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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]

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]

The risk of brain exposure to ionizing radiation increases gradually due to the extensive application of nuclear technology in medical, industrial, and aerospace fields. Radiation-induced brain injury (RBI) is highly likely to cause a wide range of neurological complications, including schizophrenia, Alzheimer's disease (AD), depression. Ginkgolide B (GB) is one of the effective active components extracted from ginkgo biloba leaves, exerts protective effects on CNS, which is involved in the regulation of the Hippo signaling pathway. MST1, as one of the core kinases of the Hippo pathway, participated in regulating cell proliferation, differentiation, and apoptosis. However, it remains unclear whether GB attenuates radiation brain injury (RBI) and whether the radioprotective effect of GB refers to MST1 signaling. Hence, our study aimed to explore the radiation protection effect and the potential mechanism of GB. C57BL/6 mice were stimulated with an X-ray (20 Gy) to establish an RBI model. Then, morris water maze test (MWM) and step-down passive avoidance test (SDPAT) were used to assess the learning and memory function of mice. The open field test (OFT), tail suspension test (TST), and forced swimming test (FST) were used to assess changes in locomotor activity and hopelessness. Besides, X-ray-stimulated SH-SY5Y cells were used to verify the radioprotective effect of GB. Immunofluorescence double staining, Dihydroethidium (DHE), western blot, and flow cytometry were used to explore the role of DCC/MST1 signaling in RBI. In this study, X-ray-treated mice exhibited cognitive impairment and depression-like behavior, which was ameliorated by GB treatment. GB also reduced the ROS production and the number of TUNEL-positive cells in the hippocampus. Moreover, GB increased the protein levels of p-AKT and Bcl2, while decreased the protein levels of MST1, p-p38, p-JNK, cleaved-caspase-3 and Bax both in vivo and in vitro. Additionally, exogenous Netrin-1 alleviated X-ray-induced ROS production and apoptosis, whereas knockout of Netrin-1 receptor DCC abolished the protective effect of GB. Oxidative stress and MST1-mediated neuronal apoptosis participated in radiation-induced cognitive impairment and depression-like behaviors, and modulation of DCC by GB was an effective intervention against RBI. [ABSTRACT FROM AUTHOR]

As the fifth-generation (5G) network is introduced in the millimetre-wave (mmWave) spectrum, and the widespread deployment of 5G standalone (SA) is approaching, it becomes essential to establish scientifically grounded exposure limits in the mmWave frequency band. To achieve this, conducting experiments at specific frequencies is crucial for obtaining reliable evidence of potential biological impacts. However, there is a literature gap where experimental research either does not utilise the mmWave high band (e.g., the 26 Gigahertz (GHz) band) or most studies mainly rely on computational approaches. Moreover, some experimental studies do not establish reproducible test environment and exposure systems. Addressing these gaps is vital for a comprehensive exploration of the biological implications associated with mmWave exposure. This study was designed to develop and implement a mmWave exposure system operating at 26 GHz. The step-by-step design and development of the system are explained. This specialised system was designed and implemented within an anechoic chamber to minimise external electromagnetic (EM) interference, creating a controlled and reproducible environment for experiments involving high-frequency EM fields. The exposure system features a 1 cm radiation spot size, enabling highly localised exposure for various biological studies. This configuration facilitates numerous dosimetry studies related to mmWave frequencies. [ABSTRACT FROM AUTHOR]

TRIPOLI-4® is a general-purpose Monte Carlo radiation transport code developed by the Service d'Études des Réacteurs et de Mathématiques Appliquées at CEA-Saclay. It uses continuous-energy nuclear data to simulate neutron, photon, electron, and positron transport in fields like radiation shielding, reactor physics, and nuclear criticality safety. To study radiation protection dosimetry in human tissues and organs, male and female adult computational phantoms from the Medical Internal Radiation Dose–Oak Ridge National Laboratory phantoms family and the International Commission on Radiological Protection (ICRP) publication 110 were recently modeled and calculated using the geometry options of TRIPOLI-4. To easily use the ICRP 110 voxel-based phantoms in different exposure scenarios, a newly developed phantom option is available in TRIPOLI-4 and its display tool T4G. This new phantom option is helpful for modeling one or more phantoms and for improving calculation performance in real irradiation environments. The 2020 published pediatric computational reference phantoms are accessible from ICRP publication 143. Male and female pediatric phantoms are also verified with the new T4G tool and TRIPOLI-4 code. This paper reports on recent works using TRIPOLI-4 on adult and pediatric computational phantoms. The modeling methods of stylized and voxel-based phantoms, the graphic displays of modeled phantoms with T4G, and the verification procedures for single-phantom and two-phantom application cases are presented. Validation for external and internal dosimetry calculations has been performed. Calculation results on organ dose S values for nuclear medicine applications are presented for single female and single male voxel phantoms using 131I and 177Lu radiation sources. Effective dose calculations for two-phantom cases using 99mTc and 18F sources are compared with traditional H*(10) calculations from nuclear medicine patient to patient caregiver. [ABSTRACT FROM AUTHOR]

Percutaneous nephrolithotomy confers the highest radiation to the urologist's hands compared to other urologic procedures. This study compares radiation exposure to the surgeon's hand and patient's body when utilizing three different techniques for needle insertion during renal access. Simulated percutaneous renal access was performed using a cadaveric patient and separate cadaveric forearm representing the surgeon's hand. Three different needle-holding techniques were compared: conventional glove (control), a radiation-attenuating glove, and a novel needle holder. Five 300-s fluoroscopy trials were performed per treatment arm. The primary outcome was radiation dose (mSv) to the surgeon's hand. The secondary outcome was radiation dose to the patient. One-way ANOVA and Tukey's B post-hoc tests were performed with p < 0.05 considered significant. Compared to the control (3.92 mSv), both the radiation-attenuating glove (2.48 mSv) and the needle holder (1.37 mSv) reduced hand radiation exposure (p < 0.001). The needle holder reduced hand radiation compared to the radiation-attenuating glove (p < 0.001). The radiation-attenuating glove resulted in greater radiation produced by the C-arm compared to the needle holder (83.49 vs 69.22 mGy; p = 0.019). Patient radiation exposure was significantly higher with the radiation-attenuating glove compared to the needle holder (8.43 vs 7.03 mSv; p = 0.027). Though radiation-attenuating gloves decreased hand radiation dose by 37%, this came at the price of a 3% increase in patient exposure. In contrast, the needle holder reduced exposure to both the surgeon's hand by 65% and the patient by 14%. Thus, a well-designed low-density needle holder could optimize radiation safety for both surgeon and patient. [ABSTRACT FROM AUTHOR]

