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In the quasi-binary system CaNi2-MgNi2 solid-solutions CaxMg1−xNi2 (0 ≤ x ≤ 1) were prepared from the elements. They crystallize in the hexagonal Laves phase type (MgNi2, C36) for x ≤ 0.33 (P63/mmc, a = 482.51(7) pm, c = 1582.1(3) pm for x = 0, a = 482.59(3), c = 1583.1(1) for x = 0.33) and in the cubic Laves phase type (MgCu2, C15) for 0.33 < x (Fd 3 ¯ m, a = 697.12(3) pm for x = 0.5, a = 705.11(2) pm for x = 0.67, a = 724.80(2) pm for x = 1). After hydrogenation in an autoclave the X-ray diffraction patterns changed completely. Reflections assigned to CaNiH3, and Ni and Rietveld refinement confirmed this. The hydrogenation properties of CaxMg1−xNi2 (0 ≤ x ≤ 1) compounds were also studied in situ by X-ray powder diffraction. In situ X-ray powder diffraction of CaxMg1−xNi2 (0 ≤ x ≤ 1) compounds under 0.3 MPa hydrogen gas flow (15 sccm), data collected on a Rigaku SmartLab diffractometer in an Anton Paar XRK 900 Reactor Chamber using Cu-Kα1 radiation. Scanning electron microscopy and EDX spectroscopy confirmed the entitled materials and elemental composition, respectively. From the Transmission electron microscopy and Selected area electron diffraction concluded that the CaxMg1−xNi2 (0 ≤ x ≤ 1) compounds were crystalline. [ABSTRACT FROM AUTHOR]

This paper presents guidelines for the calibration of radiation beams that were issued by the International Atomic Energy Agency (IAEA TRS 398), the American Association of Physicists in Medicine (AAPM TG 51) and the German task group (DIN 6800-2). These protocols are based on the use of an ionization chamber calibrated in terms of absorbed dose to water in a standard laboratory's reference quality beam, where the previous protocols were based on air kerma standards. This study aims to determine uncertainties in dosimetry for electron beam radiotherapy using internationally established high-energy radiotherapy beam calibration standards. Methods: Dw was determined in 6-, 12- and 18 MeV electron energies under reference conditions using three cylindrical and two plane-parallel ion chambers in concert with the IAEA TRS 398, AAPM TG 51 and DIN 6800-2 absorbed dose protocols. From mean measured Dw values, the ratio TRS 398/TG 51 was found to vary between 0.988 and 1.004, while for the counterpart TRS 398/DIN 6800-2 and TG 51/DIN 6800-2, the variation ranges were 0.991–1.003 and 0.997–1.005, respectively. For the cylindrical chambers, the relative combined uncertainty (k = 1) in absorbed dose measurements was 1.44%, while for the plane-parallel chambers, it ranged from 1.53 to 1.88%. Conclusions: A high degree of consistency was demonstrated among the three protocols. It is suggested that in the use of the presently determined dose conversion factors across the three protocols, dose intercomparisons can be facilitated between radiotherapy centres. [ABSTRACT FROM AUTHOR]

The objective of this study is to assess the patients' effective and organ dose during theranostic applications in Kuwait. In total, eighteen adults' patients were conducted nuclear medicine procedures with 177Lu Dotatate for theranostic purpose in Kuwait Cancer control center (KCCC), Kuwait. Medium energy collimator (MEC) (208 keV Scatter 26% better than 113 keV Scatter 60%) was utilized to obtain scans in definite time intervals ranged from one to 2 h (before voiding), 6:00, 24:00, 48:00, 72:00 h. Patients, tissue and organ radiation doses were computed utilizing OLINDA/EXM Software. The average radiation effective dose (in mSv/MBq) for bladder, liver, and both kidneys (left & right), were 0.36, 0.08, 0.61 & 0.60. The range of the effective dose was from 0.55 mSv to 7.7 mSv. The acquired scans using 177Lu were delivered diagnostic findings. The patients' effective dose is lower compared to the previous studies. Variation is attributed to the departmental protocol and administered activity. The values of the mean organ dose were comparable and lower than previously published studies. Different organs have different level of doses, which may affected by the presence of the metastatic tumors in the entire organ. • Patients' organs dosimetry in targeted radionuclide therapy were carried out in Kuwait Cancer Control Centre. • A total of 18 patients were undergone theranostic procedures with 177Lu Dotatate. • Organ and total patients doses were calculated using Organ Level INternal Dose Assessment (OLINDA) Software. • Optimization of the PET/CT imaging protocol is recommended to assure that patients received a minimal effective dose. [ABSTRACT FROM AUTHOR]

The purposes of this study are to estimate patient's radiation doses and radiogenic risk in vascular lower limb computed tomography (CT). In total, 188 (109 (68%) males and 79 (42%) females) patients undergone vascular CT for the lower limbs at three radiology departments. Three CT scanners, 160, 128, and 64 slices CT, were used in this study. CT-Expo and ImPACT CT dose estimation software were used to extrapolate the effective dose. The overall average and range of volume CT dose index (CTDIvol (mGy) and dose length product (DLP) (mGy.cm) 7.3 (2.3–22.9), and 3000 (279.1–8374.4) the same order. The overall effective dose average value was 18 mSv per procedure. The proposed diagnostic reference level (DRL) values are 9 mGy (CTDIvol) and 2500 mGy cm (DLP) per vascular lower limb CT procedure. The risk of cancer from the peripheral CT angiography procedures ranges from 1 in 1000 to 1 in 3000 procedures. The cancer risk per procedure should be considered during the justification and image acquisition stages. • Peripheral CT angiography for lower extremities were performed using three CT machines. • CT dose per procedure (DLP (mGy.cm) is higher up to 10 times compared to previous. • Patients are being seen to be receiving unnecessary radiation doses during triphasic CT abdomen procedure. • A local diagnostic reference level was proposed was established for further dose reduction. [ABSTRACT FROM AUTHOR]

This paper presents a comprehensive bibliometric analysis to understand the evolution of scintillators as neutron detection from 2014 to 4 July 2023, utilizing data sourced from Scopus. The 312 selected articles were visualized using vosViewer and Tableau. This study delves into critical aspects, such as the growth of publication in this field over time, contributions made by various countries and their collaborative networks, top journals publishing articles related to scintillators as neutron detection, frequently cited documents used as references, and research trends over specific periods. The results show that research on scintillators for neutron detection has been popular since 2014, with at least 20 articles published yearly. The United States, China, France, and Italy have published the most papers, but Lithuania, Russia, India, and China have been the most active recently. The article provides researchers with an extensive overview of their field. This information empowers them to identify research gaps and find collaborators more efficiently. Overall, this analysis serves as a valuable resource for researchers seeking to advance their understanding of scintillators as neutron detection. • Evolution of scintillators as neutron detection from 2014 to 4 July 2023. • Scintillators for neutron detection popular since 2014 with 20 articles published yearly. • The United States, China, France, and Italy have published the most papers. • Lithuania, Russia, India, and China have been the most active recently. • This information to identify research gaps and find collaborators more efficiently. [ABSTRACT FROM AUTHOR]

