Area Of Radiation Protection Research Articles

Personal dosimetry at the Paul Scherrer Institute.

The Paul Scherrer Institute (PSI) is the largest research institute for natural and engineering sciences in Switzerland. PSI develops, builds and operates complex large research facilities. Every year, >2400 scientists from Switzerland and around the world come to PSI to use the facilities and to carry out experiments. Many areas at PSI are radiation protection areas. Depending on the radiation protection area, the work carried out and the time the users spend in these areas, they have to carry a personal dosemeter. PSI runs an individual monitoring service in compliance with the Swiss legislation on radiological protection and approved by the Swiss Federal Nuclear Safety Inspectorate. The service provides about 35000 dosemeters per year for the internal and external customers consisting of whole-body dosemeters for photons and neutrons as well as extremity dosemeters. This paper gives an overview on the employed personal dosimetry techniques by the individual monitoring service of PSI, the number of distributed dosemeters for internal and external customers and statistics about the measured doses at PSI over 30years.

The implementation process of knowledge management at the Institute of Radiation Protection and Dosimetry: actions and perspectives

The Institute of Radiation Protection and Dosimetry (IRD) is a research and development institution, linked to the Brazilian Nuclear Energy Commission (CNEN), with a tradition of training human resources in the areas of radiation protection, dosimetry, medical physics and metrology of ionizing radiation. Despite this relevance, the IRD has suffered loss of its intellectual capital, mainly due to retirements and lack of replacement of qualified personnel. Thus, it is extremely important to preserve the technical-scientific knowledge related to its activities. A methodology that can help in this process is knowledge management (KM), in view of its potential to generate benefits in public and private organizations. Therefore, this work aims to carry out an experience report of the process of implementing KM at IRD, which used as a theoretical reference the models applied by the International Atomic Energy Agency (IAEA). Initial results include the creation of the working group on KM, the diagnosis of critical knowledge and maturity, the Knowledge Management Assistance Visit (KMAV) by IAEA and the production of papers. In addition, the support of the IRD's top management should be highlighted, which has made it possible to carry out activities related to the implementation and effectiveness of KM. Thus, it is intended to expand KM activities in the IRD, such as the execution of projects and the offer of training in the area.

Radiation Protection and Shielding Analysis of the Versatile Test Reactor

The Versatile Test Reactor (VTR) is currently under development by the U.S. Department of Energy. It will provide very high fast neutron flux irradiation capabilities that are currently unavailable in the United States. Given the increasingly large number of advanced reactor concepts being pursued in recent years, this irradiation testing capability will be essential to support maturation of these designs. Radiation protection is an important part of the VTR design. High neutron fluxes can pose a challenge for radiation protection of the structures and equipment near the reactor core. This paper provides a summary on the status of the radiation protection considerations and shielding analysis performed for VTR under a nominal operating condition. The main radiation sources identified and examined in the study are applicable only under this operating condition. The paper focuses on three areas of radiation protection and shielding: secondary sodium activation in the intermediate heat exchanger, air activation in the reactor vessel auxiliary cooling system, and dose rate above the head access area due to primary sodium activation. VTR design and development are continuously progressing, and as such, the shielding considerations discussed in this paper will evolve alongside the overall VTR design.

Scientific knowledge management about Monte Carlo method: a bibliometric analysis on IRD Postgraduate Program in Radiation Protection and Dosimetry

With technological advances in several research areas of science, it is becoming increasingly common to use computer programs to solve problems. Some of these programs are based on statistical analysis and simulation of reality, such as the Monte Carlo Method (MC). The MC is a statistical tool widely used in different areas of knowledge, as a resource for simulating events that involve from financial assessments to the interaction of radiation with matter. Thereby, surveys with radiation sources, for example, are constantly evolving to study the question of radiation protection. In this sense, this paper has as main objective to verify the relevance of the MC for the area of radiation protection, analyzing the studies that apply the method in the Postgraduate Program (PPG) in Radiation Protection and Dosimetry of Institute of Radiation Protection and Dosimetry (IRD). This is because it is understood thatthrough the application of Scientific Knowledge Management (SKM) the construction of knowledge happens through an exchange of scientific information, that is, exchange of relevant contents that help in the preservation of knowledge.In this sense, a bibliometric analysis of the dissertations and theses deposited in Brazilian bank was made using the search term "Monte Carlo" and its respective programs (PENELOPE, GEANT4, EGSnrc, MCNP and Visual Monte Carlo), to be found in the title, abstract or keywords. With the identification of works carried out in all areas of concentration of the PPG, it is understood that the MC is extremely relevant for studies in the area of radiation protection.