Introduction: Cranial CT scans are associated with radiation exposure to the eye lens, which is a particularly radiosensitive organ. Children are more vulnerable to radiation than adults. Therefore, it is essential to use the available dose reduction techniques to minimize radiation exposure. According to the European Consensus on patient contact shielding by the IRCP from 2021, shielding is not recommended in most body areas anymore. This study aims to evaluate whether bismuth shielding as well as its combination with other dose-saving technologies could still be useful. Methods: Cranial CT scans of a pediatric anthropomorphic phantom were performed on two up-to-date MDCT scanners. Eye lens dose measurements were performed using thermoluminescent dosimeters. Furthermore, the impact of BS and of the additional placement of standoff foam between the patient and BS on image quality was also assessed. Results: Bismuth shielding showed a significant lens dose reduction in both CT scanners (GE: 41.50 ± 4.04%, p < 0.001; Siemens: 29.75 ± 6.55%, p = 0.00). When combined with AEC, the dose was lowered even more (GE: 60.75 ± 3.30%, p < 0.001; Siemens: 41.25 ± 8.02%, p = 0.00). The highest eye dose reduction was achieved using BS + AEC + OBTCM (GE: 71.25 ± 2.98%, p < 0.001; Siemens: 58.75 ± 5.85%, p < 0.001). BS caused increased image noise in the orbital region, which could be mitigated by foam placement. Eye shielding had no effect on the image noise in the cranium. Conclusions: The use of BS in cranial CT can lead to a significant dose reduction, which can be further enhanced by its combination with other modern dose reduction methods. BS causes increase in image noise in the orbital region but not in the cranium. The additional use of standoff foam reduces image noise in the orbital region. [ABSTRACT FROM AUTHOR]

This study aimed to estimate scattered radiation and its spatial distribution around three cone-beam computed tomography (CBCT) devices, in order to determine potential positions for an operator to stand if they needed to be inside the CBCT room. The following devices were tested: Morita Accuitomo (CBCT1), Newtom Giano HR (CBCT2), Newtom VGi (CBCT3). Scattered radiation measurements were performed using different kVp, mA, and Field of View (FOV) options. An anthropomorphic phantom (NATHANIA) was placed inside the X-ray gantry to simulate clinical conditions. Scattered measurements were taken with the Inovision model 451P Victoreen ionization chamber once placed at fixed distances from each irradiation isocenter, away from the primary beam. A statistically significant (p < 0.001) difference was found in the mean value of the scattered radiation estimations between the CBCT devices. Scattered radiation was reduced with a different rate for each CBCT device as distance was increased. For CBCT1 the reduction was 0.047 μGy, for CBCT2 it was 0.036 μGy, and for CBCT3 it was 0.079 μGy, for every one meter from the X-ray gantry. Therefore, at certain distances from the central X-ray, the scattered radiation was below the critical level of 1 mGy, which is defined by the radiation protection guidelines as the exposure radiation limit of the general population. Consequently, an operator could stay inside the room accompanying the patient being scanned, if necessary. [ABSTRACT FROM AUTHOR]

As radiology continues to grow in low- and middle-income countries (LMICs), radiation exposure and risk to patients and staff will concurrently increase. This study aims to assess the knowledge of radiation safety among medical staff in Tanzania. A survey was distributed to 350 staff members at a national referral hospital in Tanzania over a 7-month period (February–August 2021). This consisted of a structured questionnaire evaluating participants' knowledge and awareness ionizing radiation and radiation safety. Chi-square and Fisher's exact tests were used to determine the association between independent and dependent categorical variables. A total of 300 surveys were completed (86% response rate). Mean age was 31 and 53% of participants were female. The majority (89%) were clinical staff employed in direct patient care. Most reported having heard of radiation protection (85%) but only 61% reported receiving training in radiation protection. Regarding radiation knowledge, 73% correctly answered how to protect oneself from radiation and 74% knew which medical staff were at greater risk of radiation exposure. However, only 32% correctly answered which imaging tests emit more radiation and only 53% correctly answered which age group was at greatest risk of radiation effects. Non-clinical staff had a significantly lower radiation awareness than clinical staff, with 69.7% reporting having heard about radiation protection, compared to 88.3% of clinical staff (p = 0.004). Female participants were more knowledgeable of radiation risks in pregnancy (p = 0.002). More early career staff reported receiving radiation protection training (64.5%) compared to those with >5 years work experience (53.9%), though this difference was not statistically significant (p = 0.09). When stratifying radiation knowledge by high (score of 80–100%), moderate (60–79.9%) and low (<60%), 20% of participants scored high, 47% moderate, and 33% low. Most staff had low to moderate knowledge on radiation safety. Our findings highlight the importance of education on ionizing radiation as medical imaging continues to rise in Africa. • As radiology continues to grow in Africa, radiation exposure and risk to patients and staff will concurrently increase. • We assessed the awareness and knowledge of radiation safety among medical staff in the east African country of Tanzania. • 85% of study participants heard of radiation protection but only 61% reported receiving training in radiation protection. • Most (80%) of medical staff at our national referral hospital had only low to moderate knowledge of radiation safety. • Our results highlight the need for improved education on radiation saftey as radiology continues to grow globally. [ABSTRACT FROM AUTHOR]

Ionizing radiations are commonly used in interventional endoscopy, mainly during endoscopic retrograde cholangio-pancreatography (ERCP). These radiations are not without short-, medium- and long-term side effects for both endoscopists and patients. Various authorities have defined specific procedures to limit the risks to patients and health-care workers from exposure to ionizing radiation. These procedures are based on well-justified procedures, optimizing procedures and monitoring dosimetry. Training in patient and health-care worker protections is mandatory for doctors performing such procedures. This article expresses the current view of the French Society of Digestive Endoscopy (SFED) about radiation protection for endoscopic procedures. [ABSTRACT FROM AUTHOR]

Using the powder metallurgy, TiO 2 -doped TV screen glass ceramic samples were prepared with TiO 2 concentrations of 0 (S-TV), 10 (S-TV/Ti10), and 20 (S-TV/Ti20) wt%. The TV screen glass was collected from a damaged TV's CRT. The fabricated materials were investigated for their physical, structural, and radiation-shielding attributes. The chemical composition of the prepared glasses was analysed with the aid of the X-ray fluorescence (XRF) method. The crystalline phase and microstructure of the glass ceramics were studied through the X-ray diffraction (XRD) method and scanning electron microscope (SEM), respectively. The density and Vickers hardness of the sample were determined by the Archimedes method and a micro hardness tester, respectively. The absorption parameters of electrons, protons, alpha particles, carbon ions, fast neutrons, and thermal neutron were calculated from various software and analytic expressions. The XRD spectra of the samples showed the presence of distinct crystalline peaks associated with TiO 2 , SiO 2 , and Ba 2 SiO 4. The SEM images revealed that crystalline structures nucleated and increased with coarser crystalline grains when the amount of TiO 2 was increased. The densities of the glass ceramics were 2.525, 2.546, and 2.285 g/cm3 for the S-TV, S-TV/Ti10, and S-TV/Ti20 samples, respectively while the corresponding Vickers hardness values were 495, 540, and 578 HV. The projected range of electrons, protons, alpha particles, and heavy carbon ions were within the limits 2.78–32182.18 μm, 0.215–1400 μm, 0.154–130.54 μm, and 0.053–14.10 μm in S-TV, 2.76–31991.36 μm, 0.205–1320 μm, 0.147–122.05 μm, and 0.049–13.11 μm in S-TV/Ti10, and 2.84–32824.95 μm, 0.212–1360 μm, 0.151–125.55 μm, and 0.051–13.45 μm in S-TV/Ti20, respectively. Among the three samples, S-TV was the best thermal neutron absorber, while S-TV/Ti10 is most effective in slowing down fast neutrons. The optimum TiO 2 doping content for enhancing the charged particle and fast neutron moderating abilities of TV screens is 10 wt%. [ABSTRACT FROM AUTHOR]