One the most complicated gastrointestinal procedures, endoscopic retrograde cholangio-pancreatography (ERCP) uses fluoroscopy guidance of an endoscope to diagnose and treat hepatobiliary system pathologies. As is true of all approved interventional radiology, it is justified by the massive benefit that it is capable of delivering, one which for the patient far outweighs the risks from radiation exposure. Nevertheless, for both patients and staff there is a need to minimize the risk of carcinogenesis and the potential for tissue reactions. Recent concern has been shown in regard to radiation induced eye lens opacifications and cataract, most particularly for the members of staff who during their regular theatre practice are in closest contact with the patient. Therefore, optimum balance between benefit versus radiation risk is required. This study reviews patient and staff dose during ERCP procedures, also seeking to provide comprehensive data regarding radiation exposure management techniques. Patient and staff doses depend on the operators, equipment and patient related factors, benefitting from awareness and experience in respect of radiation protection techniques and the availability of modern fluoroscopic equipment. It is apparent that in high workload departments, staff doses to eye lens may exceed the limits on annual exposure. • Previous studies in patients and occupational dosimetry had been studies. • Patients and staff remain constant regardless of the X ray technology development. • ERCP is safe during pregnancy for patients and pregnant workers. • It is apparent that in high workload departments, staff doses to eye lens may exceed the limits on annual exposure. • Lack of training and monitoring services in gastroenterology department are frequently reported. [ABSTRACT FROM AUTHOR]

The objective of present study is estimation of the radioactivity held within the urinary bladder and kidneys 3 h post radiopharmaceutical (99mTc-MDP) administration, comparison being made via use of MIRDose. Using the conjugate-view method and built-in camera software Mediso XP Interview, urinary bladder and kidney radionuclide activities were calculated using patient clinical data acquired at the aforesaid 3 h post 99mTc-MDP injection juncture. The study was of a cohort of 40 patients attending for staging and cancer follow-up at the Nuclear Medicine Department, Royal Care International Hospital (RCIH), Sudan, Ethical and Research Committee approval for the study having been obtained. The radioisotope biokinetics were simulated using the Medical Internal Radiation Dose (MIRD) biokinetics model, specifically in regard to radionuclide activity in the kidneys and bladder. The results were compared with the data achieved via clinical study, showing the experimentally estimated radionuclide activity in the kidney to be greater by some 50% compared to that of simulation while the bladder radionuclide activity was found to be just 2% of the simulation result. The study also found that 0.9% of the administered radioactivity remained in the urinary bladder and kidneys 3 h post administration of the radionuclide, suggestive of low radiation dose to the urinary bladder and kidneys post 99mTc-MDP bone scans. • 99mTc-MDP radionuclide biokinetics were simulated using MIRD biokinetics model. • Radionuclide activities for Urinary bladder and kidney were calculated. • The experimentally estimated radionuclide activity in the kidney to be greater by some 50%. • 0.9% of the administered radioactivity remained in the urinary bladder and kidneys 3 h. • Low radiation dose to the urinary bladder and kidneys post 99mTc-MDP bone scans. [ABSTRACT FROM AUTHOR]

This paper presents the fabrication of Cassava Starch/ Rhizophora Spp /Zn nanoparticle composite as a phantom for X-ray radiation. The use of phantoms is crucial in controlling the quality of radiation doses in medical applications. The composite materials were synthesized using a sol-gel method, and the structural properties were characterized using X-ray Diffraction (XRD) and bonding characteristics by Fourier transform infrared spectrophotometry (FTIR). Mechanical testing was performed to assess the physical and mechanical properties of the phantoms. The linear attenuation coefficient and mass attenuation coefficient were determined using CT-Scan and Mobile X-ray tests. The results showed that the composite materials exhibited amorphous characteristics with crystal structure patterns. The addition of Zn nanoparticles affected the diffraction intensity and crystal size. The FTIR analysis revealed the presence of functional groups such as hydroxyl, alkane, siloxane, alkene, and ether bonds in the composite. The synthesized phantom composites showed potential as substitutes for commercial phantoms due to the Cassava starch/ Rhizophora spp/Zn 1gr phantom is generally close to the attenuation coefficient value of the human liver phantom reported in previous studies, which is about 0.293 cm−1. This suggests that this phantom composite has a good potential as a substitute for human liver tissue in X-ray testing. • The phantom research as X-ray testing have explored various materials. • The composite materials were synthesized using a sol-gel method. • We found the best for liver phantom is phantom with 1 gr Zn in composite. • Attenuation coefficient value for human liver phantom is about 0.293 cm–1. [ABSTRACT FROM AUTHOR]

BACKGROUND: Accurate diagnosis and subsequent delineated treatment planning require the experience of clinicians in the handling of their case numbers. However, applying deep learning in image processing is useful in creating tools that promise faster high-quality diagnoses, but the accuracy and precision of 3-D image processing from 2-D data may be limited by factors such as superposition of organs, distortion and magnification, and detection of new pathologies. The purpose of this research is to use radiomics and deep learning to develop a tool for lung cancer diagnosis. METHODS: This study applies radiomics and deep learning in the diagnosis of lung cancer to help clinicians accurately analyze the images and thereby provide the appropriate treatment planning. 86 patients were recruited from Bach Mai Hospital, and 1012 patients were collected from an open-source database. First, deep learning has been applied in the process of segmentation by U-NET and cancer classification via the use of the DenseNet model. Second, the radiomics were applied for measuring and calculating diameter, surface area, and volume. Finally, the hardware also was designed by connecting between Arduino Nano and MFRC522 module for reading data from the tag. In addition, the displayed interface was created on a web platform using Python through Streamlit. RESULTS: The applied segmentation model yielded a validation loss of 0.498, a train loss of 0.27, a cancer classification validation loss of 0.78, and a training accuracy of 0.98. The outcomes of the diagnostic capabilities of lung cancer (recognition and classification of lung cancer from chest CT scans) were quite successful. CONCLUSIONS: The model provided means for storing and updating patients' data directly on the interface which allowed the results to be readily available for the health care providers. The developed system will improve clinical communication and information exchange. Moreover, it can manage efforts by generating correlated and coherent summaries of cancer diagnoses. [ABSTRACT FROM AUTHOR]

Protection of personnel against ionising exposure is necessary to prevent occurrence of biological risks. The objective of this study is to arranged light and heavy nuclei at the surface state particle of composite geopolymer concrete when filler with metal (Ni or Fe) for X-ray shielding applications. The composite fly ash geopolymer concrete with fillers Ni and fly ash geopolymer concrete with Fe as a shield for X-ray radiation has been successfully synthesized by a simple method. The shielding composites were carried out using Fourier transform infra-red (FTIR), X-ray diffraction (XRD), scanning electron microscope (SEM), and X-ray mobile to determine optical properties, structural properties, surface morphology, and shielding performance. In this study shows strong linear correlation between structural properties and the effectiveness of X-ray shielding. The best composite as an X-ray radiation shield is composite concrete geopolymer with AC and Ni as a filler indicated by higher linear attenuation coefficient μ due to present combination between heavy and light nuclei at the surface state of particle, consequently, produce high stability structural and optical properties, and bonding characteristics. The results in this study indicated composite concrete geopolymer fly ash with AC and Ni as a filler with sharp nodule at the surface state looks like prickly ball as a new composite for X-ray shield. [ABSTRACT FROM AUTHOR]