The IRPA Young Generation Network: Activity Report from the Middle of 2018 to the Beginning of 2021

Since its establishment in 2018, the Young Generation Network (YGN) has been dedicated, with support of the International Radiation Protection Association (IRPA), to a variety of activities to promote communication, collaboration and professional development of students and young professionals in the area of radiation protection and its allied fields. This article reports our recent activities from the middle of 2018 to the beginning of 2021, with highlights on some important events: “Joint JHPS-SRP-KARP Workshop of Young Generation Network” (December 2019 in Japan); contribution to “Nuclear Energy Agency Workshop on Optimization: Rethinking the Art of Reasonable” (January 2020 in Portugal); survey on the impact of coronavirus disease 2019 (COVID-19) on radiation protection among IRPA YGN members (March 2020); and contribution to IRPA15 (15th International Congress of the IRPA; January–February 2021, online). The discussion and insight obtained from each activity are also summarized. The IRPA YGN will aim to achieve its on-going activities and continue to follow the ways paved in the Strategic Agenda and despite the challenges raised by the COVID-19 pandemic. Namely, running an international survey (for example, on the usage of social media in radiation protection, and on the long-term consequences of the COVID-19 pandemic), engaging national YGNs, extending the network, finding new relationships with networks with an interest in the young generation and participation in (remote) events will be aspired for.

A bibliographical review on the concept of biological effects of ionizing radiation in Brazilian publications

At the end of the nineteenth century, with the use of ionizing radiation for the benefit of humanity in various sectors of society, its effects on human health became evident. In this way, it is necessary to clarify the population about the main aspects related to the ionizing radiation applications, in order to better understand the concepts regarding their effects on health. And one of its main effects, within the area of radiological protection and medical physics, is called by Biological Effects. This is because ionizing radiations, due to their energy range, have the property of interacting with matter, and can alter the structure of cells by ionizing their atoms. Once it reaches the cells, ionizing radiation can produce damage, especially in DNA. This may occur either by the action of the radiation itself (direct mechanism) or by toxic radicals formed by the hydrolysis (indirect mechanism). These effects, over time, were identified and described, mainly from situations in which the man was acutely exposed (by accidents or medical use). In this sense, this paper proposes a bibliographic review of some concepts and definitions found in the literature on Biological Effects, mainly in Brazilian publications. With the purpose of not presenting a definitive theoretical model, but rather demonstrating the range of existing concepts, the objective of this paper is generating a debate about the variety aspects that may be related to the subject, reaffirming the importance of the topic for the area of radiation protection.

Nordic Cooperation in the Nuclear Safety Sector: High, Low, or Differentiated Integration?

Nordic cooperation has been depicted as eroding due to the increased importance of EU-related cooperation and integration. However, scholars propose that longstanding Nordic networks, grounded in professions and located in the state administration, may prove to be more robust toward external changes. This article discusses this proposal by looking at Nordic cooperation between the national radiation protection and nuclear safety authorities in Iceland, Denmark, Norway, Sweden, and Finland. The article maps behavioural perceptions of agency staff based on a dataset of 37 interviews to illustrate if the cooperation between the Nordic authorities is characterized by high integration, low integration, or differentiated integration within the nuclear safety sector. The study finds that the cooperation is differentiated between the highly integrated areas of radiation protection and emergency preparedness, and the less integrated areas of nuclear security and safeguards. To account for variation, the data indicates the importance of path dependency and portfolio.

Concept of elaboration and operation of the united system for monitoring and recording of individual occupational exposure doses and the National Dose Registry of Ukraine

I n 2014–2018 within the frameworks of the “State social program for enhancement of the state of safety, occupational medicine and workplace environment for 2014-2018”, SE NRCRM had developed the methodological and organizational grounds of the United system for monitoring and registration of individual occupational exposure doses in Ukraine (the System), which were formulated in the respective Concept. The Concept includes the following chapters: the aim, the tasks, basic principles of the System elaboration, roadmaps and solutions, operational aspects of the functioning. The Concept envisages creation of the state (national) dose register, the coordination center, quality assurance program and present various aspects of the System functioning: interactions with data providers, data users, requirements to the scope and quality of the dosimetric data. Special attention is paid to possible risks for implementation, alternative options are considered. Elaboration and operation of the System that is based on the principles formulated in the Concept, will allow prompt accomplishment of the international standards in the area of ra-diation protection and safety. It would provide powerful tool for optimization of the levels of occupational exposure in Ukraine, and, ultimately, reduce negative impact of ionizing radiation on the population of our state Keywords: occupational exposure, radiation protection, doses, registry, occupational safety, dosimetric control. For citation: Chumak VV, Zimina OS, Bazyka DA. Concept of elaboration and operation of the united system for monitoring and recording of individual occupational exposure doses and the National Dose Registry of Ukraine. Journal of the National Academy of Medical Sciences of Ukraine. 2019;25(4):448–56.

