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Purpose: The purpose of this paper is to provide an overview of the methodology used to estimate radiation genetic risks and quantify the risk of hereditary effects as outlined in the ICRP Publication 103. It aims to highlight the historical background and development of the doubling dose method for estimating radiation-related genetic risks and its continued use in radiological protection frameworks. Results: This article emphasizes the complexity associated with quantifying the risk of hereditary effects caused by radiation exposure and highlights the need for further clarification and explanation of the calculation method. As scientific knowledge in radiation sciences and human genetics continues to advance in relation to a number of factors including stability of disease frequency, selection pressures, and epigenetic changes, the characterization and quantification of genetic effects still remains a major issue for the radiological protection system of the International Commission on Radiological Protection. Conclusion: Further research and advancements in this field are crucial for enhancing our understanding and addressing the complexities involved in assessing and managing the risks associated with hereditary effects of radiation. [ABSTRACT FROM AUTHOR]

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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

Copyright of Revista Foco (Interdisciplinary Studies Journal) is the property of Revista Foco 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.)

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]

Calibration of 22 gamma camera units was performed at 15 hospitals in southern and western Sweden to estimate 137Cs contamination in humans in a supine static geometry, with a new developed calibration protocol and phantom. The minimum detectable activities (MDAs) and the estimated committed effective doses (CEDs) were calculated for each calibration. Generic calibration factors were calculated for five predetermined groups based on the detector type and manufacturer. Group 1 and 2 included NaI-based gamma cameras from General Electrics (GEs) with a crystal thickness of 5/8′′ and 3/8′′ respectively. Group 3 and 4 included NaI-based gamma cameras from Siemens Healthineers with a crystal thickness of 3/8′′, with a similar energy window as the GE NaI-based cameras and a dual window respectively. Group 5 included semiconductor-based gamma cameras from GE with a CdZnTe (CZT) detector. The generic calibration factors were 60.0 cps kBq−1, 52.3 cps kBq−1, 50.3 cps kBq−1, 53.2 cps kBq−1 and 48.4 cps kBq−1 for group 1, 2, 3, 4, and 5 respectively. The MDAs ranged between 169 and 1130 Bq for all groups, with measurement times of 1–10 min, corresponding to a CED of 4.77–77.6 μ Sv. A dead time analysis was performed for group 1 and suggested a dead time of 3.17 μ s for 137Cs measurements. The dead time analysis showed that a maximum count rate of 232 kcps could be measured in the calibration geometry, corresponding to a CED of 108–263 mSv. It has been shown that semiconductor-based gamma cameras with CZT detectors are feasible for estimating 137Cs contamination. The generic calibration factors derived in this study can be used for gamma cameras of the same models in other hospitals, for measurements in the same measurement geometry. This will increase the measurement capability for estimating internal 137Cs contamination in the recovery phase following radiological or nuclear events. [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.

Uranium mining can cause environmental impacts on non-human biota around mine sites. Because of this, the reduction in non-human biota exposure becomes an important issue. Environmental radioprotection results from the evolution of human radioprotection; it is based on dose rate to non-human biota and uses, as a biological target, and has harmful effects on populations. In the present study, a flooded impoundment created following dam construction in a uranium mine plant undergoing decommissioning was investigated. Internal dose rates due to activity concentration of natural uranium (Unat) and 232Th in omnivorous, phytophagous, and carnivorous fish species were estimated. Radionuclide activity concentrations were obtained by spectrophotometry with arsenazo III in the visible range. The dose rate contribution of 232Th was lower than that of Unat. There were no differences between the internal dose rates to studied fish species due to 232Th, but there were differences for Unat. A dose rate of 2.30·10–2 µGy∙d−1 was found due to the two studied radionuclides. Although this value falls below the benchmark for harmful effects, it is important to acknowledge that the assessment did not account for other critical radionuclides from uranium mining, which also contribute to the internal dose. Moreover, the study did not assess external doses. As a result, the possibility cannot be excluded that dose rates at the study area overcome the established benchmarks for harmful effects. [ABSTRACT FROM AUTHOR]

Copyright of Revista Foco (Interdisciplinary Studies Journal) is the property of Revista Foco 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.)