Objectives: The objectives are to compare lead blood concentrations in veterinary workers using lead shielding with concentrations in a control population, to measure hand surface lead before and after use of shielding, and to compare hand surface lead with and without the use of disposable gloves worn under hand shielding. Methods: Blood and hand wipe samples were analyzed for lead using inductively coupled plasma mass spectrometry. Results: There was no difference in blood lead between exposed and control groups. After lead glove use, 69% (18/26) of hand surface lead samples from workers not using disposable gloves were greater than 500 μg, 42% (11/26) were greater than 1000 μg, and 12% (3/26) were greater than 2000 μg. Conclusions: If lead shielding use is unavoidable, disposable gloves should be worn, and skin should be decontaminated after use. [ABSTRACT FROM AUTHOR]

In radiology, radiation shielding is important for protection especially with diagnostic radiation, such as diagnostic X-ray, because radiation exposure can damage cellular DNA. Currently, lead is the most common radiation shielding but it poses environmental hazards due to its toxicity. This research aims to study a non-lead radiation shielding and to evaluate its effectiveness of radiation protection. We studied radiation absorption properties from primary and secondary radiations from shielding composed of silicone rubber and BaSO4 and Bi2O3 in different proportions. The results showed that the shielding material at 70% BaSO4 and Bi2O3 has the ability to reduce radiation doses from 120 kVp X-rays and has absorption properties of 90.19, 94.87% in primary and 92.72, 97.48% in secondary radiation. In addition, the silicone rubber shielding materials mixed with BaSO4 and Bi2O3 are environment-friendly, flexible and have great shielding performance in reducing diagnostic X-ray exposure. [ABSTRACT FROM AUTHOR]

Ionizing radiation (IR) is widely applied in radiotherapy for the treatment of over 50% of cancer patients. IR is also intensively used in medical diagnostics on a daily basis in imaging. Moreover, recent geopolitical events have re-ignited the real threat of the use of nuclear weapons. Medical radiation countermeasures represent one of the effective protection strategies against the effects of IR. The aim of this review was to summarize the most commonly used strategies and procedures in the development of radiation countermeasures and to evaluate the current state of their research, with a focus on those in the clinical trial phase. Clinical trials for this review were selected in accordance with the preferred reporting items for systematic reviews and meta-analyses (PRISMA) statement. The search was performed in the clinicaltrials.gov database as of May 2022. Our search returned 263 studies, which were screened and of which 25 were included in the review. 10 of these studies had been completed, 3 with promising results: KMRC011 increased G-CSF, IL-6, and neutrophil counts suggesting potential for the treatment of hematopoietic acute radiation syndrome (H-ARS); GC4419 reduced the number of patients with severe oral mucositis and its duration; the combination of enoxaparin, pentoxifylline, and ursodeoxycholic acid reduced the incidence of focal radiation-induced liver injury. The agents discovered so far show significant side effects or low efficacy, and hence most of the tested agents terminate in the early stages of development. In addition, the low profitability of this type of drug demotivates the private sector to invest in such research. To overcome this problem, there is a need to involve more public resources in funding. Among the technological opportunities, a deeper use of in silico approaches seems to be prospective. [ABSTRACT FROM AUTHOR]

• The TL dosimetry characteristics of BaSO 4 : Eu including reusability, response to varying heating rates, signal fading, dose response and order of kinetics were studied for low dose irradiations. • The optimal Eu doping concentration and heating rate were found to be 0.5 mol % and 5 K/s, respectively. • The TL reusability and fading rate were found to be only 1.2% and 0.14 % per day, respectively, demonstrating the promising dosimetric properties of the nanophosphor. Thermoluminescence (TL) dosimetry is used in radiation protection and for measuring absorbed dose to patients in diagnostic radiology and radiotherapy. The main aim of the study herein was to assess the TL properties of BaSO 4 : Eu nanophosphors following irradiation with low dose γ- and X-rays. BaSO 4 phosphors activated with various concentrations of Eu were prepared by the co-precipitation method. The highest radiation sensitivity was obtained for an Eu concentration of 0.5 mol%. The TL properties in terms of glow curve, heating rate, reusability, fading and order of kinetics were studied. Optimized BaSO 4 : Eu irradiated with doses from 1.25 to 50 mGy displayed a major TL peak at ≈ 220 °C and exhibited a linear response with absorbed dose. The reusability test was performed for ten consecutive irradiations, readings, and annealing cycles, and showed a slight decrease in TL after the first cycle after which it was stabilized. Signal fading measurements were performed for irradiated samples over 50 days, where a signal loss of about 0.14 % per day was observed. [ABSTRACT FROM AUTHOR]

Ionizing radiation is becoming increasingly prevalent in various applications on Earth and in space. This study evaluates the radiation shielding performance of five quaternary glass systems with different chemical compositions of 60SiO 2 -35Pb 3 O 4 -(5-x)ZnO-xWO 3 (0 ≤ x ≤ 5 mol%) using theoretical software and Monte Carlo simulations. The study calculates various shielding parameters, including attenuation coefficients, mean free path, half value layer, tenth value layer, effective atomic number, electron density, and build-up factors, for the photon energy range of 1 keV to 100 GeV. PZSW3 and PZSW5 show comparable attenuation coefficients at low and high energy levels, which are higher than the other selected samples. Additionally, PZSW5 has a neutron removal cross-section of 0.120 cm−1, slightly less than PZSW4's 0.122 cm−1 and greater than the other three samples. On average, PZSW5 (60SiO 2 -35Pb 3 O 4 -5WO 3) exhibits greater radiation attenuation than other samples and most of the compared 19 samples in terms of shielding parameters. The study also analyzes the trajectories of 10 5 photons in the system and finds that PZSW5 has the most effective radiation protection capability among the glass composites studied. [ABSTRACT FROM AUTHOR]

Scatter radiation from portable and pediatric X-rays could pose a risk to radiographers, nearby patients, and caretakers. We aim to evaluate the spatial scatter radiation distribution to the radiographers, nearby patients, and caretakers during common projections in portable and pediatric X-rays. We evaluated the three-dimensional scatter dose profiles of four and three commonly used portable and pediatric X-ray projections, respectively, by anthropomorphic phantoms and scatter probes. For portable X-ray, the AP abdomen had the highest scatter radiation dose recorded. Radiographer scatter radiation doses were 177 ± 8 nGy (longest cord extension) and 14 ± 0 nGy (hiding behind the portable X-ray machine). Nearby patient scatter radiation doses were 3323 ± 28 nGy (40 cm bed distance), 1785 ± 50 nGy (80 cm bed distance), and 580 ± 42 nGy (160 cm bed distance). The AP chest and abdomen had the highest scatter radiation dose in pediatric X-rays. Caretaker scatter radiation doses were 33 ± 1 nGy (50 cm height) and 659 ± 7 nGy (140 cm height). Although the estimated lens doses were all within safe levels, the use of shielding and caution on dose estimation by inverse square law is suggested to achieve the ALARA principle and dose optimization. [ABSTRACT FROM AUTHOR]

Due to the legal regulations radiation incidents in nuclear or medical/industrial facilities are rare events. Radiation incidents are much more common in the context of road traffic accidents when sources of radiation are being transported. The handling of radiation victims is accompanied by strong feelings of fear and anxiety due to the rarity of such events and the physical characteristics of radioactive irradiation. This cannot be detected by human senses and the effects are not immediately visible. The risk and threat of radiation for rescue personnel and in hospitals can be overcome by a solid basic knowledge and by following some simple rules. This continuing medical education article imparts the necessary principles and based on an algorithm demonstrates the safe approach at the scene of the accident and the handling and transfer of the patient to the hospital. Moreover, it highlights further services and support by regional radiation protection centers. [ABSTRACT FROM AUTHOR]

