Search

Objectives During computed tomography (CT), a large amount of ionizing radiation is emitted to ensure high quality of the obtained radiological image. This study measured the dose distribution around the CT scanner and the exposure of people staying near the CT scanner during the examination. Material and Methods The measurements used an anthropomorphic phantom to assess human exposure to ionizing radiation. The probability of inducing leukemia and other cancers as a result of absorbing doses recorded around the CT device was also calculated. Results The highest exposure to scattered radiation in the proximity of the CT scanner is recorded at the gantry of the tomograph, i.e., 55.7 μGy, and the lowest, below lower detection limit of 6 μGy at the end of the diagnostic table. The whole-body detector placed on the anthropomorphic phantom located at the diagnostic table right next to the CT gantry recorded 59.5 μSv and at the end of the table 1.5 μSv. The average doses to the lenses in these locations were: 32.1 μSv and 2.9 μSv, respectively. Conclusions The probability of induction of leukemia or other types of cancer is low, but the need for people to stay in the examination room during a CT examination should be limited to the necessary minimum. Int J Occup Med Environ Health. 2024;37(3):326–34

In the next decade, the International Commission on Radiological Protection (ICRP) will issue the next set of general recommendations, for which evaluation of relative biological effectiveness (RBE) for various types of tissue reactions would be needed. ICRP has recently classified diseases of the circulatory system (DCS) as a tissue reaction, but has not recommended RBE for DCS. We therefore evaluated the mean and uncertainty of RBE for DCS by applying a microdosimetric kinetic model specialized for RBE estimation of tissue reactions. For this purpose, we analyzed several RBE data for DCS determined by past animal experiments and evaluated the radius of the subnuclear domain best fit to each experiment as a single free parameter included in the model. Our analysis suggested that RBE for DCS tends to be lower than that for skin reactions, and their difference was borderline significant due to large variances of the evaluated parameters. We also found that RBE for DCS following mono-energetic neutron irradiation of the human body is much lower than that for skin reactions, particularly at the thermal energy and around 1 MeV. This tendency is considered attributable not only to the intrinsic difference of neutron RBE between skin reactions and DCS but also to the difference in the contributions of secondary γ-rays to the total absorbed doses between their target organs. These findings will help determine RBE by ICRP for preventing tissue reactions. [ABSTRACT FROM AUTHOR]

The safety and radiological protection in radiotherapy services are essential to ensure the safe use of ionizing radiation for the benefit of patients and involved professionals. Evaluative research on multidisciplinary teams regarding annual training in radiological protection in radiotherapy is scarce. It is crucial to understand how professionals from each area assess the acquired knowledge and apply theoretical precepts in the radiotherapy service. This study aimed to analyze the annual radiological protection training offered in a radiotherapy service, and as specific objectives, to map the knowledge of professionals from each area regarding radiological protection applied during training. This is a qualitative research of the case study type. Data collection occurred through semi-structured interviews, simple observation, and documentary analysis, organized in the ATLAS.ti software version 24. The results indicate significant challenges, including the lack of understanding of basic principles by professionals, the absence of integration between the team and supervisors, and the lack of clear definition of the training format in current regulations. The results were categorized into: professionals' knowledge of radiological protection; training weaknesses; training strengths; suggestions for training delivery methods and topics in radiological protection. More effective educational strategies, along with precise guidance on the training format, emerge as promising solutions to overcome these challenges.

The exacerbated increase in the use of ionizing radiation to obtain images, and the risks and standards that exist to preserve the health of those who use it, are not properly taken into account when carrying out radiodiagnostic examinations. The professionals who work in these environments play a decisive role in the performance of their numerous activities within radiodiagnostic services, bearing in mind that any dose of radiation is associated with a probability of biological effects occurring, no matter how low that dose may be. Thus, the aim of building a software program was to optimize the work of the multiprofessional and interdisciplinary team in radiodiagnostic services, in the management of radiological protection. This is a methodological and quasi-experimental study carried out in a university hospital in southern Brazil, intentionally chosen because it has a Radiological Protection Committee. This research design was adopted for the development of technological production, in this case software for managing radiological protection. The study was carried out in the radiological protection sector of the radiology department of a university hospital in southern Brazil. The results showed that the software, called SisPRad - Management System for Radiological Protection, is a tool that helps the service's multi-professional and interdisciplinary team in terms of managing radiological protection. Finally, it aims to ensure the safety of professionals working in the service and its users, as well as reducing repetition of activities at management level, and can be adapted for other institutions. The computer registration number 512019002125-8 was obtained from the National Institute of Industrial Property for the first version of the software and the registration number 512023003116-0 for its second version.