Assessing radiation protection knowledge in diagnostic radiography in the Republic of Cyprus. A questionnaire survey

IntroductionRadiation protection knowledge is essential for medical personnel in ensuring that the possible risks do not outweigh the benefits of diagnostic imaging. This study aimed to assess the radiation protection knowledge of radiographers in Cyprus. MethodsA cross-sectional study was carried out among radiographers in Cyprus through the Cyprus Society of Registered Radiologic Technologists & Radiation Therapy Technologists. The study was a quantitative descriptive analysis, using a questionnaire with 22 multiple-choice questions. Analysis of the data was done using the statistical software Stata, by performing mean knowledge score comparisons by different participants’ characteristics, using t-test and analysis of variance test. Statistical significance was assumed as a p-value < 0.05. ResultsThe answers provided for each question indicate that some areas of radiation protection are less known compared to others, as there is quite a wide range of correct-to-incorrect ratios. The analysis based on participant characteristics in relation to overall radiation effects knowledge, identified important determinants, namely the workplace of the participant (p = 0.006), the type of work licence the participant held at the time of the questionnaire (p = 0.024), and the years of clinical experience of the participant (p = 0.021). ConclusionThe study showed that the levels of knowledge in radiation protection are of a very good standard. However, work is needed to clarify the specifics of dose limits and the national radiation protection legislation with regards to informing patients about the possible effects of ionising radiation. Implications for practiceThe study results indicate the importance of educating radiographers about the requirements of national radiation protection legislation and how this new knowledge can be linked with practise.

CLINICAL APPLICATIONS OF BIOMARKERS OF RADIATION EXPOSURE: LIMITATIONS AND POSSIBLE SOLUTIONS THROUGH COORDINATED RESEARCH.

Dosimetric biomarkers have been effectively and intensively used for a long time in the area of radiation protection. In contrast to that, no robust standards or widely accepted protocols for application of these end-points in radiotherapy, diagnostic and interventional radiology and nuclear medicine exist to date. The International Atomic Energy Agency (IAEA) organized the review of the available data on the possibilities of the use of dosimetric biomarkers in medical irradiation scenarios. The resultant Technical Report also contains a summary of identified problems, gaps in knowledge, limitations in methodology and recommendations for their overcoming. This work provided a conceptual background for the initiation of a new IAEA Coordinated Research Project E35010, MEDBIODOSE (2017-21), which is aimed specifically at the development and improvement of applications of biodosimetric markers in clinical practice.

EDUCATION AND TRAINING IN EUROPE TO SUPPORT LOW-DOSE RADIATION PHYSICS AND RADIOBIOLOGY.

The success of any research programme is dependent on a continuing influx of new expertise, and continuing education to ensure the newest technologies and methods are exploited. In the past decade, a strategic approach has been used to build up the research expertise in the area of radiation protection and risk estimation. The High Level Expert Group (HLEG, www.hleg.de) in their 2009 report on European low-dose research asserted that education and training were key components in the development and maintenance of expertise for research into the risks from low-levels of ionising radiation. Following their recommendations, a Euratom-funded Network of Excellence (DoReMi, www.doremi-noe.net) was setup to develop a platform of European research institutions to coordinate the research programme and develop expertise in the area. We present here the activities initiated by DoReMi and currently continued by CONCERT (www.concert-h2020.eu) in support of education and training in the scientific areas underpinning radiation protection research.

EURAMED's vision on medical radiation protection (research).

While many areas of radiation protection have formed so-called 'platforms' in Europe which provide strategic research agendas for their areas of interest, this did not happen for a long while for medical exposure, which is the application of ionising radiation that causes the greatest man-made exposure, at least in first world countries. Finally, in 2015, a European medical radiation protection strategic research agenda was set up, and a corresponding platform was launched in 2016. This was named 'EURAMED' - the European Alliance for Medical Radiation Protection Research. In its strategic research agenda, EURAMED defined its vision for medical radiation protection and the corresponding research needed. Five major topics were identified, ranging from measurements of medical application-related parameters such as exposures and image quality and radiation biology aspects relevant for medical applications to individual optimisation strategies, to optimal use of techniques and harmonisation of practises, and finally to justification of the use of ionising radiation in medicine, all based on sufficient infrastructures for quality assurance. The ultimate goal is to reduce radiation exposure and risk individually for patients and staff by interdisciplinary research between clinicians, physicists, and engineers. Therefore, it is essential that the results are translated into clinical practice.

