Search

The International Commission on Radiological Protection (ICRP) described its approach to the protection of the environment and how it should be applied in Publication 124. The report expanded on the Commission’s objectives for environmental protection, and how the Derived Consideration Reference Levels (DCRLs) apply within different exposure situations. DCRLs relate radiation effects to doses over and above their normal local background radiation levels, and consider different potential pathways of exposure for animals and plants. This paper will describe how the DCRLs may be used within existing exposure situations to better understand the potential impacts on animals and plants. In these circumstances, the Commission recommends that the aim be to reduce exposures to levels that are within the DCRL bands (or even below, depending upon the potential cost/benefits), but with full consideration of the radiological and non-radiological consequences of doing so. Using examples, this paper will demonstrate how this may be achieved in practice, bearing in mind the potential exposure of humans, animals and plants during and following any remediation attempted.

Los equipos de radiología dental portátil son una innovación tecnológica que ha aportado grandes cambios en la práctica clínica, especialmente en el área de endodoncia donde se usan de manera rutinaria, estos producen radiaciones ionizantes que tanto paciente como operador están expuestos, estas radiaciones interactúan con la materia viva y pueden producir efectos nocivos lo cual dependerá de la dosis absorbida, tiempo y tipo de tejido expuesto. Este estudio de tipo Observacional analítico de corte transversal cuantificó el nivel de radiación dispersa en ambientes contiguos a los equipos portátiles (Nomad Pro, Port X-II, DX 3000, Prox), para ello se utilizó un equipo medidor de radiación tipo Geiger, ubicado en dos situaciones: en retrodispersión y a dos metros de distancia del equipo de radiología dental portátil, con el cual se realizaron 10 tomas por cada situación programando los equipos para la toma de radiografía de un molar de adulto, y se cuantifico la radiación absorbida por el operador y el personal ocupacional mente expuesto. Los resultados mostraron que el equipo Nomad Pro obtuvo las medias de radiación más bajas en las dos situaciones siendo 0,011 mSv/hora el valor para la situación de operador y 0,013 mSv/hora para la situación a dos metros. Como conclusión del proyecto a pesar de que ninguno de los equipos evaluados estuvo por encima del límite permitido anualmente (20mSv/año), nada impide el uso de medidas de radio protección para mantener el principio de ALARA. The Portable Equipments of Dental Radiology are a technological innovation that has brought great changes in the clinical practice, especially in the máxi of endodontics where they are used routinely. They produce ionizing radiation to both patient and operator; this radiation interacts with the living matter and can produce harmful effects. The harmful effects maximum ó the absorbed dose, time and type of material exposed. This analytical observational study of cross section quantifies the level of scattered radiation in adjacent environments of these equipments (Nomad Pro, Port X-II, DX 3000, Prox) for this purpose it was used a Geiger radiation meter equipment, based in two situations: backscatter and two meters away from the portable dental radiology. It was made 10 shots by each situation, programming the equipments for a radiograph of a molar adult and quantified the radiation absorbed by the operator and occupational support staff. The Results showed that the Nomad Pro obtained the lowest radiation under the two situations being 0,011 mSv/hr the value for the operator status and 0.013 mSv/hr for the situation of two meters. As maximums ón of the máximum, even though none of the tested equipments were above to the allowed annually limit (20mSv / year), nothing prevents the use of radiological protection to keep the ALARA principle. Especialista en Endodoncia Especialización

Objetivo: Apresentar uma ferramenta de análise de dados que pode ser utilizada para proteção de pacientes e traba- lhadores em áreas de uso de equipamentos móveis. Materiais e Métodos: Foi desenvolvida uma ferramenta, em pla- nilha ativa Excel®, que utiliza medidas de exposição para gerar um banco de dados de fatores de forma e calcular o kerma no ar ao entorno de um leito. O banco de dados inicial foi coletado com três equipamentos móveis. Um espalhador não antropomórfico foi utilizado, sendo realizadas medidas de exposição em uma malha de (4,2 × 4,2) m2, ao passo de 0,3 m. Resultados: A ferramenta calcula o kerma no ar (associado à exposição de pacientes expostos e ao equiva- lente de dose ambiente) à radiação secundária. Para distâncias inferiores a 60,0 cm, valores acima do limite máximo de equivalente de dose ambiente definido para área livre (0,5 mSv/ano) foram verificados. Os dados coletados a 2,1 m foram sempre inferiores a 12% do referido limite. Conclusão: A ferramenta é capaz de auxiliar na proteção radiológica de pacientes e trabalhadores, quando associada à coleta de dados adequada, pois possibilita a determinação de áreas livres ao entorno de leitos em áreas onde equipamentos móveis geradores de radiação X são utilizados. Objective: To present a data analysis toolkit that may be utilized with the purpose of radiation protection of hospital inpatients and workers in areas where mobile apparatuses are used. Materials and Methods: An Excel® ActiveSheet was utilized to develop a computational toolkit with exposure measurements to generate a database of shape factors and to calculate the air kerma around hospital beds. The initial database included data collected with three mobile apparatuses. A non-anthropomorphic phantom was utilized and exposure measurements were performed on a (4.2 × 4.2) m2 mesh-grid at 0.3 m steps. Results: The toolkit calculates the air kerma (associated with patients’ radiation exposure and with ambient equivalent dose) under secondary radiation. For distances lower than 60.0 cm, values above the maximum ambient equivalent dose threshold defined for radiation free areas (0.5 mSv/year) were verified. Data collected at 2.1 m have always presented values lower than 12% of that threshold. Conclusion: The toolkit can aid in the radiological protection of patients and workers, provided it is combined with appropriate data collection, since it allows the determination of radiation free areas around beds in rooms where mobile X-ray apparatuses are utilized.