The Partner Agencies of the International Space Station (ISS) maintain separate career exposure limits and shared Flight Rules that control the ionising radiation exposures that crewmembers can experience due to ambient environments throughout their space missions. In low Earth orbit as well as further out in space, energetic ions referred to as galactic cosmic radiation (GCR) easily penetrate spacecraft and spacecraft contents and consequently are always present at low dose rates. Protons and electrons that are trapped in the Earth’s geomagnetic field are encountered intermittently, and a rare energetic solar particle event (SPE) may expose crew to (mostly) energetic protons. Space radiation protection goals are to optimize radiation exposures to maintain deleterious late effects at known and acceptable levels and to prevent any early effects that might compromise crew health and mission success. The conventional radiation protection metric effective dose provides a basic framework for limiting exposures associated with human spaceflight and can be communicated to all stakeholders. Additional metrics and uncertainty analyses are required to understand more completely and to convey nuanced information about potential impacts to an individual astronaut or to a space mission. Missions to remote destinations well beyond low Earth orbit (BLEO) are upcoming and bestow additional challenges that shape design and radiation protection needs. NASA has recently adopted a more permissive career exposure limit based upon effective dose and new restrictions on mission exposures imposed by nuclear technologies. This manuscript reviews the exposure limits that apply to the ISS crewmembers. This work was performed in collaboration with the advisory and guidance efforts of International Commission on Radiological Protection (ICRP) Task Group 115 and will be summarized in an upcoming ICRP Report.

The Partner Agencies of the International Space Station (ISS) maintain separate career exposure limits and shared Flight Rules that control the ionising radiation exposures that crewmembers can experience due to ambient environments throughout their space missions. In low Earth orbit as well as further out in space, energetic ions referred to as galactic cosmic radiation (GCR) easily penetrate spacecraft and spacecraft contents and consequently are always present at low dose rates. Protons and electrons that are trapped in the Earth's geomagnetic field are encountered intermittently, and a rare energetic solar particle event (SPE) may expose crew to (mostly) energetic protons. Space radiation protection goals are to optimize radiation exposures to maintain deleterious late effects at known and acceptable levels and to prevent any early effects that might compromise crew health and mission success. The conventional radiation protection metric effective dose provides a basic framework for limiting exposures associated with human spaceflight and can be communicated to all stakeholders. Additional metrics and uncertainty analyses are required to understand more completely and to convey nuanced information about potential impacts to an individual astronaut or to a space mission. Missions to remote destinations well beyond low Earth orbit (BLEO) are upcoming and bestow additional challenges that shape design and radiation protection needs. NASA has recently adopted a more permissive career exposure limit based upon effective dose and new restrictions on mission exposures imposed by nuclear technologies. This manuscript reviews the exposure limits that apply to the ISS crewmembers. This work was performed in collaboration with the advisory and guidance efforts of International Commission on Radiological Protection (ICRP) Task Group 115 and will be summarized in an upcoming ICRP Report. [ABSTRACT FROM AUTHOR]

This article presents the development, advancements, challenges and achievements of the "Optimization of Protection in Pediatric Interventional Radiology in Latin America and the Caribbean" (OPRIPALC) program. This international initiative is led by the World Health Organization, the Pan American Health Organization and the International Atomic Energy Agency. The main objectives of OPRIPALC are to foster a culture of radiological protection in pediatric interventions, enhance these procedures' quality, and define optimization strategies such as the use of diagnostic reference levels (DRLs). Currently, 33 centers from 12 countries participate actively in the program. Significant progress has been made towards the proposed objectives, overcoming the challenges posed by the COVID-19 pandemic. Through many virtual meetings for coordination, planning, training and follow-up, a comprehensive set of DRLs for both diagnostic and therapeutic procedures, categorized by weight and age, have been established and are in use. A consensus document on good practices is in the final stage of development. The program's continuation into at least a second phase is essential to address pending issues, including the integration of automatic dose management systems, the levels of occupational radiation doses, their correlation with pediatric patient doses, and strategies to reduce them. [ABSTRACT FROM AUTHOR]