Composite geopolymer apron cellulose/black carbon (BC)/Fe–Cu/polyvinyl alcohol (PVA) has been successfully synthesized with variations in Fe–Cu (Cel/Bc I, Cel/Bc II, and Cel/Bc III) as shielding X-ray radiation by employing a simple approach characterized by Fourier Transform Infra-Red (FTIR), X-ray diffraction (XRD), scanning electron microscopy (SEM), and X-ray mobile. The quantitative analysis of the FTIR spectrum using the Kramers-Kronig (K–K) relation was employed to analyze the optical properties, the refractive index (n) , the extinction coefficient (k), real (ε 1) , and imaginary (ε 2) of the dielectric function and the energy loss function. The analysis of XRD spectra demonstrated that the crystallite size decreases as the Fe concentration decreases in the composite's apron and the best radiation shielding characteristics are shown in the Cel/Bc III sample with a small crystallite size of 12.72 nm. The quantitative analysis of X-ray mobile showed that the absorption properties of Cel/Bc III by the attenuation coefficient 0.441 cm−1 is higher and more effective with a half value layer of 1.57 cm and mean free path of 2.26 cm, which is indicated as a new cellulose-based composite apron X-ray in future. • Geopolymer Cellulose-Based Composite for Eco-Friendly Apron X-Ray. • Surface morphology with stretched cellulose (elongated and crossed). • Crystallite size decreases as the Fe concentration decreases. • Best absorption is composite Cel/Bc III with attenuation coefficient 0.441 cm−1. • The half value layer of 1.57 cm and mean free path of 2.26 cm. [ABSTRACT FROM AUTHOR]

This study aimed to measure entrance surface air kerma (ESAK, in mGy) during routine skull X-ray examinations of adult patients and to establish a local diagnostic reference level (LDRL) in the diagnostic radiology department of King Khalid Hospital in Majmaah. The patient's ESAK, mGy and effective dose (ED, in mSv) at the 75th percentile were calculated based on the output of the X-ray tube and the exposure parameters, as well as the use of suitable conversion coefficients, respectively. To calculate the ED and patient's ESAK, the output and exposure characteristics of the X-ray tube and relevant conversion coefficients were considered (ESAK). Additionally, the 75th percentile distributions for the ESAK and KAP distributions were calculated. A wide range of ESAK was observed, which might be due to the difference in the exposure factors applied for each examination. The mean values of ESAK and KAP together with 75th percentiles for Anteroposterior (AP) and lateral skull projection were 0.22 (0.10–0.30) mGy, 0.24 (0.0.18–0.25) mGy and 0.21 (0.19–0.26) Gy.cm2, 0.29 (0.17–0.32) Gy.cm2, respectively. The findings were significantly lower than national reference levels, the most reported European DRL values, and other previously reported dose values. The measured ESAK and KAP were within the recommended and acceptable dose limits. The best radiation protection can be achieved by optimizing the radiation dose while preserving image quality. • The patient's ESAK effective dose were calculated based on the exposure parameters. • Radiation application has increased as a result of technological progress. • The best radiation protection can be achieved by optimizing the radiation dose. [ABSTRACT FROM AUTHOR]

Computed tomography (CT) are often used for adult and pediatric patients. This is basically due to its powerful diagnostic capabilities in providing the tiniest details of pathologies in the body. Nevertheless, this detailed and accurate imaging occurs at the expense of the high doses received by the patients, although in general, the benefits outweighs the risks precisely of malignancy. Pediatrics are radiosensitive more than adults due to their longer life expectancy and their rapidly dividing cells. This study aims at measuring and evaluating pediatric patient doses in four hospitals equipped with 16, 20 and 128 CT detectors. Forty-eight pediatric patients who underwent brain (72.7%) and abdomen (36.3%) Computed Tomography are included in this study. Data includes CTDI vol (mGy) and DLP (mGy.cm). CTDOSE computer software which is based on Monte Carlo simulations was used to calculate the effective and organ equivalent doses (mSv). The CTDIvol (mGy) per procedure range was 11.0–95.0 mGy for brain CT and 3.0–30.0 mGy for abdomen CT. DLP on the other hand ranged between 129.0 and 2510.0 mGy cm for brain CT and 84.0–1604.0 for abdomen CT. The high doses were attributed to the fact that the protocols used for pediatric patients were the adult protocols, not bearing in mind the high radio-sensitivity of the pediatrics. Establishing a protocol for pediatric CT is hence of great importance to prevent them from receiving unnecessary high doses which may eventually cause cancer. • The radiation doses during specific pediatric CT examinations in four hospitals were evaluated. • Patient dose per CT procedure ranged from 84.0 to 2510.0 mGy cm. • Adults protocols used for pediatric patients resulted in unnecessary exposure. • Standardizing imaging protocols during pediatric CT imaging is recommended. [ABSTRACT FROM AUTHOR]

This study aimed to estimate the cumulative radiation exposure, effective and organ dose from the recurrent computed tomography (CT) head scan during the stroke. Data was collected using a validated survey, including scanner information, patient demographic information, scan protocol, and dose indices (CTDIvol and DLP). A retrospective search of the picture archiving and communicating system (PACS) database for all the patients who underwent at least three head scans while admitted to the hospital because of stroke. Effective and organ doses are calculated by VirtualDose software based on ICRP 103. One hundred fifty-two patients underwent three to five scans during their hospitalization, which lasted from three weeks to three months. The age ranged from 45-to 76 years; males were (n = 104, 68.4%) and females were (n = 48, 35.6%). The scan range was 20.9–28.8 cm, with a mean of 24.4 ± 1.5. The mean CTDIvol and DLP values per scan were 21 ± 0.8 and 429 ± 85, respectively. The calculated effective doses for patients with three, four, and five scans were 6.4, 8.5, and 10.7 mSv, respectively. The highest organ dose is recorded in the brain and the lowest at the breast. Focusing on referring physician awareness and encouraging request justification and dose optimization for patients subject to frequent radiation exams. In addition, the cumulative effective dose should be part of training programs for referrers, radiologists and radiographers. • Efforts should be made to dose reduction in stroke CT scans. • CT scanning remains the useful technique for diagnosis of stroke. • Potential risks exist from multiple CT scan. • Referring physician awareness encourage request justification and dose optimization. [ABSTRACT FROM AUTHOR]

Microplastics (MPs) have become an emerging global pollutant due to their widespread dispersion and potential threats to marine ecosystems. However, studies on MPs in estuarine and coastal ecosystems of Bangladesh are very limited. Here, we conducted the first study on abundance, distribution, characteristics, and risk assessment of microplastics in the sediment of Karnaphuli River estuary, Bangladesh. Microplastic particles were extracted from sediments of 30 stations along the estuary by density separation and then enumerated and characterized using a stereomicroscope and Fourier Transform Infrared (FT-IR) spectroscopy. In the collected sediment of the Karnaphuli River estuary, the number of MPs varied from 22.29 to 59.5 items kg−1 of dry weight. The mean abundance was higher in the downstream and left banks of the estuary, whereas the predominant shape, colour, and size of MPs were films (35%), and white (19%), and 1–5 mm (30.38%), respectively. Major polymer types were polyethylene terephthalate, polystyrene, polyethylene, cellulose, and nylon. MPs were found to pose risks (low to high) in the sediment of the estuary, with the highest risk occurring at one station near a sewage outlet, according to the results of risk analyses using the pollution risk index, polymer risk index (H), contamination factors, and pollution load index (PLI). The single value index, PLI, clearly demonstrated that all sampling sites were considerably polluted with microplastics (PLI > 1). H values showed toxic polymers, even in lower proportions, possess higher polymeric hazard scores and vice versa. This investigation uncovered new insights on the status of MPs in the sediments of the Karnaphuli River estuary, laying the groundwork for future research and control of microplastic pollution and management. [ABSTRACT FROM AUTHOR]