Urinary Excretion of Yttrium-90 after Radioembolization with Yttrium-90-Labeled Resin-based Microspheres.

In radioembolic therapy (RET) of hepatic malignancies using yttrium-90 (Y)-labeled resin microspheres, radiation protection is primarily concerned with avoiding contamination by radioactive spheres. However, as Y is bound to the microsphere surface by a potentially reversible ion-exchange process, the aim of this study was to assess the extent of the potential excreted activity in urine. After RET with Y-labeled resin-based microspheres, urinary excretion of free Y was prospectively analyzed in 51 interventions (n = 45 patients) by sampling urine over 48 h (two 24-h intervals) consecutively. The measured urinary concentration of Y, normalized to the administered microsphere activity, was a median of 58.5 kBq L GBq (range = 3.5-590.9 kBq L GBq) and 17.8 kBq L GBq (1.8-58.8 kBq L GBq) for the first and second 24-h periods after administration, respectively (p ≤ 0.0001, F = 28.4, result from ANOVA). The total excreted activity significantly decreased (p ≤ 0.0001) from a median of 72.5 kBq in the first 24-h period to a median of 22.1 kBq in the second 24-h period. Urinary excretion of free Y after resin-based RET occurs for a longer period and at a higher activity excretion than previously published, which has to be considered when patients are either hospitalized or return home after RET. Existing approaches for patient hospitalization, especially in temporary radiation protection areas, justified by the previously reported lower excretion rate, should be re-evaluated, and as a consequence, the current product safety information and handling recommendations for Y-labeled resin-based microspheres may need to be revised.

Comparative investigation of three dose rate meters for their viability in pulsed radiation fields

Pulsed radiation fields, characterized by microsecond pulse duration and correspondingly high pulse dose rates, are increasingly used in therapeutic, diagnostic and research applications. Yet, dose rate meters which are used to monitor radiation protection areas or to inspect radiation shielding are mostly designed, characterized and tested for continuous fields and show severe deficiencies in highly pulsed fields. Despite general awareness of the problem, knowledge of the specific limitations of individual instruments is very limited, complicating reliable measurements. We present here the results of testing three commercial dose rate meters, the RamION ionization chamber, the LB 1236-H proportional counter and the 6150AD-b scintillation counter, for their response in pulsed radiation fields of varied pulse dose and duration. Of these three the RamION proved reliable, operating in a pulsed radiation field within its specifications, while the other two instruments were only able to measure very limited pulse doses and pulse dose rates reliably.

Radiation protection for an intraoperative X-ray source compared to C-arm fluoroscopy

BackgroundIntraoperative radiotherapy (IORT) using the INTRABEAM® system promises a flexible use regarding radiation protection compared to other approaches such as electron treatment or HDR brachytherapy with 192Ir or 60Co. In this study we compared dose rate measurements of breast- and Kypho-IORT with C-arm fluoroscopy which is needed to estimate radiation protection areas. Materials and MethodsC-arm fluoroscopy, breast- and Kypho-IORTs were performed using phantoms (silicon breast or bucket of water). Dose rates were measured at the phantom's surface, at 30cm, 100cm and 200cm distance. Those measurements were confirmed during 10 Kypho-IORT and 10 breast-IORT patient treatments. ResultsThe measured dose rates were in the same magnitude for all three paradigms and ranges from 20μSv/h during a simulated breast-IORT at two meter distance up to 64 mSv/h directly at the surface of a simulated Kypho-IORT. Those measurements result in a circle of controlled area (yearly doses >6 mSv) for each paradigm of about 4 m±2 m. Discussion/ ConclusionsAll three paradigms show comparable dose rates which implies that the radiation protection is straight forward and confirms the flexible use of the INTRABEAM® system.