Introduction: in general, spine surgeons seek to minimize soft tissue damage by using less invasive approaches, which causes them to use intraoperative images much more frequently than other surgical specialties; therefore, they are at increased risk of radiation exposure. Objective: the aim of this work was to analyse the amount of radiation to which the spine surgeon is exposed in different scenarios. Material and methods: a prospective study with a descriptive, longitudinal non-randomized data source. We carried out this study in the period from 2015 to 2019, the radiologic protection consisted in lead apron, thyroid shield and leaded glasses, there were 10 badge dosimeters. Results: only 4 dosimeters were included in the study, the other six were excluded. During the study period one surgeon suffered thyroid cancer and other suffered of liposarcoma. In the protected group were two surgeons, in the group of aleatory exposition was one surgeon and in the unprotected group was one surgeon. In the study the dosimeter in the unprotected group received more amount of radiation in all the years, we did an inferential analysis per year related with the number of surgeries without significant correlation, we attribute this result because we didn't classified the type of surgery realized by each surgeon. Conclusion: we conclude that the spine surgeon must apply the primary methods of radiological protection and that the unprotected spine surgeon receives more amount of radiation in comparison of the protected ones. [ABSTRACT FROM AUTHOR]

The National University Hospital of Iceland stored Ra-226 disused radioactive sources. The Icelandic Radiation Safety Authority requested assistance to the International Atomic Energy Agency (IAEA) for the conditioning of these sources. The IAEA opened a tender and the Radiation Protection and Hygiene Center (CPHR) presented an offer that was approved. The objective was to condition the disused sources to allow for safe storage, awaiting further management by the Hospital. The conditioned sources would be sent to a foreign company for recycling. The sources were characterized and conditioned in a Special Form Capsule for transportation. The operations were carried out safely and under the License granted to the National University Hospital by the Regulatory Body and with the supervision of the IAEA. The capsule with the Ra-226 sources was safely stored at the Department of Oncology ready to be transported. [ABSTRACT FROM AUTHOR]

The paper focuses on a high-priority subject nationwide: the growing need for training in radiation protection for occupationally exposed workers and the strength of having specialized web portals on this matter. The Specialized Web Portal, EDUCPRA "Cuba's Portal for Education and Training in Radiological Protection", has been developed in this context, which makes available to its users, in an easy and integrated way, access to contents, regulations, national and international standards, directories, applications and services related to the matter that allow the identification, dissemination, and promotion of the training capacities in radiation protection. The main objective of EDUCPRA is to become the technological support of the National Strategy for Education and Training in Radiological Protection. EDUCPRA allows supervising the operation of the education and training activity in Radiological Protection in Cuba, and contributing to the processes of identification of needs, certification of personnel, and competence recognition of radiation protection courses. Through EDUCPRA, the available capacities to the country can be promoted to be able to comply with the training requirements established in the national regulatory framework, and the number of personnel trained by practice and occupational category can be known, allowing the evaluation of the effectiveness of the national training program. EDUCPRÁ will give visibility to the performance indicators of the training in Radiological protection in the country. [ABSTRACT FROM AUTHOR]

Copyright of Journal for Technology in Theory & Practice / Zeitschrift für Technikfolgenabschätzung in Theorie und Praxis (TATuP) is the property of Oekom Verlag GmbH and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)

Objectives While working with cyclotrons used for the production of radiopharmaceuticals, workers can experience significant exposure to the adverse effects of ionizing radiation. The aim of this paper was to determine the typical level of such exposure received by such personnel while servicing cyclotrons. Material and Methods Exposure was assessed using TLD detectors placed in an anthropomorphic phantom, as well as dose meter to determine whole body and eye lens exposure. The phantom was placed in locations receiving the greatest exposure to ionizing radiation during service activities. The time spent by employees during servicing was assessed based on routine visits by service technicians. The obtained results were compared with readings of detectors worn by employees during service activities. Results The highest equivalent doses in the thoracic area were found to be received by the lungs (211.16 μSv/year). In the head and neck area, the highest dose was measured in the eye lens (3410 μSv/year). The effective dose for the whole body was found to be 1154.4 μSv/year, based on the phantom, and 149 μSv per service visit (1192 μSv/year), based on the dose meters carried by the workers. Conclusions Service workers are exposed to significant doses of ionizing radiation, representing a clear radiological protection issue. To reduce exposure to eye lenses, it is recommended to use protective goggles when working with highly-radioactive elements. Int J Occup Med Environ Health. 2022;35(6):753–60