UV radiation is used for sterilization but has adverse health effects in humans. UV-A radiation has lower antimicrobial effect than UV-B and UV-C but constitutes a lower health risk, opening up the possibility to sanitize environments with human presence in controlled exposure conditions. We investigated this possibility by identifying safe exposure conditions to a UV-A lamp along with efficient sanitization of the environment. The human exposure limits were calculated following the guidelines provided by the International Commission on Non-Ionizing Radiation Protection and the International Commission on Illumination. Antibacterial activity was evaluated on Escherichia coli, Pseudomonas aeruginosa and Staphylococcus aureus. The maximum human exposure duration has been identified at different irradiation distance and angle, increasing with the increase of both parameters. Bactericidal activity was observed in all microorganisms and was higher with higher exposure time and at lower distance from the source. Noteworthily, in equal conditions of radiant exposure, the exposure time impacts on the bactericidal activity more than the distance from the source. The modulation of factors such as distance from the source, exposure time and irradiation angle can enable effective antibacterial activity and human safety. Prolonged direct irradiation of the surfaces associated with indirect human exposure represents the condition of greater efficacy and safety. [ABSTRACT FROM AUTHOR]

The increasing utilisation of computed tomography (CT) in the medical field has raised a greater concern regarding the radiation-induced health effects as CT imposes high radiation risks on the exposed individual. Adherence to radiation protection measures in CT as endorsed by regulatory bodies; justification, optimisation and dose limit, is essential to minimise radiation risks. Islam values every human being and Maqasid al-Shari'ah helps to protect human beings through its sacred principles which aim to fulfil human beings' benefits (maslahah) and prevent mischief (mafsadah). Alignment of the concept of radiation protection in CT within the framework of al-Dharuriyat; protection of faith or religion (din), protection of life (nafs), protection of lineage (nasl), protection of intellect ('aql) and protection of property (mal) is essential. This strengthens the concept and practices of radiation protection in CT among radiology personnel, particularly Muslim radiographers. The alignment provides supplementary knowledge towards the integration of knowledge fields between Islamic worldview and radiation protection in medical imaging, particularly in CT. This paper is hoped to set a benchmark for future studies on the integration of knowledge between the Islamic worldview and radiation protection in medical imaging in terms of other classifications of Maqasid al-Shari'ah; al-Hajiyat and al-Tahsiniyat. [ABSTRACT FROM AUTHOR]

BACKGROUND: Radiological technologists serve as risk communicators who aim to lessen patients' anxiety about radiation exposure, in addition to performing radiological examinations. OBJECTIVE: We conducted a fact-finding survey on knowledge and awareness of radiation disasters among the radiological technologists to reveal their literacy and competencies regarding radiation disasters. METHODS: A paper questionnaire was distributed to 1,835 radiological technologists at 166 National Hospital Organization facilities in Japan. The 28-item questionnaire covered knowledge and awareness of radiation protection and radiation disasters. Radiological technologists were divided into 2 groups by regionality: areas where a nuclear power station was present/nearby (NPS areas) and non-NPS areas. RESULTS: Completed questionnaires were returned from 148 facilities with a facility response rate of 89.2% and from 1,391 radiological technologists with a response rate of 75.8%. There were 1,290 valid responses with a valid response rate of 70.3%. The correct answer rate for knowledge of radiation protection and radiation disasters was high in the 24 NPS areas. There were no differences in awareness of radiation disasters between NPS and non-NPS areas. CONCLUSIONS: Establishing a nationwide, region-independent training system can be expected to improve literacy regarding radiation disasters among radiological technologists. Willingness to assist during disasters was high among radiological technologists irrespective of area, indicating that the competencies of radiological technologists represent a competency model for radiation disaster assistance. [ABSTRACT FROM AUTHOR]

BACKGROUND: Radiological technologists serve as risk communicators who aim to lessen patients' anxiety about radiation exposure, in addition to performing radiological examinations. OBJECTIVE: We conducted a fact-finding survey on knowledge and awareness of radiation disasters among the radiological technologists to reveal their literacy and competencies regarding radiation disasters. METHODS: A paper questionnaire was distributed to 1,835 radiological technologists at 166 National Hospital Organization facilities in Japan. The 28-item questionnaire covered knowledge and awareness of radiation protection and radiation disasters. Radiological technologists were divided into 2 groups by regionality: areas where a nuclear power station was present/nearby (NPS areas) and non-NPS areas. RESULTS: Completed questionnaires were returned from 148 facilities with a facility response rate of 89.2% and from 1,391 radiological technologists with a response rate of 75.8%. There were 1,290 valid responses with a valid response rate of 70.3%. The correct answer rate for knowledge of radiation protection and radiation disasters was high in the 24 NPS areas. There were no differences in awareness of radiation disasters between NPS and non-NPS areas. CONCLUSIONS: Establishing a nationwide, region-independent training system can be expected to improve literacy regarding radiation disasters among radiological technologists. Willingness to assist during disasters was high among radiological technologists irrespective of area, indicating that the competencies of radiological technologists represent a competency model for radiation disaster assistance. [ABSTRACT FROM AUTHOR]

INTRODUCTION: Medical imaging involving ionizing radiation is common in the clinical setting. Little is known about the level of radiation safety training for medical trainees and attending physicians. We sought to identify the level of radiation safety knowledge and training at the undergraduate, postgraduate, and attending physician level. METHODS: A 29-question survey was sent by email to two sites in Canada. We pooled the results of medical students, residents, and attending physicians. The primary outcome was to describe the amount of radiation safety training among these groups. The secondary outcomes were to describe the frequency of radiation exposure, level of radiation knowledge, and preferred training method for radiation safety. RESULTS: Of 115 surveys that were properly completed, 31 (26.9%) medical students, 17 (14.7%) residents, and 67 (58.3%) attending physicians responded. A greater number of medical students (41.9%) reported they had zero hours of training time for radiation safety compared to attending physicians (14.9%) (p<0.05). A higher number of attending physicians (47.8%) and residents (64.7%) participated in patient care involving fluoroscopy daily or at least several times per week compared to medical students (3.2%) (p<0.001). Attending physicians had the greatest number of correct responses to radiation safety questions. Online courses and workshops were the preferred training methods. CONCLUSIONS: Radiation safety training is an important component of medical education for medical trainees and attending physicians. Current radiation safety training requirements and procedures at various levels of medical training in Canada should be addressed. Implementing radiation safety education may improve adherence to the radiation safety principles. [ABSTRACT FROM AUTHOR]

Mobile radiography allows for the diagnostic imaging of patients who cannot move to the X-ray examination room. Therefore, mobile X-ray equipment is useful for patients who have difficulty with movement. However, staff are exposed to scattered radiation from the patient, and they can receive potentially harmful radiation doses during radiography. We estimated occupational exposure during mobile radiography using phantom measurements. Scattered radiation distribution during mobile radiography was investigated using a radiation survey meter. The efficacy of radiation-reducing methods for mobile radiography was also evaluated. The dose decreased as the distance from the X-ray center increased. When the distance was more than 150 cm, the dose decreased to less than 1 μSv. It is extremely important for radiological technologists (RTs) to maintain a sufficient distance from the patient to reduce radiation exposure. The spatial dose at eye-lens height increases when the bed height is high, and when the RT is short in stature and abdominal imaging is performed. Maintaining sufficient distance from the patient is also particularly effective in limiting radiation exposure of the eye lens. Our results suggest that the doses of radiation received by staff during mobile radiography are not significant when appropriate radiation protection is used. To reduce exposure, it is important to maintain a sufficient distance from the patient. Therefore, RTs should bear this is mind during mobile radiography. [ABSTRACT FROM AUTHOR]