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]

Twelve years have passed since the Great East Japan Earthquake and Fukushima Daiichi Nuclear Power Station accident (Fukushima nuclear accident) occurred in March 2011. In addition to direct deaths from the disaster itself, various risk issues have arisen, including disaster-related deaths, radiation exposure, secondary physical and psychological health effects due to evacuation and lifestyle changes, and economic impact. It also highlighted the importance of a multifaceted and integrated approach to risk assessment, management, and communication. The diverse and intertwined risk challenges and approaches to resolving them presented lessons and perspectives on risk governance. This manuscript reports on the 2023 spring symposium titled “Discussing the present from Fukushima: A panoramic view of the lessons and perspectives for risk governance.” We discussed topics related to the International Commission on Radiological Protection recommendations for radiological protection in the accident and its challenges, a summary of secondary health effects after the Fukushima nuclear accident, efforts toward sustainable management and disposal of removed soil and other materials, and the involvement of various stakeholders. [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]

Cone-beam computed tomography (CBCT) allows three-dimensional evaluation and has high diagnostic accuracy of endodontic conditions. Considering that the most indicated protocol for endodontics should have smaller field-of-view and higher spatial resolution, a higher radiation dose may be associated. Thus, this study evaluated the accuracy of an optimized CBCT protocol for the detection of intraoperative endodontic complications. An image phantom was custom-made with a human mandible covered with Mix-D and forty mandibular first molars. The teeth were subdivided into 4 groups of endodontic complications which were simulated. All teeth were individually inserted into the left second molar socket of the phantom and CBCT images were acquired with OP 300 unit adjusted to a field-of-view of 6 × 4 cm, 90kVp, and 2 dose protocols: low and high. Furthermore, a titanium implant, a tooth with endodontic treatment, and a cobalt-chromium post were inserted into the empty sockets adjacent to the teeth of interest and additional images were acquired. Four endodontists evaluated the images and indicated the presence of endodontic complications on a 5-point scale. Sensitivity, specificity, and area under the receiver operating characteristic curve were obtained. The different groups were compared by ANOVA and Tukey tests (α = 0.05). In most conditions, irrespective of the presence of metallic materials, the values of accuracy, sensitivity, specificity, and area under the receiver operating characteristic curve did not differ significantly (P >.05) between the dose protocols. Optimized CBCT protocols should be considered for the detection of intraoperative endodontic Diagnostic complications. [ABSTRACT FROM AUTHOR]

Copyright of Die Urologie is the property of Springer Nature 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. [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]

Ionising radiation has been used for over a century for peaceful purposes, revolutionising health care and promoting well-being through its application in industry, science, and medicine. For almost as long, the International Commission on Radiological Protection (ICRP) has promoted understanding of health and environmental risks of ionising radiation and developed a protection system that enables the safe use of ionising radiation in justified and beneficial practices, providing protection from all sources of radiation. However, we are concerned that a shortage of investment in training, education, research, and infrastructure seen in many sectors and countries may compromise society's ability to properly manage radiation risks, leading to unjustified exposure to or unwarranted fear of radiation, impacting the physical, mental, and social well-being of our peoples. This could unduly limit the potential for research and development in new radiation technologies (healthcare, energy, and the environment) for beneficial purposes. ICRP therefore calls for action to strengthen expertise in radiological protection worldwide through: (1) National governments and funding agencies strengthening resources for radiological protection research allocated by governments and international organisations, (2) National research laboratories and other institutions launching and sustaining long-term research programmes, (3) Universities developing undergraduate and graduate university programmes and making students aware of job opportunities in radiation-related fields, (4) Using plain language when interacting with the public and decision makers about radiological protection, and (5) Fostering general awareness of proper uses of radiation and radiological protection through education and training of information multipliers. The draft call was discussed with international organisations in formal relations with ICRP in October 2022 at the European Radiation Protection Week in Estoril, Portugal, and the final call announced at the 6th International Symposium on the System of Radiological Protection of ICRP in November 2022 in Vancouver, Canada. [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]