The interest in radiation protection in industrial sectors involving Naturally Occurring Radioactive Materials (NORM) is increasingly growing. This is due also to the recent implementation of the European Council Directive 59/2013/Euratom which in Italy and in the other European Union Member States extends the field of application to industrial sectors never involved before. This paper reports main results of a research project on radiation protection in industries involving NORM carried out in Italy aimed to provide useful tools for stakeholders to comply new legal obligations. The project activities were mainly focused on different aspects relevant to the NORM involving industries, accounting for the positive list reported in the Italian law. Firstly, the inventory of the industries currently operating in Italy in order to identify the industrial sectors with an important radiological impact on population and workers was updated. Based on this information, a general methodology was elaborated taking into account a graded approach. The first phase consists in the identification and characterization of the most critical exposure scenarios and of the radiological content of NORMs involved in the different phases of the industrial processes. In the second phase calculation methods were developed for dose estimation for workers and members of public. These tools require the use of existing and well tested calculation codes, and the development of a dedicated user-friendly software. [ABSTRACT FROM AUTHOR]

In public discussion, high-level nuclear waste is often referred to as an exceptional environmental problem. It is indeed an exceptional problem, but not primarily because of the permanent threat that nuclear waste poses to future generations, as is usually argued. Its exceptionality rather stems from socio-technical factors that create deadlocks and dilemmas, thus hampering and delaying decision-making. This article provides an overview of major socio-technical issues pertaining to nuclear waste, including some that have been neglected in previous literature, and thus contributes to technology assessment in this field.

This article presents the development, advancements, challenges and achievements of the “Optimization of Protection in Pediatric Interventional Radiology in Latin America and the Caribbean” (OPRIPALC) program. This international initiative is led by the World Health Organization, the Pan American Health Organization and the International Atomic Energy Agency. The main objectives of OPRIPALC are to foster a culture of radiological protection in pediatric interventions, enhance these procedures’ quality, and define optimization strategies such as the use of diagnostic reference levels (DRLs). Currently, 33 centers from 12 countries participate actively in the program. Significant progress has been made towards the proposed objectives, overcoming the challenges posed by the COVID-19 pandemic. Through many virtual meetings for coordination, planning, training and follow-up, a comprehensive set of DRLs for both diagnostic and therapeutic procedures, categorized by weight and age, have been established and are in use. A consensus document on good practices is in the final stage of development. The program’s continuation into at least a second phase is essential to address pending issues, including the integration of automatic dose management systems, the levels of occupational radiation doses, their correlation with pediatric patient doses, and strategies to reduce them.

When handling unsealed radioactive sources, radiological protection attention must be taken to avoid unnecessary exposure and radioactive contaminations, and an important and necessary practice to prevent such contaminations is the use of gloves when handling these sources. The present work aimed to determine the effectiveness of contamination protection provided by different types of disposable polymeric gloves used in Nuclear Medicine Service in Clinic Hospital of Porto Alegre, testing the main radiopharmaceuticals used at this site: [99mTc]sodium pertechnetate, [18F]FDG and [131I]sodium iodide. The analysis was performed using the wipe test inside gloves intentionally contaminated on the outside with these radiopharmaceuticals. The radiation detector used to measure the contamination was a NaI(Tl) scintillator well-type counter. The results indicate that three types of gloves analyzed protect the user from [99mTc]sodium pertechnetate and [18F]FDG contamination, for permanence times with the glove after contamination for up to 15 min (interval tested). For [131I]sodium iodide, gloves are completely effective in protection as long as they are used for a time interval after contamination of the external surface of up to: Latex – 5 min; Vinyl – 5 min; Nitrile – 10 min. Among them, the nitrile glove are the most effective, since contamination was not observed on the inner face for times equal to or less than 10 min; and, for an interval of 15 min, the percentage of permeation obtained was lower than the other two types: 3.3 times lower than vinyl glove permeation and 1.3 times lower of the latex glove permeation. It was also possible to estimate the skin dose rate due to contamination caused by iodine permeation for each glove case and time tested.