We report the physical, optical and nuclear radiation attenuation behaviours of tellurite–germanate (TeO 2 –GeO 2 –PbO) glasses reinforced with varying amounts of Eu 2 O 3. The samples were synthesised using the conventional melt-quenching method and had the following composition (in wt.%): 33.34TeO2 - 33.33GeO 2 - 33.33PbO (TGP). Different concentrations of Eu2O3 (in wt.%) were added to the glass composition, labelled TGP1, TGP2 and TGP3. The physical, optical and nuclear radiation attenuation properties were measured using both experimental and theoretical methods. At room temperature, the visible to near-infrared optical absorption spectrum ranged from 400 to 900 nm. The TGP1 sample with 1 wt% The Eu2O3 additive exhibited the lowest absorbance and the highest transparency. The TGP1 sample also exhibited the highest nuclear radiation absorption properties. The gamma-ray absorption capabilities of TGP1 were demonstrably superior to those of various types of glass shields and other old- and new-generation concrete-shielding materials. Thus, adding 1 wt% Eu 2 O 3 to tellurite–germanate glasses would 'improve nuclear radiation absorption and optical properties. It can also be concluded that expanded scientific community investigations in this area would be a significant step toward gaining a deeper understanding of these glass structures and determining what other optimisation tasks the addition of 1 wt% Eu 2 O 3 can accomplish. [ABSTRACT FROM AUTHOR]

This paper is aimed at estimating Radio Frequency (RF) radiation absorbed by humans around Base Transceiver Stations (BTS) within Kaduna metropolis. RF radiation absorbed by humans from forty two (42) selected (BTS) tagged M1 to M42 of the four major network providers (MTN, 9mobile, Airtel and Globacom) within Kaduna metropolis, Kaduna State, Nigeria within radial distance intervals of 20 m to 100 m from the foot of each BTS were estimated. The Average Power Density (PDAve) and Specific Absorption Rate of data obtained from these BTS were computed, and the results indicated that the average amount of SAR for the selected forty two (42) base transceiver BTS facilities were within the range of 16.9 - 331.7 × 10-9 W/kg and 0.648-10.659 × 10-6 W/m² respectively. These values are lower than the recommended limit by International Commission on Non Ionization Radiation Protection (ICNIRP) which is 0.08 W/kg for the human body. This study has shown that RF radiation absorbed by people either residing or transiting the study area has negligible effect on their health. [ABSTRACT FROM AUTHOR]

The purpose of this study is to show the actual recommendations for dose management and provide an overview of the available options for dose tracking and dose optimization. The legal institutions that supervise the radiological exposure of patients and their most important directives are presented. A literature review of existing diagnostic reference levels for computed tomography (CT), interventional radiology, radiography, paediatric radiography, mammography, and fluoroscopy in Europe and Poland was carried out. It has been shown that, in Poland, it is necessary to verify and determine the new diagnostic reference levels (DRLs) for each imaging modality because the existing ones are adapted from other countries and are not determined on the basis of data from Polish hospitals. They have not been updated for 11-17 years, although it is recommended to update them every 3-5 years. Many countries in Europe have already determined DRLs based on the analysis of their own dosage data (e.g. Austria and Germany). Analysing the existing DRLs for CT in Poland, it was noticed that they concern only a single anatomical region. It is necessary to determine the DRLs for multi-region CT (i.e. chest-abdomen-pelvis and neck-chest-abdomen-pelvis) examinations because these examinations account for about 60% of all oncological CT examinations-based on data collected from The Maria Sklodowska-Curie National Research Institute of Oncology in Warsaw. [ABSTRACT FROM AUTHOR]

The Adverse Outcome Pathway (AOP) framework, a systematic tool that can link available mechanistic data with phenotypic outcomes of relevance to regulatory decision-making, is being explored in areas related to radiation risk assessment. To examine the challenges including the use of AOPs to support the radiation protection community, an international horizon-style exercise was initiated through the Organisation for Economic Co-operation and Development Nuclear Energy Agency High-Level Group on Low Dose Research Radiation/Chemical AOP Joint Topical Group. The objective of the HSE was to facilitate the collection of ideas from a range of experts, to short-list a set of priority research questions that could, if answered, improve the description of the radiation dose-response relationship for low dose/dose-rate exposures, as well as reduce uncertainties in estimating the risk of developing adverse health outcomes following such exposures. The HSE was guided by an international steering committee of radiation risk experts. In the first phase, research questions were solicited on areas that can be supported by the AOP framework, or challenges on the use of AOPs in radiation risk assessment. In the second phase, questions received were refined and sorted by the SC using a best-worst scaling method. During a virtual 3-day workshop, the list of questions was further narrowed. In the third phase, an international survey of the broader radiation protection community led to an orderly ranking of the top questions. Of the 271 questions solicited, 254 were accepted and categorized into 9 themes. These were further refined to the top 25 prioritized questions. Among these, the higher ranked questions will be considered as 'important' to drive future initiatives in the low dose radiation protection community. These included questions on the ability of AOPs to delineate responses across different levels of biological organization, and how AOPs could be applied to address research questions on radiation quality, doses or dose-rates, exposure time patterns and deliveries, and uncertainties in low dose/dose-rate effects. A better understanding of these concepts is required to support the use of the AOP framework in radiation risk assessment. Through dissemination of these results and considerations on next steps, the JTG will address select priority questions to advance the development and use of AOPs in the radiation protection community. The major themes observed will be discussed in the context of their relevance to areas of research that support the system of radiation protection. [ABSTRACT FROM AUTHOR]

The concept of the adverse outcome pathway (AOP) has recently gained significant attention as to its potential for incorporation of mechanistic biological information into the assessment of adverse health outcomes following ionizing radiation (IR) exposure. This work is an account of the activities of an international expert group formed specifically to develop an AOP for IR-induced leukemia. Group discussions were held during dedicated sessions at the international AOP workshop jointly organized by the MELODI (Multidisciplinary European Low Dose Initiative) and the ALLIANCE (European Radioecology Alliance) associations to consolidate knowledge into a number of biological key events causally linked by key event relationships and connecting a molecular initiating event with the adverse outcome. Further knowledge review to generate a weight of evidence support for the Key Event Relationships (KERs) was undertaken using a systematic review approach. An AOP for IR-induced acute myeloid leukemia was proposed and submitted for review to the OECD-curated AOP-wiki (aopwiki.org). The systematic review identified over 500 studies that link IR, as a stressor, to leukemia, as an adverse outcome. Knowledge gap identification, although requiring a substantial effort via systematic review of literature, appears to be one of the major added values of the AOP concept. Further work, both within this leukemia AOP working group and other similar working groups, is warranted and is anticipated to produce highly demanded products for the radiation protection research community. [ABSTRACT FROM AUTHOR]