The International Commission on Radiological Protection (ICRP) is recognised as the de-facto world authority in the field of radiological protection. The ICRP Recommendations have been used as a basis for regulations and policy in almost every country, and with the current review and revision of the System of Radiological Protection, it will continue to make significant contributions in radiation safety for patients, workers, the public, and the environment. In a society undergoing significant change, it is necessary to give careful thought to which groups will be perceived as authoritative organisations by the constituents of the future. The ideal form of an authoritative organisation in the new society of the future is to continue to show how it came to make such recommendations, how it reflected the opinions of interested parties in the process, and how it discloses its records with as much transparency as possible. The question now is what we must do to ensure that decision-making advances in a way that not only makes sense to the present generation, but will be easily consumed by future generations. The path that ICRP is taking to formulate the next set of General Recommendations is doing just that, in line with the key procedural values of I NCLUSIVE, A C COUNTABLE, AND T R ANS P ARENT. [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.

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Following a radiological or nuclear (RN) event, rapid measurement of 131 I in members of the public is of utmost importance, and much equipment is needed for a high throughput. In this study, three gamma cameras (GCs), two thyroid uptake meters (TUMs) and one whole-body counter (WBC) were calibrated for activity measurements of 131 I in the thyroid. Minimum detectable activity was derived for the GCs, the TUMs and the WBC giving that a committed effective dose (CED) in the interval 2.0-85 μ Sv, 13-700 μ Sv and 0.52-6.4 μ Sv, and thyroid absorbed doses in the interval 0.075-2.1 mGy, 0.48-17 mGy, and 0.020-0.15 mGy, respectively, can be assessed for children, adolescents, and adults. These numbers are based on 10 min measurement, performed at 1, 3 and 7 d after intake, and the CED includes intake by ingestion and inhalation of aerosols Type F, with an activity median aerodynamic diameter of 1 μ m. For a fractional signal loss of 63% due to dead time, a CED up to 2.0, 84 and 3.6 Sv and thyroid absorbed dose up to 47 Gy, 2000 Gy and 88 Gy for the three systems, respectively, can be assessed for children and intake by ingestion as a worst-case scenario in terms of CED, measured 7 d after intake. This study demonstrates the potential and limitations of using equipment readily available at larger hospitals for estimation of 131 I content in thyroid, which could increase the measurement capability following an RN event., (Creative Commons Attribution license.)

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.)

Objective: To evaluate the impact of novel shielding curtains combined with pulsed irradiation mode to protect medical radiation workers from radiation exposure during ureteroscopy. Methods: 0.25 mm Pb equivalent novel shielding curtains were mounted to the caudal and bilateral sides of the operating table in the ureteroscopy setting. C‐arm was positioned as per normal in the operating room with the X‐ray tube under the patient table. A water‐filled anthropomorphic renal collecting system phantom was positioned in the standard position on the operating table that was set at a height of 100 cm. The ionization chambers were also positioned at a height of 100 cm and set in eight positions. We took measurements at distances of 50, 100, 150, and 200 cm from the phantom with the focus directed toward the X‐ray tube. We measured the spatial distribution of the scattered radiation dose in four combinations: (1) continuous irradiation mode without novel shielding curtains; (2) pulsed irradiation mode (11 films per second) without novel shielding curtains; (3) continuous irradiation mode with novel shielding curtains; and (4) pulsed irradiation mode with novel shielding curtains. Continuous or pulsed irradiation was activated for 30 s each time. Results: Pulsed irradiation mode with novel shielding curtains was a significantly more efficient method than other combinations to reduce scattered radiation exposure in this study (P < 0.001). There was approximately a 95% reduction in scattered radiation exposure with the pulsed irradiation mode with novel shielding curtains set up as compared with continuous irradiation mode without novel shielding curtains. Conclusion: Combining a novel shielding curtain and using a low pulse radiation setting can greatly reduce radiation exposure during ureteroscopic procedures. [ABSTRACT FROM AUTHOR]

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.