In the present study we focused on the anti-asthmatic and antioxidant effects of Zingiber officinalis roscoe L. (ZO) aqueous extract. This study includes 20 adult male rats, which were grouped into four; Group I: control group; Group II: asthmatic group (Ovalbumin sensitized/challenge model, Oval group); Group III: received ovalbumin sensitized/challenge associated a dose of 207 mg/kg body weight (BW) of ZO (Oval + D1 group); Group IV: received ovalbumin sensitized/challenge associated a dose of 414 mg/k BW of ZO (Oval + D2 group). After 21 days, blood and lung samples were collected for biochemical, hematological, and histopathological analyses. The ameliorative effect of ZO phytochemical compounds was also assessed by in silico approach on transducer and activator of transcription 6 (STAT6) and tumor necrosis factor-α (TNF-α) receptors. The oxidative/antioxidative status was evaluated in the lung tissues. Our results show that ZO extract alleviated the ovalbumin-induced hematological and biochemical disruptions associated oxidative injury. In fact, white and red blood cells (WBC and RBC, respectively), aspartate aminotransaminase (ASAT), malondialdehyde (MDA), glutathione (GSH), and glutathione peroxidase (GPx) were significantly disrupted (p < 0.05) in Oval group and alleviated following ZO treatment. Besides, several histopathological features were outlined in lung tissues of Oval group. Interestingly, ZO was found to exert ameliorative effects on tissue level. In silico analyses, particularly the binding affinities, the number of H-bonds, the embedding distance and the molecular interactions of ZO phytochemical compounds with either STAT6 or TNF-α supported the in vivo results. These findings confirm the potential ethno-pharmacological effects of ZO against asthma and its associated complications. [ABSTRACT FROM AUTHOR]

Due to variation among radiographers' practice, and the importance of unifying practice during radiography for optimizing radiation level and image quality, the current manuscript aims to assess the radiation dose level and propose local diagnostic reference levels (LDRL) for posterior-anterior (PA) chest, antero-posterior (AP) abdomen, and pelvis examinations in two hospitals in Khartoum ('K') and one hospital in Wad-Medani ('M') cities, Sudan. Along with patient demographics like height and weight, the radiation exposure parameters including tube potential, current, and radiation duration were documented. This included 732 patients whose tests were conducted at one of three departments located in two different cities. The entrane surface air kerma (ESAK) was calculated using DosCal software and an Unfors -Xi-meter. The average ESAK for an X-ray of the chest was 0.18 mGy in M, 0.19 mGy in K (averaged over two hospitals in the K), for the abdomen it was 1.1 and 1.23 mGy, and for the pelvis it was 1.8 and 01.9 mGy respectively. The proposed DRL was achieved from the third quartile of radiation dosage of data, and it was 0.21, 1.7 and 1.9 mGy for the chest, abdomen and pelvis respectively. There was a wide variation in dosage levels among the three hospitals. The current proposed DRL was lower than most literature for the chest, abdomen and pelvis. More studies are recommended for other examinations such as skull and contrast media studies. • Radiation dose level for chest, abdomen and pelvis was assessed in major hospitals in Sudan. • Average dose for conventional X-ray of chest, abdomen and pelvis was 0.19, 1.2 and 1.9 mGy respectively. • Local diagnostic reference level was suggested for the above examinations. • The Suggested LDRL was lower than available literature. [ABSTRACT FROM AUTHOR]

Cardiovascular nuclear medicine (NM) imaging examinations expose patients to extremely high absorbed doses of ionizing radiation, which necessitates extensive efforts to reduce the doses without compromising the quality of images. This study aims to assess patients' radiation doses to patients and public exposure in Cardiac rest and stress single photon emission computed tomography (SPECT) scans. The patients' exposure was calculated for 21 patients using the administered activity (AA, MBq). (GE SPECT) was the device used for all patients. AA (MBq) mean and range were 370 for Rest and 1110 for Stress. The average range of the dose rate was 1.59 (0.67–2.34) mR/h for rest and 7.29 (4.2–9.98) mR/h for stress when computed at 30 cm from the patient's chest level after injection. At 100 cm from the patient, the mean dose rate values were 0.37 (0.16–0.73) mR/h for rest and 1.39 (1.01–2.0) mR/h for stress. The overall effective dose is 12.1 mSv per rest and stress SPECT procedure. The mean effective dose for cardiac rest is comparable with previously published studies while the effective dose from cardiac stress is higher than previously published studies. The variation in the effective dose depends on several factors, including the department's clinical indication imaging protocols and radiation safety measures. • The patient's effective dose and dose were quantified during cardiac rest and stress SPECT procedures. • The mean effective dose for cardiac rest is comparable with previously published studies. • The effective dose from cardiac stress is higher than previously published studies. • The current AA activity for rest and stress is lower than the DRL and the previous studies. [ABSTRACT FROM AUTHOR]

Renal diseases and urinary tract disorders are causing a global burden, with an estimated prevalence of around 13%. Contrast-enhanced computed tomography urography (CE-CTU) is a well-known diagnostic technique for urinary system diseases for initial diagnosis and, very often, for follow-up. CE-CTU procedure exposes patients to high doses of ionizing radiation; hence, justification and optimization of doses are necessary to maximize the benefits and minimize the patients' risks. This study aims to evaluate radiation doses to patients during CE-CTU procedures and estimate the subsequent radiogenic risk. The study included twenty-seven patients who underwent CE-CTU examination in two different hospitals (National Ribat Hospital (NRH) and National Security Fource Hospital (NSFH)), where 16-slice CT machines from different vendors are used. The variables and significance were analyzed using SPSS and Scheffe's statistical tool. Data collected included the age of patients (19–70 years), the radiation dose received by patients: dose length product (DLP, mGy.cm) and volume CT dose index (CTDIvol (mGy)), and tube current-time product (mAs). Patients' dose measurements per CE-CTU procedure given as (mean and range) was: DLP 3098 (647–5301) (mGy.cm) and CTDIvol 44.11 (15–136) (mGy). The results revealed statistically significant differences in DLP (mGy.cm), CTDIvol (mGy), and mAs, and this could be attributed to discrepancies in protocols, machines, and operators among the hospitals and within each hospital. Considering gender, the variables (age, tube current-time product (mAs), and CTDIvol) showed no statistically significant differences. The radiogenic risks from the CE-CTU procedure were ≈1 per 400. Comparison between the two hospitals showed that the variables varied significantly between the hospitals studied, but no significant differences were found based on gender. CE-CTU with contrast medium exposes patients to high doses. Therefore, proper dose optimization is crucial. • The radiation doses during IVU and the subsequent risks from exposure are studied. • The entrance-surface air kerma (ESAK) and effective dose were quantified. • Calculation of the overall cancer risk yielded 5.85 per million procedures. • The effective and cancer risk are around ten times lower during IVU procedures compared to CTU. [ABSTRACT FROM AUTHOR]