Radiation induces deterioration to life, the environment and electronic gadgets. Also, the escalating quests in use of radioactive entities has induced increased radioactive hazards resulting in the need to fabricate advanced materials for efficient protection against the deteriorating effects of radiation. Inclusive of differing techniques to achieve radiation attenuation, the use of compounds exhibiting elevated atomic number (Z), including lead, has been attained. On the other hand, lead exhibit toxicity. Therefore, varying researches have investigated the use of minimally-toxic post-transitionally metallic-oriented compounds, such as bismuth. However, polymeric materials offer great prospects attributable to their inherent electrical, mechanical, thermal, as well as multi-functional dispositions. However, composites fabricated from polymers with elevated atomic number reinforcements facilitate attainment of materials exhibiting minimal weight, good flexibility, and exceptional processability. Therefore, this paper elucidates emerging advancements in synthesization of polymeric materials and nanoarchitectures for radiation protection, focusing on application of polymeric nanoarchitectures for attenuation of varying forms of radiation. [ABSTRACT FROM AUTHOR]

Ionizing radiation has enough energy to damage DNA and increase human risk of developing cancer. Radiation protection must be assured to all the people of the hospital, from the employing authority to the workers carrying out radiological procedures. This work aims to evaluate the radiation safety in diagnostic procedures using X-ray, in Mekelle city, in the case of governmental and non-governmental hospitals. All the data are collected by observation and interviewing the staff members of each facility, measuring the dose rate at the controlled and supervised areas, the outputs and leakage of the X-ray machines. The collected data are evaluated both qualitatively and quantitatively. The result shows that 25.9 % of the radiation workers are females, and 74.1 % of them are males. As concerns the educational background, 37 % of the workers are bachelor degree holders, and 63 % are possessors of university diplomas. Thermoluminescence dosimeters (TLD) produce a file on the procedures being practiced for the assessment of personal doses. A need for such a file has also been touched to ensure the uniformity in processing of dosimeters, recording and reporting of doses by different TLD. It was noticed that there is a problem in using the existing protective devices during the radiotherapy practice. To improve the radiation safety procedure, the lifetime of the X-ray machine has to be limited. Also, it is necessary to adjust the maintenance and service shop to control the X-ray machine. At the same time, the radiation workers must permanently update their knowledge and skills. [ABSTRACT FROM AUTHOR]

For more than two years, coronavirus disease 19 (COVID-19) has represented a threat to global health and lifestyles. Computed tomography (CT) imaging provides useful information in patients with COVID-19 pneumonia. However, this diagnostic modality is based on exposure to ionizing radiation, which is associated with an increased risk of radiation-induced cancer. In this study, we evaluated the common dose descriptors, CTDIvol and DLP, for 1180 adult patients. This data was used to estimate the effective dose, and risk of exposure-induced death (REID). Awareness of the extensive use of CT as a diagnostic tool in the management of COVID-19 during the pandemic is vital for the evaluation of radiation exposure parameters, dose reduction methods development and radiation protection. [ABSTRACT FROM AUTHOR]

[Display omitted] • β-Ca 2 SiO 4 :Nd3+ phosphors were synthesized using agro-waste products. • TDPL investigations reveal outstanding thermal stability, with the emission intensity remaining at 92.7 % even at 423 K. • Thermoluminescence (TL) glow curves derived from samples exposed to beta radiation displayed three discernible peaks at temperatures of 95 °C, 147 °C and 194 °C. • TL experiments furnish empirical evidence affirming the potential suitability of β-Ca 2 SiO 4 :5Nd3+ as a phosphor for dosimetry applications. A series of Nd3+ doped β-Ca 2 SiO 4 (β-CSO:Nd3+) phosphors are synthesized using the solid-state reaction method, employing agricultural waste from egg shells and bamboo leaves as the source materials. XRD analysis confirmed the monoclinic structure of the resulting phosphors. The photoluminescence (PL) emission spectra display the distinct emission peaks associated with Nd3+ ions. Optimization of the Nd3+ ions concentration is carried out, revealing that 5 mol % yielded the highest intensity (β-CSO:5Nd3+). Further increases in concentration led to a reduction in emission intensity attributed to concentration quenching (CQ). The phosphors excitation spectra are characterized by a wide range, spanning from 450 to 900 nm. When excited at 581 nm, the phosphor emitted strong infrared light at 1053 nm, attributed to transitions of Nd3+ ions, specifically 4F 3/2 → 4I 9/2 , 4F 3/2 → 4I 11/2 , and 4F 3/2 → 4I 13/2. The near-infrared (NIR) down conversion emissions exhibited by the material suggest exciting prospects for leveraging the synthesized phosphors in the development of photonic devices engineered to emit within the NIR spectrum. The investigation of temperature-dependent photoluminescence (TDPL) within the range of 303–483 K revealed that emissions at elevated temperatures are significantly more intense compared to those observed at room temperature. TDPL investigations reveal outstanding thermal stability, with the emission intensity remaining at 92.7 % even at 423 K. Moreover, the phosphor demonstrates promising potential for temperature sensing applications, supported by its absolute sensitivity of 1.4 × 10−3 K−1 and relative sensitivity value of 0.14 % K−1. The Thermoluminescence (TL) glow curves derived from samples exposed to beta radiation displayed three discernible peaks at temperatures of 95 °C, 147 °C, and 194 °C. Moreover, the signal intensity exhibited a proportional augmentation corresponding to the escalation in irradiation dose, spanning from 1.58 to 100.86 Gy. The observed repeatability and fading signal trends in TL experiments furnish empirical evidence affirming the potential suitability of β-CSO:5Nd3+ as a phosphor for dosimetry applications. [ABSTRACT FROM AUTHOR]

This study investigates the effects of La 2 O 3 on the mechanical, thermal, and physical characteristics and the ability of bismuth germinate glass with different compositions to protect against radiation. The glasses included ZnO, Na 2 O, Bi 2 O 3 , GeO 2 , and different concentrations of La 2 O 3 (between 0 and 20 mol%). The glass density substantially increased from 3428 kg/m³ to 4412 kg/m³ as the concentration of La 2 O 3 increased. This observation underscores the considerable influence of La 2 O 3 on densification, which can be attributed to its higher coordination number and molecular weight. In addition, bridging oxygen atoms reduced the molar volume from 60.2 to 57.8 × 10−6 m3. This decrease suggests the synthesis of oxygen atoms, which increase the glass transition temperature from 536 to 573 K, improving the glass's thermal properties under investigation. As the amount of La 2 O 3 increased, the ultrasonic velocity measurements indicated an increase in longitudinal and shear velocities from 3192 to 3611 m/s and 1884–2185 m/s, respectively. Longitudinal and shear ultrasonic velocity measurements can be utilized to determine the elastic moduli, Poisson's ratio, and Debye temperature. Correlations between these results and theoretical models highlighted the strengthening effect of La 2 O 3 on the glass structure. Another important study area was radiation shielding efficiency, which showed that higher La 2 O 3 content improved photon blocking. The study showed the potential of La 2 O 3 -enriched glasses in applications needing radiation protection by looking at the effective atomic number and neutron shielding. Overall, adding La 2 O 3 strengthens the characteristics of bismuth-germinate glasses, increasing their suitability for certain applications in radiation-exposed areas. • La2O3-doped bismuth-germanate glasses synthesized. • Improved mechanical and shielding properties. • Empirical and theoretical validations were conducted. • Outperforms heavy-weight concrete in shielding. [ABSTRACT FROM AUTHOR]