Radiological protection is often considered a matter of scientific and technological facts only, not of value judgements. This perception is now gradually changing, especially with ICRP Publication 138, which addressed the ethical foundation of the system of radiological protection. It identified values which have guided the Commission’s recommendations over the decades, but have not always been made explicit. Four core values are discussed (beneficence/non-maleficence, prudence, justice, dignity) as well as three procedural values (accountability, transparency, inclusivity). The latter are considered critical to the practical implementation of the system of radiological protection. Here we are exploring empathy as a procedural values complementing the three identified in ICRP Publication 138. Empathy can be defined as the ‘capability (or disposition) to immerse oneself in and to reflect upon the experiences, perspectives and contexts of others’. It is often understood as a skill that one either has or has not, but research has shown it can be taught and therefore can be required as an attitude of those working in health care, education, design, and technology. We suggest it is an essential prerequisite to the assessment and management of any radiological situation and the health problems accruing from it. The concerns of people affected, their needs and wishes need to be taken seriously from the very beginning of any decision-making process. Even if they are considered unfounded and exaggerated, the insights they provide will be valuable for the understanding of the overall situation. Without empathy, our practice of beneficence and non-maleficence as well as solidarity would be oddly limited. [ABSTRACT FROM AUTHOR]

In addition to the International Commission on Radiological Protection (ICRP), there are several international organizations that are engaged in activities related to radiological protection. This article briefly reviews the aims and major activities of and interrelationships between those organizations, followed by opinions about how Japanese experts should contribute to those activities. [ABSTRACT FROM AUTHOR]

This document presents the ICRP's updated vision on "Areas of Research to Support the System of Radiological Protection", which have been previously published in 2017. It aims to complement the research priorities promoted by other relevant international organisations, with the specificity of placing them in the perspective of the evolution of the System of Radiological Protection. This document contributes to the process launched by ICRP to review and revise the System of Radiological Protection that will update the 2007 General Recommendations in ICRP Publication 103. [ABSTRACT FROM AUTHOR]

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.

In 2018, the International Commission on Radiological Protection (ICRP) released Publication 138, which highlights the ethical values foundational to the system of radiological protection. Additional work, both within and beyond the ICRP, has proposed or recommended ethical values associated with applications of the system in different areas, perhaps most notably in medical, veterinary, and environmental radiological protection. There are also existing ethical frameworks not specifically related to radiological protection that are nonetheless relevant to its practice; for example, the Beauchamp and Childress principles of biomedical ethics are of particular significance when it comes to medical uses of radiation and radioactivity. At first glance, it may seem as if there are unique or isolated sets of ethical values that need to be applied depending on the circumstance. Yet while each area of application will indeed have its own unique aspects and associated value judgements, there are consistent and complementary relationships between these ethical values. This paper reviews the work of the ICRP related to ethics, including brief historical context, and highlights the similarities and differences between sets of ethical values with emphasis on medical, veterinary, and environmental applications of radiological protection., (Creative Commons Attribution license.)

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]

This study shows the 222Rn concentration levels registered in 45 wells of the federal water supply system of Mexico City. Mexico City is one of the most populated cities in the world and has considerable telluric activity. Despite these two facts, there are no studies that analyze radon concentration levels in water supplied by the government. The values obtained show a concentration that ranges between 0.11 and 2.4 Bq L−1, levels below those recommended by the World Health Organization. [ABSTRACT FROM AUTHOR]