The widespread consumption of pharmaceutical drugs and their incomplete breakdown in organisms has led to their extensive presence in aquatic environments. The indiscriminate use of antibiotics, such as sulfonamides, has contributed to the development of drug-resistant bacteria and the persistent pollution of water bodies, posing a threat to human health and the safety of the environment. Thus, it is paramount to explore remediation technologies aimed at decomposing and complete elimination of the toxic contaminants from pharmaceutical wastewater. The review aims to explore the utilization of metal-oxide nanoparticles (MONPs) and graphitic carbon nitrides (g-C 3 N 4) in photocatalytic degradation of sulfonamides from wastewater. Recent advances in oxidation techniques such as photocatalytic degradation are being exploited in the elimination of the sulfonamides from wastewater. MONP and g-C 3 N 4 are commonly evolved nano substances with intrinsic properties. They possessed nano-scale structure, considerable porosity semi-conducting properties, responsible for decomposing wide range of water pollutants. They are widely applied for photocatalytic degradation of organic and inorganic substances which continue to evolve due to the low-cost, efficiency, less toxicity, and more environmentally friendliness of the materials. The review focuses on the current advances in the application of these materials, their efficiencies, degradation mechanisms, and recyclability in the context of sulfonamides photocatalytic degradation. [Display omitted] • Graphitic bio-carbon nitride and metal oxide for the degradation of sulfonamide. • Advanced modifications for improving photocatalytic efficiency of the new materials. • Effective stability and reusability of new materials for photocatalytic applications. [ABSTRACT FROM AUTHOR]

With the rapid increase in computed tomography (CT) examinations among pediatric patients, the concern about the effects of radiation exposure in this population has increased. Therefore, it is necessary to measure and regulate radiation exposure, which can be done using diagnostic reference levels (DRLs). This study aimed to calculate typical values for common pediatric studies at the radiology department of King Abdulaziz University Hospital Jeddah, Saudi Arabia. For a single institute, these are calculated as the median of computed tomography dose index (CTDIvol, mGy) or dose length product (DLP, mGy.cm) values. Pediatric patient data from January 2015 to December 2020 were collected, including CT examinations, dose descriptors, imaging protocols, and scanning parameters. A total of 8717 radiological studies were included in the sample. They were categorized into three age groups; more than half of the 5102 (58.5%) belonged to Group 1 (0–5 years), 1790 (20.5%) were in Group 2 (6–10 years), and 1826 (20.9%) were in Group 3 (11–15 years). Brain CT angiogram, non-enhanced brain CT, and Internal Auditory Canal (IAC) CT had the highest mean CTDI Vol and DLP, while virtual bronchoscopy contrast-enhanced chest and neck CT angiography had the lowest mean CTDI Vol. The values of DRLs in the current study were approximately lower than and comparable with those reported in other studies. • This study quantified pediatric doses during common CT procedures. • A total of 8717 radiological studies were included in the sample. • Local DRLs were established for common CT procedures. • The values of DRLs in the current study were lower than other studies. [ABSTRACT FROM AUTHOR]

Mammary glands or breasts are radiosensitive organs that makeup 12% of the body's overall radiation sensitivity. According to estimates, Saudi Arabia has a 27.3% overall cancer incidence rate for breast cancer. Recent studies reported that breasts get significant organ equivalent doses during diagnostic procedures with ionizing radiation, even though the breast is not the target organ. The objective of this work is to assess the effective and breast equivalent doses during positron emission tomography (PET)/Computed tomography (CT) imaging examinations. The effective and breast equivalent doses per PET/CT (GE PET/CT 710) examination were quantified using the amount of the injected radiopharmaceutical (MBq) (18F- fluorodeoxyglucose (FDG)), and external doses from CT examinations. The average, standard deviation (SD) and range of examined patients' age (years) and body mass index ((BMI), kg/m2) were 58 ± 11 (39–76) and 30 ± 5 (20.7–43.1), respectively. Constant administered activity (AA, 185 MBq) and tube potential (120 kVp) were used for all patients. The average, SD, and range of the patients effective dose (mSv) from PET/CT (18F- FDG) examination was 8.0 ± 0.93 (7.0–10.0) and 2.075 ± 0.11 (1.91–2.29) in that order. Breast doses are comparable with previous studies during the PET/CT and mammographic examination. Proper justification criteria and dose optimization are essential to lowering excessive exposure while preserving image quality, especially for young females because they have a higher risk of radiation-induced cancer. • Breast doses during PET/CT imaging procedures were evaluated. • Breast absorbed dose depends on CT protocol and administered activity. • The organ equivalent dose ranged from 1.91 to 2.29 mGy per procedure. • Breast doses are comparable with previous studies PET/CT procedures. • Young females have a higher risk of breast cancer due to PET/CT procedure. [ABSTRACT FROM AUTHOR]

The rising environmental concerns have triggered film technology to find a bio-based polymer for environmental sustainability. Thus, this research provides a sustainable route for the preparation of new thermoplastic elastomer film based on non-polar natural rubber (NR) and poly(3-hydroxybutyrate-co-3-hydroxyhexanoate) (P(3HB-co-3HHx) which could be employed in film separation application. To modify the new film properties, graft copolymerization technique was employed, and benzoyl peroxide (BPO) was selected as a radical initiator. Besides that, the influence of various polymer compositions was investigated, and the physico-chemical characteristics of the NR graft P(3HB-co-3HHx) film were characterized. NR graft P(3HB-co-3HHx) exhibited homogeneous and porous nature with improved thermal stability as the grafting interaction between the polymer was achieved. Besides that, swelling test has shown the excellent resistance and affinity towards polar solvents such as ethanol, and it showcases lower affinity towards non-polar solvents as n-hexane was observed. Therefore, the NR graft P(3HB-co-3HHx) films can potentially be used for biofilm can be used for environmental remediation applications as a replacement to the synthetic polymer films. [Display omitted] • Eco-friendly process for unique film with NR and P(3HB-co-3HHx) for separation. • Various polymer compositions were explored, characterized, and analyzed. • NR graft P(3HB-co-3HHx) achieved thermal stability forming porosity. • Swelling test showed strong polarity preference, favoring ethanol than n-hexane. • NR graft P(3HB-co-3HHx) films may replace synthetic polymers in eco-remediation. [ABSTRACT FROM AUTHOR]

This work using a borosilicate glass medium seeks to detect photoneutrons generated by a medical linear accelerator. The studies involved an Elekta Infiniti accelerator located in the Oncology Centre, Medical City, Riyadh, the neutrons resulting from interactions at above-threshold therapeutic photon energies. The borosilicate detectors were produced from microscope glass slides of nominal thickness 1.0 mm, the latter made into square segments of area 0.6 × 0.6 cm2, a size capable of being accommodated within the planchette of the thermoluminescent (TLD) Reader (Harshaw 600). With some 4% boron in the coverslip glass and the abundance of 10B being 19.8%, thermalised neutrons 10B(n,α)7Li interactions offer a cross-section that can achieve a value as large as 3837 b. Apart from interactions in boron, of additional note is that 2H(γ,n)1H and 9Be(γ,n)8Be are two further photoneutron reactions, giving rise to particularly low threshold energies at 2.226 and 1.666 MeV, respectively. The presence of natural carbon in the present borosilicate samples has been measured to be 1.3%. Accordingly, with the abundance of 13C in natural carbon being 1.109% this would appear to be of very little interest herein. Moreover, compositional measurements made on the borosilicate coverslip glass indicates 9.40 Na. The induced activity in the glass falls to some 25% 30 h post-irradiation, a delay time beyond which readout can subsequently be conducted. • Borosilicate glass media for neutron sensing was developed. • Photoneutron was generated using an Elekta Infiniti linear accelerator beams. • Neutron activation of nuclides within the expanse of the beam should be considered. [ABSTRACT FROM AUTHOR]