Objectives: Vascular and interventional radiology procedures are characterized by high exposure of personnel to ionizing radiation. This study assessed the exposure of medical personnel to ionizing radiation during vascular radiology and mechanical thrombectomy procedures., Material and Methods: During vascular radiology procedures, the exposure of 4 groups of workers participating in the procedures was analyzed, i.e., the main operating physician, an assistant physician, a sterile nurse, and a nurse. Measurements of exposure to ionizing radiation were performed using thermoluminescent dosimetry., Results: The registered effective dose during 1 treatment in individual groups is, respectively: mean (M) ± standard deviation (SD) 75±15 μSv, 24±5 μSv, 13±3 μSv, and 8±2 μSv. During mechanical thrombectomy, the operating physician receives an effective dose of M±SD 9±2 μSv. The equivalent doses for the lenses for the operating physician and the doctor assisting during vascular radiology procedures are M±SD 1419±285 μSv and 987±198 μSv, respectively, and for the hands, including the left and right hands, M±SD 4605±930 μSv, 1420±284 μSv, 1898±380 μSv, 1371±274 μSv., Conclusions: If the principles of optimizing radiological protection are not applied during vascular radiology procedures, the permissible dose limits and operational limits equivalent to doses to lenses and hands may be exceeded. Exposure during vascular radiology procedures is comparable to exposure during nuclear medicine procedures in terms of the use of glucose labeled with radioactive fluorine. Int J Occup Med Environ Health. 2024;37(4)., (This work is available in Open Access model and licensed under a CC BY-NC 3.0 PL license.)

Objectives: During computed tomography (CT), a large amount of ionizing radiation is emitted to ensure high quality of the obtained radiological image. This study measured the dose distribution around the CT scanner and the exposure of people staying near the CT scanner during the examination., Material and Methods: The measurements used an anthropomorphic phantom to assess human exposure to ionizing radiation. The probability of inducing leukemia and other cancers as a result of absorbing doses recorded around the CT device was also calculated., Results: The highest exposure to scattered radiation in the proximity of the CT scanner is recorded at the gantry of the tomograph, i.e., 55.7 μGy, and the lowest, below lower detection limit of 6 μGy at the end of the diagnostic table. The whole-body detector placed on the anthropomorphic phantom located at the diagnostic table right next to the CT gantry recorded 59.5 μSv and at the end of the table 1.5 μSv. The average doses to the lenses in these locations were: 32.1 μSv and 2.9 μSv, respectively., Conclusions: The probability of induction of leukemia or other types of cancer is low, but the need for people to stay in the examination room during a CT examination should be limited to the necessary minimum. Int J Occup Med Environ Health. 2024;37(3):326-34., (This work is available in Open Access model and licensed under a CC BY-NC 3.0 PL license.)

The interest in radiation protection in industrial sectors involving Naturally Occurring Radioactive Materials (NORM) is increasingly growing. This is due also to the recent implementation of the European Council Directive 59/2013/Euratom which in Italy and in the other European Union Member States extends the field of application to industrial sectors never involved before. This paper reports main results of a research project on radiation protection in industries involving NORM carried out in Italy aimed to provide useful tools for stakeholders to comply new legal obligations. The project activities were mainly focused on different aspects relevant to the NORM involving industries, accounting for the positive list reported in the Italian law. Firstly, the inventory of the industries currently operating in Italy in order to identify the industrial sectors with an important radiological impact on population and workers was updated. Based on this information, a general methodology was elaborated taking into account a graded approach. The first phase consists in the identification and characterization of the most critical exposure scenarios and of the radiological content of NORMs involved in the different phases of the industrial processes. In the second phase calculation methods were developed for dose estimation for workers and members of public. These tools require the use of existing and well tested calculation codes, and the development of a dedicated user-friendly software.

Since the COVID-19 outbreak, diagnostic imaging has been providing valuable radiological support for disease diagnosis and prognosis prediction. Radiological staff, especially radiographers working on the front line in the battle against the COVID-19 outbreak. They are in direct contact with the patients, bearing the responsibility and pressure of both the infection prevention and control and the radiation protection. A number of relevant professionals and experts reached a consensus, which clarifies the detailed implementing rules with respective to infection control and protection of the radiation workers, disinfection of diagnostic radiology equipment and workplace, and radiological protection. The aim is to further normalize the clinical procedures of radiological staff, reduce the infection risk, especially the radiation risk to medics and patients.