Comparison between measurements of dose rate in the vicinity of a point source and a flat source of 3600 MBQ iodine-131

Introduction In nuclear medicine, whenever radiation calculations must be made in the vicinity of a source of iode131, is regularly asks the difference between point source and plane. Using two different detectors measurements were made. They show differences in the vicinity of sources. Materials and methods Two detectors were used: GM Nardeux type and type Victoreen ionization chamber with two radioactive sources iode131 of 3600 MBq. A point source of 1 ml in a bottle and a flat source in a phantom of 53 × 42 cm 2 . For each source and each detector measurements were performed for distances from 0.1 to 3 m. Results There was no significant difference between the two detectors. We observed that there are differences between the two types of sources for distances less than 1 m. For example at 25 cm 1500 mSv/ h for the source plane and 2200 mSv/h for the point source that is 50% more. Conclusion Less than 1 m there is a difference between a measurement in the vicinity of a point source and a flat source for the same radioactivity. From 1 m, and considering that this is the area of radiation protection, the values for the two types of sources are identical.

Challenges in Radiation Protection of Patients for the 21st Century

The purpose of this article is to presage the upcoming challenges in the area of radiation protection of patients in imaging for different stakeholders, such as dosimetrists, radiation biologists, patients, referring physicians, radiologists, radiographers, medical physicists, and manufacturers. Most of the challenges facing different stakeholders are actually based on the contribution required from industry; thus, manufacturers play the greatest role in making patients safer in this century.

TH-C-211-01: International Perspectives on Radiation Protection

There are some actions which require international cooperation. An example of good cooperation can be found in the largely seamless international use of credit cards and ATM machines. Conversely, an example where international cooperation has not been effective can be found in the diversity of electricity plugs and sockets in different countries. In the area of radiation protection, there are also examples of good and bad cooperation. The global acceptance of concepts and principles of radiation protection as developed by the International Commission on Radiological Protection (ICRP) such as justification, optimization and dose limitation is a good example. Conversely, there are quite a few examples of non-agreement or partial agreement of issues in the field of radiation protection, such as dose limits for workers and members of the public, and acceptance of SI units e.g. Sv and Gy against rem and rad. When it comes to radiation protection of patients, there is Universityersal agreement that there should be no dose limits and that the concept of diagnostic reference levels (DRLs) should be used with flexibility. International actions are needed not only to create harmonization of concepts but also to give impetus to some areas, raise awareness about emerging issues and forewarn about upcoming dangers if actions are not initiated by countries well in time. The talk will cover “How does the International System of Radiation Protection work” and inform about an International Action Plan on Radiation Protection of Patients of the IAEA. Is the international system binding or national systems are?. How harmonization is achieved through the work of the IAEA. Ultimately, the role medical physicists and health physicists in implementing the radiation protection requirements for staff and patient protection shall be discussed. Learning Objectives: 1. To understand the system of radiation protection in international and national context 2. To become familiar with international action plan on radiation protection of patients 3. To become familiar with international organizations in the area of medical radiation protection 4. To understand the potential role you can play in international activities

Radiation protection of medical staff in the latest draft of the revised Euratom Basic Safety Standards directive

Abstract The European Union has a long and successful history of legislating in the area of radiation protection of the public, workers and individuals submitted to medical exposure, the first Euratom “Basic Safety Standards” (BSS) adopted in 1959 and subsequently updated and supplemented with other Directives. The recent revision of this legislation aims to update it in the light of the latest knowledge and experience and to simplify it by consolidating the current legal acts into one Directive. The draft of the revised Euratom BSS Directive has been approved by the group of scientific experts under Euratom Treaty Article 31 and is currently undergoing the European Commission’s procedures. This draft contains several new or amended provisions relating to protection of medical staff, among them: (i) a streamlining of the annual dose limit provisions, (ii) enhancing the use of dose constraints in optimization of protection, and (iii) ensuring better recording and transfer of occupational dose data including in cases of trans-border movement of workers. The Community action to radiation protection of workers is not restricted to passing relevant legislation but also includes ‘soft action’ as issuing guidance, supporting research and stakeholders’ involvement, etc. In August 2010 the Commission issued a Communication to the Council and the European Parliament dealing with the issues in the medical uses of ionizing radiation, including those relating to radiation protection of medical staff.

RADIATION PROTECTION AT U.S. NUCLEAR POWER PLANTS—TODAY AND TOMORROW

The nuclear power industry work ethic and culture is founded on learning from experience and continuously finding ways to improve performance--especially in regard to radiation safety. Over the past 25 y, this process of continuous improvement has yielded exceptional results in regard to radiation protection of workers, the public and the environment. In light of the resurgence of nuclear energy in the United States, the nuclear power industry is developing strategies to achieve continuous improvements to performance and address emerging challenges in the area of radiation protection.