This article presents the physical, mechanical, optical, and radiation shielding properties of several articles discussing BaO-based glass systems prepared by the melt-quench technique. Specifically, the article discussed is an article that reports experimentally the effectiveness of BaO-based glass systems as shielding gamma-ray radiation at an energy of 0.662 MeV published since 2019. In addition, we also compare the theoretical effectiveness of several glass systems by recalculating using Phy- X/PSD based on the respective compositions reported by previous studies at several energies, namely: 0.284, 0.347, 0.662, 0.826, 1.173, 1.333, and 2.506 MeV. Based on the analysis, the Bi 2 O 3 –BaO–B 2 O 3 glass system is the best in terms of absorbing radiation. But it still needs to be developed to get the best physical, mechanical, and optical properties. With this article, scholars can more easily determine the composition of a BaO-based glass system to be applied as a more effective and high-quality radiation shield. • Evolution of gamma-ray radiation at an energy of 0.662 MeV published since 2019. • The theoretical effectiveness were calculated using Phy- X/PSD. at various energies. • The Bi2O3–BaO–B2O3 glass system is the best in terms of absorbing radiation. • Scholars easily determine composition BaO-based for effective radiation shield. • Physical, mechanical, and optical properties important in for BaO-based glass. [ABSTRACT FROM AUTHOR]

This paper provides a comprehensive bibliometric analysis to better understand the evolution of concrete composite as a radiation shielding research from when it was first published in 1949 to October 26, 2022. This study was conducted based on the Scopus database, and the publications analyzed a total of 541 documents. The data in this paper is visualized using the VOSviewer and Tableau to perform bibliometric analysis and scientific mapping. The analysis results show that published documents have continued to increase in recent years and are dominated by articles. Some countries show productivity and influence in their country/region with the broadest range of partners. This study presents the most contributed journals and the most frequently cited documents. In addition, keyword analysis was carried out to find the hotspots on this research topic. This paper helps scholars to understand the evolution of concrete composite as a radiation shielding research from a bibliometric perspective and inspires them to develop new concrete composite with high stability absorption properties from waste or natural material to replace concrete Lead (Pb)-based. • Evolution concrete composite as shielding research from 1949 to October 26, 2022. • Data perform using bibliometric analysis and scientific mapping. • To helps scholars, understand evolution of concrete composite as a radiation shield. • Bibliometric perspective help to develop new high absorption of concrete composite. • High stability from waste or natural material to replace concrete Lead (Pb)-based. [ABSTRACT FROM AUTHOR]

Medical personnel working with ionizing radiation are exposed to significant radiation doses. Previously published studies reported increased incidence of induced cancer and cataracts among radiation workers in medical and industrial premises due to exposure to ionizing radiation. Therefore, an assessment of occupational exposure is recommended. The purpose of this study is to estimate the radiation risk caused by staff exposure and ambient exposures during diagnostic radiography. The study involved 46 staff members: 38 technologists, 8 Radiologists and 22 patients: 11 undergoing conventional radiology and 11 undergoing fluoroscopic radiology. Occupational and ambient doses were measured using calibrated optical stimulating-luminescent dosimeters (OSL) (Al2O3:C). These badges were read using an automatic OSL reader. Patients' doses were calculated form the reading of the x-ray machines. Calculating the dose parameters for patients, the mean and standard deviation (SD) of the kVp, mAs, and patient doses in terms of Dose Area Product (DAP)were 113.1 ± 16.2, 7.5 ± 11.65, and 869.6, respectively. The mean and range of the annual effective dose (mSv) for technologists was (0.6 ± 0.36) (0–2.11). The mean and range of effective dose (mSv) for Radiologists were (0.48 ± 0.19) (0.17–0.74). The occupational exposure in this study showed that radiology technologists and radiologists are exposed to a low dose according to the current workload. The staff dose reported in this study is lower than those available in most previous studies. • Staff annual radiation dose were assessed for radiology technologists for two consecutive years. • Occupational doses were quantified with OSL dosimeters. • The occupational exposure is 90% below the annual dose limits. [ABSTRACT FROM AUTHOR]

Occupational radiation exposure can occur due to various human activities, including the use of radiation in medicine. Occupationally exposed personnel surpassing 7.4 millions, and respresent the biggest single group of employees who are exposed to artificial radiation sources at work. This study compares the occupational radiation dose levels for 145 workers in four different hospitals located in the Aseer region in Saudi Arabia. The occupational exposure was quantified using thermoluminescence dosimeters (TLD-100). The levels of annual occupational exposures in targeted hospitals were calculated and compared with the levels of the international atomic energy agency (IAEA) Safety Standards. An average yearly cumulative dose for the two consecutive years. The average, highest and lowest resulted occupational doses under examination in this work is 1.42, 3.9 mSv and 0.72 for workers in various diagnostic radiology procedures. The resulted annual effective dose were within the IAEA approved yearly dose limit for occupational exposure of workers over 18, which is 20 mSv. Staff should be monitored on a regular basis, according to current practice, because their annual exposure may surpass 15% of the annual effective doses. • Annual occupational dose (Hp(10) were evaluated at four diagnostic radiology department. • Staff doses represent approximately 15% of the annual effective dose. • Students and trainees should be monitored on a regular basis, according to current practice. • Occupational exposure is comparable with the most previously published studies. [ABSTRACT FROM AUTHOR]

Exposure to ionizing radiation may induce cancer risk to the patients proportional to the radiation absorbed dose and the organ sensitivity. Therefore protection of radiation exposure is essential to minimize the radiation cancer risk and prevent the deterministic effects. The International Atomic Energy Agency (IAEA) encourages member countries to establish national diagnostic reference levels (DRLs) to reduce unjustified radiation exposure. This study establishes a local DRL for computed tomography (CT) abdomen and pelvis procedures. In total, 1444 CT abdomen procedures were carried out during nine months. CT abdomen procedures were carried out at King Faisal Specialist Hospital and research center using six CT machines from different vendors. The mean and range of patients' weight (kg) are 50 (42–120). The recommended DRLs values in DLP (mGy.cm) and CTDIvol (mGy) were 900 and 15 per CT abdomen and pelvis procedure, respectively. 3% (41 cases) were higher than the national DRL for CT abdomen and pelvis. The proposed DRL values are slightly higher than the European and the American College of Radiologists (ACR) DRL values in DLP. The purpose of DRL in terms of CTDIvol (mGy) is comparable with the international guidelines. Thus reducing the scan length, is recommended ensuring that patients receive a minimal possible radiation dose while maintaining the image quality. • Patient radiation was calculated for CT abdomen examinations. • Six multi-detector CT machines 64, 128, 384 and 256 (three machines) were used. • 3% (41 cases) were higher than the national DRL for CT abdomen and pelvis. • The proposed DRL is higher than previously reported values in Europe. [ABSTRACT FROM AUTHOR]