Antecedents and objective: The knowledge of the reference levels for diagnoses and therapeutic studies is important, because it contributes to the optimization of the radiological protection of the patients, avoiding them to be exposed to unnecessarily high doses. However, there was no evidence of these levels in interventionist cardiology procedures in Ecuador, so the objective of this study was to estimate the diagnostic reference levels of dose at the entrance surface in adult patients under-going interventional cardiology procedures (cinecoronariography, catheterization and coronary percutaneous interventionism) in the Unit of Hemodynamic of the Hospital of Specialties Carlos Andrade Marín in Ecuador. Materials and methods: The measurements of product dose-area, dose in input surface, number of images and the time of fluoroscopy performed using the Axiom Artis angiographer, and the obtained data was tabulated and processed with the Excel computer program. For this study, 145 patients older than 18 years were selected, and the values obtained from diagnostic reference dose levels were compared with others reported in previous investigations and with the permissible limits for the appearance of deterministic effects on the skin. Results: This study made it possible to establish reference levels for diagnosis in interventional cardiology procedures (coronary angiography, catheterization and percutaneous coronary intervention) in the Hemodynamics Unit of the Carlos Andrade Marín Specialty Hospital in Ecuador. Conclusions: The results showed that the intake surface doses obtained were lower than the maximum levels recommended by the International Atomic Energy Agency. [ABSTRACT FROM AUTHOR]

The Distance Learning modality (E-learning) seeks to facilitate access and democratization for all who seek qualification or continuity of studies. Combined with university extension, it can become an excellent tool to promote continuing education in the workplace. This study aimed to report the experience of the team of professors and students of the Higher Course in Technology in Radiology and the Professional Master's Degree in Radiological Protection at the Federal Institute of Santa Catarina (IFSC) in partnership with the Cardiology Institute of Hospital Homero de Miranda Gomes from São José, Santa Catarina, Brazil, during the first edition of a training course via distance learning for the multidisciplinary team of the Nuclear Medicine service. It is an experience report on the development and operation of a university extension course. Of the 307 individuals enrolled in the course, 113 did not start, 77 participants accessed the class schedule, watched the welcome video to the course, but did not watch the video classes or perform any assessment, 116 students performed all the proposed assessments completing the course. Only 1 participant performed the assessments and did not reach an average of 6.0. The outreach action promoted interaction between higher education students, graduate students, teachers, and the external community at national and international levels. Thus, the extension culture in higher education was consolidated, and the awakening of postgraduate courses to integrate with society through extension. [ABSTRACT FROM AUTHOR]

Abstract Background The conventional concept of radiation protection is based on epidemiological studies of radiation that support a positive correlation between dose and response. However, there is a remarkable difference in biological responses at the tissue level, depending on whether radiation is delivered as a uniform or non-uniform spatiotemporal distribution due to tissue sparing effects (TSE). From the point of view of radiation micro-dosimetry, environmental radiation is delivered as a non-uniform distribution, and radiation-induced biological responses at the tissue level, such as TSE, would be implicated in individual risk following exposure to environmental radiation. Hypothesis We hypothesize that the health risks of non-uniform radiation exposure are lower than the same dose at a uniform exposure, due to TSE following irradiation. Testing the hypothesis requires both radiobiological studies using high-precision microbeams and the epidemiological data of environmental radiation-induced effects. The implications of the hypothesis will lead to more personalized approaches in the field of environmental radiation protection. Conclusion The detection of spatiotemporal dose distribution could be of scientific importance for more accurate individual risk assessment of exposure to environmental radiation. Further radiobiological studies on non-uniform radiation-induced biological responses at the tissue level are expected.

The aim of this work is to demonstrate the need to develop more efficient means for radiological protection, making use of the latest automation and robotics technologies. A manipulator model has been developed that has technological differentials that can positively influence the performance and cost of remote manipulation. The built-in equipment has a Slave manipulator, developed without using semiconductor elements. They are housed in the control center, which is attached to the manipulator via umbilical cord, facilitating the equipment adaptation in hot cells and other working environments. The arrangement of the joints and the links, have similarities with the anatomy of the human arm, improving the instinctively of the operation. To demonstrate its technological feasibility, a prototype Master-Slave manipulator was designed, and built using three control programs, which were written exclusively for this work. It was also designed to reduce construction and operation costs, making it accessible to most areas. The results obtained with the prototype construction are shown to be promising, providing an incentive to continue the development of manipulators using similar technologies. The equipment, obtained satisfactory results in relation to the operability, being able to perform movement tasks of loads, as foreseen in the project.