Using cadmium-modified iron lead borate glasses with formula 30 B 2 O 3 – 40 PbO – 10 Na 2 O – (20 -x) Fe 2 O 3 – x CdO where x ranges from 0 to 20 mol%, this work aims to investigate the structural, physical, elastic, and radiation-shielding properties of practical economic radiation shields. The X-ray diffraction patterns confirm the amorphous nature of the samples. The results of Fourier-transform infrared spectroscopy (FTIR) demonstrate the formation of robust B–O–Cd linkages and diborocadmium ([B 2 CdO 8 ]2−) structures, as well as the conversion from [BO 3 ] to [BO 4 ] structural units with increased CdO and the presence of PbO and Na 2 O as modifiers. The CdO function also plays a dual role as a former and as a modifier. The FTIR analysis showed that the material's elasticity and the CdO oxide concentration were directly correlated, suggesting that the glass system becomes stiffer as the CdO concentration increases. The study explores the effectiveness of radiation shielding and demonstrates that CdO-rich samples have higher effective atomic numbers and attenuation qualities. • CdO enhances glass structure, elasticity, and protection. • 20% CdO: Ideal for gamma radiation protection. • CdO-enhanced glasses excel in shielding assessments. • Research benefits: extensive utilization in the field of radiation safety. [ABSTRACT FROM AUTHOR]

This paper presents the various side effects of radiation including tumor cure probability (TCP) accompanied with frequently severe but transient acute side effects in the surrounding normal (mainly epithelial) tissues and also the risk of late side effects in normal organs, confined to their partial or whole volumes. Besides the local side effects, unexpected exposure to low radiation doses results in the stochastic risk of mutagenic, teratogenic or cancerogenic side effects. In order to minimize the risk of various radiation side effects, some obligatory radiation protection constraints should be restrictively fulfilled. [ABSTRACT FROM AUTHOR]

The radiation emitted during radiological examinations can be harmful to the human body, but the technique is still used because it is helpful to the patient. Therefore, radiologic examinations must follow radiation protection principles such as justification and optimization, and only minimal required re-examinations should be performed. Proper use of radiation in the medical field can be achieved by proper education of individuals from multiple medical fields. [ABSTRACT FROM AUTHOR]

Patients can require imaging for several reasons. Many are for something other than annual checkups, and this can cause undue stress or fear of radiation. For parents, caregivers, and patients alike, understanding the basics of radiation and how to stay safe and get the imaging exams needed can be daunting. The information provided here will help patients and their caregivers understand the benefits and risks of radiation, and inform them not only about how radiation works, but also where and how they may encounter radiation. [ABSTRACT FROM AUTHOR]

The importance of the optimization principle implementation in ensuring the radiation protection of NPP personnel was emphasized. The potential of route optimization in reducing the dose load of the personnel of nuclear power plants and other nuclear facilities is shown. The paper considers the main directions of the authors' development of the theory and algorithms of route optimization of work in inhomogeneous radiation fields during maintenance, repair, modernization, dismantling of NPP equipment, and elimination of the radiation accident consequences. The results of the computational experiments that were carried out with the "Uran" supercomputer of the IMM UB RAS for the checking of the developed algorithms are presented. The article provides an overview of the developed methods of route optimization of work using the dynamic programming method, including consideration of the constraints in the form of precedence conditions, which means the requirement to perform certain tasks only after the completion of others. Dijkstra's method was used to solve the "dosimetrist's problem", where the optimal route for the dosimetrist's movement is being constructed, including obstacles bypassing and visiting specified points in the room where it is necessary to perform work to determine the radiation environment characteristics such as measuring the radiation dose rate, taking samples, etc. The routing of movements with the non-additive aggregation of costs is considered. The content of the problem is shown on the example of the radiation accident consequences eliminating on a locality, where, as a result of radioactive fragments scattering, a system of emitting elements appears, which must be deactivated, i.e., dismantled or screened. This task must be carried out in consecutive cycles with a definite threshold level of personnel exposure per shift. A characteristic feature is the dependence of cost functions (here, dosimetric cost) on the list of tasks: only sources that have not been dismantled yet continue emitting at the moment. Precedence conditions are also possible. [ABSTRACT FROM AUTHOR]

Crucially, some of the few studies that used an ecosystem level approach by analyzing leaf litter decomposition (an ecosystem function) also reported divergent conclusions (Mousseau et al. [35]; Bonzom et al. [2]), strengthening the need to better unravel ecosystem level impacts. But the same low doses would be capable of triggering perturbation at multispecies ecosystem level, especially when the ecosystem is poorly resilient (as would result from permanent long-term exposure to low doses of contaminants). Keywords: Ecosystems; environment protection; ecological risk assessment; radiation EN Ecosystems environment protection ecological risk assessment radiation 999 1007 9 06/13/22 20220601 NES 220601 1. Tackling assessment of ecosystem condition in relation to stressors requires to integrate toxicological knowledge together with ecosystem understanding, such as to be able to derive how ecosystem structure and functions can be best protected from degradation triggered by stressors. [Extracted from the article]

Emerging molecular and precision medicine makes nuclear medicine a de facto choice of imaging, especially in the era of target-oriented medical care. Nuclear medicine is minimally invasive, four-dimensional (space and time or dynamic space), and functional imaging using radioactive biochemical tracers in evaluating human diseases on an anatomically configured image. Many radiopharmaceuticals are also used in therapies. However, there have been concerns over the emission of radiation from the radionuclides, resulting in wrongly neglecting the potential benefits against little or any risks at all of imaging to the patients. The sound concepts of radiation and radiation protection are critical for promoting the optimal use of radiopharmaceuticals to patients, and alleviating concerns from caregivers, nuclear medicine staff, medical colleagues, and the public alike. [ABSTRACT FROM AUTHOR]

Background and Aims: Exposure to ionising radiation to Anaesthesiology consultants, residents, technicians and nurses (Anaesthesiology personnel) is steadily increasing as a consequence of growing usage of imaging technology for diagnostic and therapeutic purposes. We conducted a questionnaire-based survey of Anaesthesiology professionals (consultants, residents, technicians and nursing staff) working in three major tertiary care medical institutes in northern India regarding the existing knowledge, attitudes and practices of radiation safety at their workplaces. Methods: A printed and validated 30-point questionnaire was distributed. Questions were graded into the domains of demographics (6 questions), knowledge (9 questions), attitude (4 questions) and practice (11 questions). Data obtained from the responses was collated and analysed statistically Results: Out of the 403 questionnaires distributed, 222 were returned completed (55%). Majority of the respondents were residents (53.60%) and males (57.20%). Many were unaware of the principle of As Low As Reasonably Achievable (ALARA), (70.7%) regarding collimators (65.85%) and their usage (41.9%). Maximum respondents stressed on the necessity of knowing the exposure dosage of radiations (89.2%) and were concerned regarding the same (87.8%). Lead apron was the commonest protection equipment and 97.3% of them were not using dosimeters. Highest levels of knowledge, attitude, and practices were demonstrated by the consultants. In terms of practices, the technicians fared better than the residents. Conclusion: Knowledge, attitude and practices regarding radiation protection issues and doses of radiological procedures is limited. Although all the cadres scored high on their attitude scores, the practice sector requires improvement. [ABSTRACT FROM AUTHOR]