Computed tomography (CT) is the leading source of the cumulative effective doses to the general populace from medicinal and artificial sources. With the increased use of CT examinations comes the concern regarding the health effects of unnecessary radiation exposure and the need to optimize the doses that patients receive. The current study evaluates the patients' doses during specific CT procedures and establishes institutional diagnostic reference levels (DRLs) for the frequent CT scans performed. 8156 CT scan examinations were performed during three years from 2015 to 2018 using a single CT scan machine at our institution. Data from the six most common examinations were analyzed. The volume CT dose index (CTDIvol (mGy)) and dose length product (DLP) distribution's median and 75th percentile values were computed. The results were descriptively compared with DRLs from different countries and regions. The six most common examinations constituted 5815 studies. We established our DRLs as the median value of CTDIvol (mGy)| and DLP (mGy × cm) as follows: CT of the brain: 35.0 mGy and 839 mGy × cm, respectively; chest with contrast: 4 mGy and 148 mGy-cm, respectively; chest without contrast: 5 mGy and 190 mGy-cm, respectively; abdomen and pelvis with contrast: 8 mGy and 636 mGy-cm, respectively; abdomen and pelvis without contrast 8 mGy and 568 mGy-cm, in that order; abdomen, pelvis, and kidneys: 11 mGy and 458 mGy × cm, respectively. Our values for brain and chest CTs were lower than the international DRLs, while those for abdominal imaging were higher. The established DRLs offer an opportunity for us to optimize the dose delivered to patients and compare them to the national benchmarks when they are issued. The study revealed that CT dose showed wide discrepancies for the same procedures at the department levels suggesting that the practice was neither optimized nor harmonized. Therefore, DRL should be reassessed after the operators' training and awareness to reduce the patients' dose and related radiogenic risk to its minimal value. • DRL was quantified for six standard CT examinations. • The study revealed that CT dose showed wide discrepancies for the same procedures. • The proposed DRLs are within the international values. • DRL should be reassessed after the technologists' training on imaging protocol optimization. [ABSTRACT FROM AUTHOR]

The pathology of the urinary system is usually investigated using Intravenous Urography (IVU). The study objectives are to quantify patients' radiation dose and radiation induced malignant tumors risk during IVU examination. The radiation doses during IVU and the subsequent risks from exposure are studied, using data from 50 patients imaged in one hospital. The demographic data given as (mean ± std) was as follows:The age of patients was 39 ± 14 years; height of patients was 1.7 ± 0.1 m, the mass was 69 ± 10 kg and the body-mass-index was 24.3 ± 4.1 kg m−2. The physical exposure parameters recorded were: kVp: 74.04 ± 3.1, mAs: 33.64 ± 4. Moreover, the average number of films per procedure was 5.72 ± 1.49. The entrance-surface air kerma (ESAK) was 2.1 ± 0.64 mGy, and the mean effective dose was 0.131 ± 0.04 mSv. Calculation of the overall cancer risk yielded 5.9 × 10−6 procedures. ESAK (mGy) and effective dose values obtained in this study were comparable with reported studies as shown in the text. The effective and cancer risk are around ten times lower during IVU procedures than for example, contrast enhanced computed tomography urography (CTU) examination. Reduction of doses received by patients to meet the values of the diagnostic reference levels without compromising the quality and clarity of the images is highly recommended. Radiation dosimetry; IVU; Radiology; Cancer risk; medical imaging. • The radiation doses during IVU and the subsequent risks from exposure are studied. • The entrance-surface air kerma (ESAK) and effective dose were quantified. • Calculation of the overall cancer risk yielded 5.85 per million procedures. • Patients received higher doses due to unoptimized imaging protocol. [ABSTRACT FROM AUTHOR]

A significant source of ionizing radiation for medical use is computed tomography (CT). According to estimates, more than 84 million CT scans are carried out yearly in the US. Because the neck area contains several organs and tissues that are very sensitive to ionizing radiation, such as the thyroid gland, CT for the neck region is commonly done for a variety of clinical causes. This study's goal is to assess the patient doses to radiosensitive organs and effective doses received during the CT neck surgery in the pastAt Riyadh Care Hospital, a multislice CT (MSCT) system (Siemens Somatom Sensation, 64 slices/detector) was used to perform improved CT treatments on a total of 54 patients. Patient ages were 41.5–15.5 years old on average, with a wide variation (21–73). Using computer software based on Monte Carlo simulation, organ and effective dosages were assessed. The International Commission of Radiological Protection (ICRP) risk variables were used to calculate the patient's radiogenic risk for a particular organ. The patients' dose length product (DLP, mGy.cm) for CT neck examination were 993.3 ± 539.5 (267.3–2441.7). The mean and range of volume CT dose per slice (CTDIvol (mGy)) were 1.5 ± 3.9 (3.91–22.55). The overall effective dose (mSv) per procedure is ranged from 1.3 to 11.7 with a mean value 2.8 mSv. Patients' CT neck procedures have been repeated the procedure up to 7 times during the treatment course. The risk of malignancy is 1x10-6 CT procedure. The study showed that patients received wide discrepancies in patients' doses up to 9 times. Optimization of image acquisition protocol and scan length is necessary to reduce the unnecessary risk. • The effective and organ equivalent doses during neck CT procedure were studied. • Lens of the eye, salivary gland and thyroid gland received a high radiation dose. • The overall effective dose (mSv) per procedure is ranged from 1.3 to 11.7 • Patients' CT neck procedures have been repeated the procedure up to 7 times during the treatment course. [ABSTRACT FROM AUTHOR]

Artificial radiation is the primary radiogenic risk source to the general population. Medical field has been growing in Sudan. This study aims to estimate effective doses for adult patients from nuclear medicine examinations. The study involved 685 patients from five different hospitals in Sudan. In total, 300, 196, and 189 patients underwent renal, thyroid, and bone scans. All procedures were carried out using the Tc-99m radionuclide. Effective dose has been estimated using computer software depending on conductive activity. The results show that dose information for patients from thyroid, renal, and bone scan, for thyroid scan the patients' age was 42.82 ± 16.46 years, the patient's weight 68.58 ± 12.82 kg, the activity 4.75 ± 0.543 mCi and the effective dose for thyroid was 2.28 ± 0.26 mSv. For renal scan, the patients' age 45.19 ± 16.36 years, the weight 65.96 ± 13.78 kg, the activity 5.21 ± 1.166 mCi, and the effective dose 0.94 ± 0.211 mSv. For a bone scan, the patients' age was 57.59 ± 14.92 years, the patient's weight was 69.48 ± 13.71 kg, the activity 19.96 ± 2.11 mCi, and the effective dose for bone was 4.208 ± 0.443 mSv. The study revealed that the administered activity is independent of patient weight. Patients received unjustified exposure due to the high amount of administered activity. Implementation of national guidelines is necessary to improve the practice and patient safety. • Effective dose has been estimated for thyroid, renal and bone scan procedures. • Patients received the least effective dose during renal scan procedures. • The study revealed that the administered activity is independent of patient weight, according to the current protocol. • Proper optimization are recommended to save young from potential radiogenic risks. [ABSTRACT FROM AUTHOR]