Evaluation of radiation protective devices in radiology departments is one of the practices that ensure radiation protection and staff and patients safety in hospitals. A research work to evaluate 1.5mm lead shield used for radiological protection was carried out in Radiological Unit of Sharda Hospital, of Sharda University, India, using 300mA fixed x-ray machine room. The evaluation was done in the x-ray energy (kVp) range between 52- 81 and by using calculative procedure and by direct measurement of the radiation dose rates. The two results were compared. The results shows that, in the absence of the shield, only 11.82% of the radiation exposure was attenuated by the air space before reaching the radiographer’s stand, while in the presence of the shield, 96.50% was attenuated, whereas, for the measured result only 10.17% was attenuated in the absence of the shield and 89.83% was attenuated in the presence of the shield before reaching the radiographer’s stand. The unit of radiation exposure was converted to that of equivalent dose and that of effective dose in order to assess the radiographer’s safety level behind the shield. It was found that, the equivalent/effective dose is as low as to be accepted according to the policy of ALARA (As Low As Reasonably Achievable), and within the NCRP recommended limit. This guaranteed the effectiveness of the lead shield of 1.5mm thickness in the x-ray energy range used in this study. Keywords: Lead shield, radiological protection, effectiveness of 1.5mm leadshield, presence of shield, absence of shield, radiographer’s safety.

During firefighting and rescue operations there is a high probability that rescuers will come into contact with ionizing radiation and radiation contamination. The firemen of the State Fire Service and the Volunteer Fire Service perform a number of tasks during the action [Obwieszczenie Marszałka Sejmu… 2009], for which they are prepared during exercises and theoretical sessions. A significant reduction in the probability of radiation or radiation contamination risk can be achieved by taking appropriate precautions and following certain rules and procedures. The actions at which ionizing radiation occurs take place very rarely and procedures are regulated by the “Rules of conduct in the event of radiation risk” [Komenda Główna… 2009] annexed to the “Rules of the organization of chemical and environmental rescue in the National Firefighting and Rescue System” [Komenda Główna… 2013]. The aim of this article is to present the possibilities of protecting the rescue team during fire and rescue operations associated with the potential presence of radioactive materials at the scene.

Evaluation of radiation protective devices in radiology departments is one of the practices that ensure radiation protection and staff and patients safety in hospitals. A research work to evaluate 1.5mm lead shield used for radiological protection was carried out in Radiological Unit of Sharda Hospital, of Sharda University, India, using 300mA fixed x-ray machine room. The evaluation was done in the x-ray energy (kVp) range between 52- 81 and by using calculative procedure and by direct measurement of the radiation dose rates. The two results were compared. The results shows that, in the absence of the shield, only 11.82% of the radiation exposure was attenuated by the air space before reaching the radiographer's stand, while in the presence of the shield, 96.50% was attenuated, whereas, for the measured result only 10.17% was attenuated in the absence of the shield and 89.83% was attenuated in the presence of the shield before reaching the radiographer's stand. The unit of radiation exposure was converted to that of equivalent dose and that of effective dose in order to assess the radiographer's safety level behind the shield. It was found that, the equivalent/effective dose is as low as to be accepted according to the policy of ALARA (As Low As Reasonably Achievable), and within the NCRP recommended limit. This guaranteed the effectiveness of the lead shield of 1.5mm thickness in the x-ray energy range used in this study. [ABSTRACT FROM AUTHOR]

Through radiation measurement of the patients after brachytherapy with radioiodine seeds for malignant tumor at different distances and shielding condition, the importance, optimization and individualization of the radiological protection are well recognized. The 35 patients were randomly selected in the minimally invasive interventional ward of Peking University Shenzhen Hospital who underwent brachytherapy for malignant tumor with radioiodine seeds. Within 2 hours after the brachytherapy, the radiation of the patients without shielding, with 0.25 mmPb and 0.5 mmPb shielding were detected by an x-γ ray detector at different distances (equivalent dose rate). The results were analysed by SPSS19.0 t test. Annual equivalent dose was calculated by the average close contact time (two hours everyone per day). The average annual equivalent dose of the 35 patients without shielding was below 20 mSv at 0.5 meter, close to the public limit 1 mSv at 2 meters and equivalent to the background at 4 meters. Under 0.25 mmPb shielding, 6 patients’ radiation was still above the pubic limit, although the average radiation of the 35 patients was below the pubic limit; under 0.5 mmPb shielding, all patients’ radiation was nearly equivalent to the background at 0 meter. The results showed that among the time, distance and shielded protection, the individual radiological protection was especially important. The 0.25 mmPb lead cushion was the most commonly used shield. The 0.5 mmPb lead cushion also should be used in case of the large number of radioiodine seeds implantation and/or more superficial implant site, so as to ensure the individualization and optimization in radiological protection.

