary particles. Our findings analyzed the body's self-shielding effect and proton dose buildup effect. This study provides systematic data that offers valuable insights into astronaut safety during deep space exploration.

Abstract Water usually contains small quantities of radioactivity. The presence of significant levels of radioactivity in drinking water sources poses potential health risks to the public. Consequently, determining the concentrations of gross alpha and gross beta activity in water is essential for ensuring water safety. Thirteen commercially bottled mineral water samples were collected from Moroccan markets and analyzed using the Liquid Scintillation Counting technique, based on the ISO 11704:2018 method. The results show that the activity concentrations range from a minimum below the lower limit of detection to a maximum of 0.21 ± 0.02 and 0.15 ± 0.01 Bq·L−1 for gross alpha and gross beta, respectively. The concentrations of anions and cations are within recommended limits for drinking water. For each sample, the annual effective dose was calculated and lifetime cancer risks were estimated. The levels of the annual effective dose and lifetime cancer risk were all below the World Health Organization’s recommended values for drinking water quality. Highlights

The market share of pure electric vehicle (PEV) as a green transportation steadily increases as the global demand for renewable energy sources and environmentally friendly mobility continues to increase. However, during PEV operation, the inverter system, as the key power conversion device, generates strong electromagnetic field in the local space. Long-term exposure to such electromagnetic environments may have potential effects on human body. In this study, the electromagnetic environment model of the PEV body, human body and simplified inverter is established. The finite element software, COMSOL Multiphysics, is used to calculate and analyse the variations in the induction field in different tissues of the driver and rear passenger, caused by the electromagnetic field generated by the inverter system operating at maximum power. The electromagnetic exposure level of the driver and rear passenger is assessed. Results show significant differences in the electromagnetic exposure levels of different seating positions in the vehicles. The electromagnetic exposure level in the driver's body is higher than that of the rear passenger, but it does not exceed the exposure limits defined by the International Commission for Non-ionizing Radiation Protection. This finding effectively complements the study on evaluating the safety of the electromagnetic environment of PEV and improves public awareness.

Activity concentration of 238U and 232Th and their decay products are assessed in soil at three hydrocarbon zones to determine the baseline before further fracking studies. The range of activity concentration for the three zones was 238U (from 9.2±0.5 to 115.8±7.5) Bqkg-1, 228Ra (from 8.3±2.0 to 50.0±4.4) Bqkg-1 and 226Ra (from 24.1±2.3 to 86.8±4.7) Bqkg-1; which are comparable to the global average values reported by UNSCEAR in soil. Similar activity-concentration patterns for 238U decay series and 232Th decay series for the three zones indicate no previous industrial action. This baseline is useful to assess a possible enrichment of Naturally Occurring Radioactive Materials if industrial activities take place in the future.