Occupational exposure to ionizing radiation of medical personnel is very common at radiology and nuclear medicine departments. Strict regulations and guidelines for the exposure of staff working in such departments were regulated by international authorities such as the International Atomic Energy Agency (IAEA), and the International Commission on Radiological Protection (ICRP) as well as national protocols. In order to reduce stochastic effects, for example, radiation induced carcinogenesis, the exposure of staff working at nuclear medicine department should be maintained at levels lower than 20 mSv per year or 100 mSv in five years. The objective of this study is to measure staff radiation dose at four radiology departments in the south region of the Kingdom of Saudi Arabia. Exposures received by a total of 106 staff working at the radiology department were monitored for two consecutive years using calibrated Thermoluminecnt dosimeters (LiF:Mg:Ti (TLD-100). Exposure was then quantified in terms of deep dose: Hp (10). The TLD signal was obtained using an automatic TLD reader (Harshaw 6600). The overall annual dose for staff was 1.4 ± 0.37 (0.67–8.74). The study revealed that the annual radiation exposure in the four-radiology department is below the annual dose limits. However, staff doses could be reduced if proper radiation protection are followed. • Staff annual radiation dose were assessed for radiology technologists for two consecutive years. • Occupational doses were quantified with LiF: Mg, Ti (TLD-100). • 90% of monitored staff received an annual occupational dose below 2.0 mSv. • Radiology technologists are well protected against occupational exposure. [ABSTRACT FROM AUTHOR]

The instrumental neutron activation analysis (INAA) method was combined with the γ − γ coincidence technique to measure Iron (Fe) and Terbium (Tb) concentrations in geological (Montana II Soil) and environmental (Coal Fly Ash) standard materials. The measured concentrations, which agree well with the corresponding certified values, are compared with those obtained from the traditional INAA method. It is demonstrated that employing the γ − γ coincidence technique slightly improves the accuracy of the analysis. Furthermore, the coincidence technique enhances the detection limits of Tb by ∼4.5 and ∼5.5 times in environmental and geological samples, respectively, but has almost no enhancement in those of Fe. The γ − γ coincidence technique therefore does not always promote the analysis quality of the INAA method, but it is effective for analyzing elements whose characteristic γ rays sustain a high Compton background and/or are overlapped with other γ rays. • Apply the gamma – gamma coincidence method to neutron activation analysis. • An analysis of Tb and Fe concentrations in geological and environmental samples. • The coincidence method can slightly improve the accuracy of the analysis. • The coincidence method significantly enhances the detection limit for Tb element. [ABSTRACT FROM AUTHOR]

Image-guided radiation therapy (IGRT) adds an additional imaging radiation dose to existing levels of therapeutic radiation. The extra radiation dose received by organs from multiple conae beam computed tomography (CBCT) scans can increase the probability of the secondary cancer risk. In this study, an effort has been made to assess CBCT dose and image quality for standard pre-sets defined for different organs namely, the chest, pelvis, brain, head and neck, and abdomen. The second goal was to investigate whether the radiation dose could be reduced while still achieving high image quality. Image quality was evaluated on the CatPhan Model 503 (Phantom Lab, NY), while organ kV- CBCT doses were evaluated using an Unfors device (Fluke Biomedical) to provide representative measurements for clinical settings. Nominal CBCT projections with reduced exposure times were reconstructed in 3D using the Unfiltered and Filtered-back Projection algorithms. Patient organ dose (mGy) per procedure for brain, chest, pelvis, abdomen, and head and neck were 7.9, 35.3, 28.1, 58.3, and 0.77, respectively. The experimental analysis suggests that adequate image quality could be obtained while decreasing the number of radiographic projections. Reducing the number of the radiographic projections will reduce the scan time and therefore the imaging dose. The proposed method provides an opportunity to reduce the organ doses comparatively lower than the standard CT doses for head and body protocols. The study provides a framework for delivering low radiation doses to critical organs with no risk of long-term exposure. • This study has successfully quantified CBCT doses for some critical organs. • Image quality and radiation dose were evaluated during CBCT. • Adequate image quality could be obtained while decreasing the number of radiographic projections. • The study provides a framework for delivering low radiation doses to critical organs with no risk of long-term exposure. [ABSTRACT FROM AUTHOR]

Current work reports the excellent antibacterial and antioxidant activities of the hexagonal boron nitride nanoparticles (10BNNPs) synthesized with enriched-Boron (10B) in a horizontal dual-zone quartz tube furnace. The antibacterial activities of the as-synthesized 10BNNPs are tested by using the well-diffusion technique. According to the antibacterial results, it has been found that 10BN-NPs are highly responsive to K. pneumoniae and least responsive to P. aeruginosa bacterial strains. The antioxidant activity of 10BNNPs is analyzed by scavenging free radicals of 2,2–diphenyl–1–picrylhydrazyl hydrate (DPPH) with time interval and variation in concentration of 10BN-NPs. The activity of DPPH scavenging of 10BNNPs is observed by UV and visible light Spectrophotometer. The results show that the antioxidant potential of 10BNNPs is up to 79.5%. In addition, the 10B-contents with a semiconductor nature, the synthesized 10BNNPs offer a great potential to be used in Boron neutron capture therapy (BNCT) for tumor cells destruction and as a sensing element in a solid-state neutron detector. (a) 10B-enriched Hexagonal Boron nitride nanoparticles are synthesized. (b) The synthesized sample tested for antibacterial showed that K. pneumoniae was the most responsive to 10BNNPs, while P. aeruginosa had the least response. (c) The antioxidant activity results show that the antioxidant potential of 10BNNPs is up to 79.5%. (d) Being 10B-enriched and wide band gap, 10BNNPs can be an excellent choice in Boron-neutron capture therapy as well as a neutron sensing element in a solid-state neutron detector. [Display omitted] • 10B-enriched Hexagonal Boron nitride nanoparticles are synthesized. • K. pneumoniae is found highly responsive to 10BN-NPs, than P. aeruginosa. • The antioxidant potential of 10BN-NPs is up to 79.5 %. • 10BN-NPs can be an excellent choice as a neutron sensing element in a solid-state neutron detector. [ABSTRACT FROM AUTHOR]

In interventional radiology attendant staff can be exposed to significant doses from the radiation scattered from the patient, giving rise to heterogeneous energy distribution, exposure occurring over extended periods of time. Protection of staff is a prime concern, also including reducing the risk of carcinogenesis. With only limited published studies available, as in for instance in regard to lens opacifications, further evaluation of staff exposures and assessment of radiation protection techniques and measures are crucial. Present study has sought to evaluate staff radiation exposure in a radiology department that performs interventional procedures. Annual occupational exposures were obtained for 32 personnel (6 females and 26 males) in a radiology department at a tertiary hospital. Personal dose equivalent H p (d) was measured in terms of H p (0.07) (shallow dose) and H p (10) (deep dose). The measurements were made over a period of two consecutive years, 2017 and 2018, use being made of TLD-100 thermoluminescent dosimeters. In units of mSv, the corresponding average annual dose equivalent and range for H p (10) and H p (0.07) were 4.6 ± 7.0 (0.1–25.5) and 5.1 ± 7.3 (0.1–25.5). Notably, 16% of staff received doses that were greater than the annual dose limit. Since H p (10) offers a conservative evaluation of effective dose, evaluation of the working environment is necessary in seeking to ensure dose values remain below annual dose limits. • Occupational exposure was measured at interventional radiology department. • Personal dose equivalent (H p (d) were measured in terms of H p (0.07) (shallow dose) and H p (10) (deep dose) were evaluated. • Staff exposures were measured using TLD-100 thermoluminecent dosimeters. • 16% of the staff received doses that were greater than the annual dose limit. • Variation in staff dose is due to workload and type of the procedure. [ABSTRACT FROM AUTHOR]