Background: Occupational exposure to ionising radiation poses potential health risks to radiation workers unless adequate protection is in place. The catheterisation laboratory is a highly contextualised workplace with a distinctive organisational and workplace culture. Objective: This study was conducted to understand the culture of radiation protection (CRP). Methods: This study was a qualitative study and data were collected through 30 in-depth and 6 group interviews with 54 purposively selected South African interventionalists (interventional radiologists and cardiologists). The participants included a diversity of interventionalists who varied in sex, geographic location and years of experience with fluoroscopy. The transcribed data were analysed thematically using a deductive and inductive approach. Results: ‘Culture of radiation protection’ emerged as a complex theme that intersected with other themes: ‘knowledge and awareness of radiation’, ‘radiation safety practice’, ‘personal protective equipment (PPE) utilisation’ and ‘education and training’. Conclusion: Establishing and sustaining a CRP provides an opportunity to mitigate the potentially detrimental health effects of occupational radiation exposure. Education and training are pivotal to establishing a CRP. The time to establish a culture of radiation in the catheterisation laboratory is now.

Copyright of Momento: Revista de Física is the property of Universidad Nacional de Colombia, Departamento de Fisica and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)

Radiological protection of the environment has been intensively discussed in recent years. Much progress has been made recently with regard to the development of models: (i) to estimate the uptake of radionuclides by flora and fauna in different habitats and ecosystems; (ii) to calculate internal and external exposures for a wide range of terrestrial and aquatic organisms; and (iii) in investigating and analyzing the effects of radiation exposures to biota. This paper gives an overview of the current status of this work. Furthermore, the current status of the integration of environmental protection into the radiation protection system is also summarized.

Copyright of Archives of Dental Science / Arquivos em Odontologia is the property of Universidade Federal de Minas Gerais, Faculdade de Odontologia and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)

Introduction: in general, spine surgeons seek to minimize soft tissue damage by using less invasive approaches, which causes them to use intraoperative images much more frequently than other surgical specialties; therefore, they are at increased risk of radiation exposure., Objective: the aim of this work was to analyse the amount of radiation to which the spine surgeon is exposed in different scenarios., Material and Methods: a prospective study with a descriptive, longitudinal non-randomized data source. We carried out this study in the period from 2015 to 2019, the radiologic protection consisted in lead apron, thyroid shield and leaded glasses, there were 10 badge dosimeters., Results: only 4 dosimeters were included in the study, the other six were excluded. During the study period one surgeon suffered thyroid cancer and other suffered of liposarcoma. In the protected group were two surgeons, in the group of aleatory exposition was one surgeon and in the unprotected group was one surgeon. In the study the dosimeter in the unprotected group received more amount of radiation in all the years, we did an inferential analysis per year related with the number of surgeries without significant correlation, we attribute this result because we didn't classified the type of surgery realized by each surgeon., Conclusion: we conclude that the spine surgeon must apply the primary methods of radiological protection and that the unprotected spine surgeon receives more amount of radiation in comparison of the protected ones.

Múltiples trabajos se han publicado en los últimos años orientados a disminuir las dosis de irradiación en niños. La experiencia en sobrevivientes japoneses de la bomba atómica, que recibieron bajas dosis, dentro del espectro de la radiología diagnóstica, demostró que ellas se asocian a un pequeño, pero significativo aumento en la incidencia de tumores. El mayor efecto de las radiaciones en niños nos obliga a tomar medidas necesarias para racionalizar su uso especialmente el de la TC, método que aporta las mayores dosis. Estas medidas se pueden resumir en: 1.- Selección adecuada por parte del clínico de los casos que se van a beneficiar con el método. 2.- Disminuir los factores de exposición. 3.- Dirigir el examen sólo al área que es necesario estudiar. 4.- Salvo excepciones, realizar estudios de TC monofásicos. 5.- Protección de órganos superficiales. 6.- Instructivo para padres y público en generalMany reports have been publicated in the past few years orientate to reduce the irradiation dose in children. It was compared with survivors of the atomic bomb in Japan. The ones who received low doses, in order to the 10 to 50 mSv, levels that left inside of diagnostic radiology spectrum, and in asociation in a small but significant increase in the tumors incidence. The major radiosensibility of children, obligate us to take, the necessary measure to rationalize the use of ionization radiation in pediatric, in special the CT, wich is the method that gives the higher doses. This measures can be abridge to: 1. - Select properly the cases that are going to be benefit whit the method trough the pediatrician. 2.- Reduce the exposition factors. 3.- Direct the exam only to the specific study area. 4.- Except special cases, perform only single phase studies. 5. Protection for superficial organs. 6. Deliver information for parents and general public