Background Radiographers have used social media networks for education, research, professional development and other purposes. However, in Saudi Arabia, there are no studies on the use of social media by radiographers. Therefore, the objective of this research was to evaluate the use of social media for the improvement of radiation safety knowledge among Saudi Arabian radiographers. Methods A questionnaire was designed to collect the data from Saudi Arabian radiographers. The questionnaire was created using Google Forms and was sent to 530 radiographers using WhatsApp. In total, 159 participants completed and returned the questionnaire through WhatsApp. The response rate was 30%. Basic descriptive statistics were employed to analyse the data. Results Most of the participants (79.9%) thought that social media could be used as a tool for the improvement of radiation safety knowledge. Also, almost half of participants (49.7%) employed social media when they needed to obtain information about radiation protection. Similarly, a majority of respondents (69.2%) used social media when they required information related to radiation safety. In addition, 81.7% of participants observed on video the existing information on radiation safety. Also, 71.7% of them were disposed to expand the use of social media to obtain information for radiation protection in their professional activities. Conclusion The results indicate that social media can help to improve radiation safety knowledge among Saudi Arabian radiographers. Consequently, participants were willing to increase the use of these tools in their professional work. [ABSTRACT FROM AUTHOR]

Background: In the assessment of diseases causing skeletal lesions such as multiple myeloma (MM), whole-body low-dose computed tomography (WBLDCT) is a sensitive diagnostic imaging modality, which has the potential to replace the conventional radiographic survey. Purpose: To optimize radiation protection and examine radiation exposure, and effective and organ doses of WBLDCT using different modern dual-source CT (DSCT) devices, and to establish local diagnostic reference levels (DRL). Material and Methods: In this retrospective study, 281 WBLDCT scans of 232 patients performed between January 2017 and April 2020 either on a second- (A) or third-generation (B) DSCT device could be included. Radiation exposure indices and organ and effective doses were calculated using a commercially available automated dose-tracking software based on Monte-Carlo simulation techniques. Results: The radiation exposure indices and effective doses were distributed as follows (median, interquartile range): (A) second-generation DSCT: volume-weighted CT dose index (CTDIvol) 1.78 mGy (1.47–2.17 mGy); dose length product (DLP) 282.8 mGy·cm (224.6–319.4 mGy·cm), effective dose (ED) 1.87 mSv (1.61–2.17 mSv) and (B) third-generation DSCT: CTDIvol 0.56 mGy (0.47–0.67 mGy), DLP 92.0 mGy·cm (73.7–107.6 mGy·cm), ED 0.61 mSv (0.52–0.69 mSv). Radiation exposure indices and effective and organ doses were significantly lower with third-generation DSCT (P < 0.001). Local DRLs could be set for CTDIvol at 0.75 mGy and DLP at 120 mGy·cm. Conclusion: Third-generation DSCT requires significantly lower radiation dose for WBLDCT than second-generation DSCT and has an effective dose below reported doses for radiographic skeletal surveys. To ensure radiation protection, DRLs regarding WBLDCT are required, where our locally determined values may help as benchmarks. [ABSTRACT FROM AUTHOR]

The National Council on Radiation Protection and Measurements (NCRP) is coordinating an expansive epidemiologic effort entitled the Million Person Study of Low-Dose Radiation Health Effects (MPS). Medical workers constitute the largest occupational radiation-exposed group whose doses are typically received gradually over time. A unique opportunity exists to establish an Institutional Review Board/Privacy Board (IRB/PB) approved, retrospective feasibility sub-cohort of diseased Memorial Sloan Kettering Cancer Center (MSK) medical radiation workers to reconstruct occupational/work history, estimate organ-specific radiation absorbed doses, and review existing publicly available records for mortality from cancer (including leukemia) and other diseases. Special emphasis will be placed on dose reconstruction approaches as a means to provide valid organ dose estimates that are as accurate and precise as possible based on the available data, and to allow proper evaluation of accompanying uncertainties. Such a study that includes validated dose measurements and information on radiation exposure conditions would significantly reduce dose uncertainties and provided greatly improved information on chronic low-dose risks. The feasibility sub-cohort will include deceased radiation workers from MSK who worked during the nearly seventy-year timeframe from 1946 through 2010 and were provided individual personal radiation dosimetry monitors. A feasibility assessment focused on obtaining records for about 25–30,000 workers, with over 124,000 annual doses, including personnel/work histories, specific dosimetry data, and appropriate information for epidemiologic mortality tracing will be conducted. MSK radiation dosimetry measurements have followed stringent protocols complying with strict worker protection standards in order to provide accurate dose information for radiation workers that include detailed records of work practices (including specific task exposure conditions, radiation type, energy, geometry, personal protective equipment usage, badge position, and missed doses), as well as recorded measurements. These dose measurements have been ascertained through a variety of techniques that have evolved over the years, from film badges to thermoluminescent dosimetry technology to optically stimulated luminescent methodologies. It is expected that individual total doses for the sub-cohort will have a broad range from <10 mSv to > =1000 mSv. MSK has pioneered the use of novel radiation diagnostic and therapeutic approaches over time (including initial work with x-rays, radium, and radon), with workplace safety in mind, resulting in a variety of radiation worker exposure scenarios. The results of this feasibility sub-cohort of deceased radiation workers, and associated lessons learned may potentially be applied to an expanded multicenter study of about 170,000 medical radiation worker component of the MPS. [ABSTRACT FROM AUTHOR]

Scientific Committee 6–9 was established by the National Council on Radiation Protection and Measurements (NCRP), charged to provide guidance in the derivation of organ doses and their uncertainty, and produced a report, NCRP Report No. 178, Deriving Organ Doses and their Uncertainty for Epidemiologic Studies with a focus on the Million Person Study of Low-Dose Radiation Health Effects (MPS). This review summarizes the conclusions and recommendations of NCRP Report No. 178, with a concentration on and overview of the dosimetry and uncertainty approaches for the cohorts in the MPS, along with guidelines regarding the essential approaches used to estimate organ doses and their uncertainties (from external and internal sources) within the framework of an epidemiologic study. The success of the MPS is tied to the validity of the dose reconstruction approaches to provide realistic estimates of organ-specific radiation absorbed doses that are as accurate and precise as possible and to properly evaluate their accompanying uncertainties. The dosimetry aspects for the MPS are challenging in that they address diverse exposure scenarios for diverse occupational groups being studied over a period of up to 70 y. Specific dosimetric reconstruction issues differ among the varied exposed populations that are considered: atomic veterans, U.S. Department of Energy workers exposed to both penetrating radiation and intakes of radionuclides, nuclear power plant workers, medical radiation workers, and industrial radiographers. While a major source of radiation exposure to the study population comes from external gamma- or x-ray sources, for some of the study groups, there is also a meaningful component of radionuclide intakes that requires internal radiation dosimetry assessments. [ABSTRACT FROM AUTHOR]

Glass systems such as Tb2O3-La2O3-P2O5 (TLP-system) exhibit both transparency of visible light and remarkable attenuation of ionizing radiation. In this research article, the TLP-system was explored for potential shielding application against nuclear radiation in various technological facilities. Monte Carlo method is applied by using Geant4 packages to assess the radiation shielding performance of the TLP-system. The validation of the simulation outcomes is achieved by the theoretical calculations. The obtained findings showed that the maximum attenuation coefficients (MACs) of the TLP-system are observed at 0.284 MeV, while the minimum MACs were noticed at 1.275 MeV. At 0.284 MeV photon energy, TLP-A glass with 5 mol% of Tb2O3 has the maximum effective atomic number (Zeff) with worth of 18.3229, whereas the TLP-E glass with 25 mol% Tb2O3 has the maximum Zeff with worth of 21.0558. Moreover, the radiation protection efficiency (RPE) values of the TLP-system decrease with photon energy and increment as the Tb2O3 content increases. [ABSTRACT FROM AUTHOR]