This paper introduces the new approach of risk analysis established by the French Ministry of the Environment and develops the benefits of applying nuclear probabilistic safety assessment approaches to the chemical industry. In the aftermath of the AZF disaster in Toulouse on 21 September 2001, a new law was proposed by the French government asking for the investigation of all representative scenarios and the assessment of the probability of the resulting dangerous phenomena to demonstrate an acceptable level of safety. Therefore, any accident is investigated from a global point of view, according to its gravity and its probability. In 2000, the French Ministry of the Environment asked the Institute for Radiological Protection and Nuclear Safety (IRSN), and in particular its Systems and Risk Protection Assessment (SESPRI) and its Industrial Risks, Fire and Containment Assessment and Study (SERIC) departments, to conduct a Probabilistic Safety Assessment (PSA) study of an LPG distribution facility, specially for the BLEVE scenario. This study has showed the power of PSA for defining and prioritizing actions to be carried out to improve safety of facilities; however, it requires credible data for reliability and failure of the equipment, not available in generic failure databases. Since 2007, IRSN has taken several initiatives in collaboration with operators in order to provide more precise and representative failure rates for main safety equipment, ready to use in future PSA relative to LPG plants. © 2010 Elsevier Ltd.

Generic guidance on the withdrawal of sheltering, withdrawal of evacuation and evacuation of sheltered populations (displacement) has been developed based on previously unpublished work in the UK and France and on input from stakeholder panels in Germany, Belgium, France and the UK. The guidance is a living document that can be developed further in the future, both in its generic form and also as customised versions in some Member States. The guidance outlines the many factors which influence the withdrawal of emergency countermeasures: official confirmation that any release has stopped; adequacy of monitoring data; radiological criteria; radiological protection advice; availability of resources; social and psychological needs; stakeholder dialogue; and communication strategy. The relative importance placed by decision makers on each of these criteria would vary according to the nature and scale of the accident and also on socio-political, economic and cultural perspectives. In the event of a radiological incident, decision makers will need to be in a position to construct a strategy for managing the withdrawal of emergency countermeasures. For larger scale, longer duration releases involving several nuclides, a management strategy is likely to be complex. The guidance therefore includes a series of checklists which have been developed in conjunction with stakeholders to take into account the main criteria and factors which should be considered. © EDP Sciences, 2010.

OBJETIVO: Pretendeu-se averiguar que importância os técnicos de radiologia atribuem à implementação de um programa de controle de qualidade em radiologia, e conhecer a importância da existência de critérios de proteção. MATERIAIS E MÉTODOS: Estudo descritivo e transversal. Os dados foram recolhidos por meio de um questionário (quatro partes), tendo sido garantido o anonimato e a confidencialidade dos dados. Participaram neste estudo 48 técnicos de radiologia que exercem funções em instituições de saúde, situadas no Distrito de Vila Real (norte de Portugal). RESULTADOS: Dos técnicos de radiologia participantes do estudo, 62,5% não sabem em que consiste um programa de controle de qualidade em radiologia, mas 85,4% consideram muito importante a sua implementação nos seus serviços, e 89,6% consideram que a sua implementação seria um fator de motivação. Verificamos também que as instituições estudadas (hospitais e centros de saúde) não se encontram adequadas com os princípios básicos da radioproteção. CONCLUSÃO: Embora os técnicos de radiologia não saibam em que consiste um programa de controle de qualidade em radiologia, estariam dispostos a colaborar na sua elaboração. Este estudo permitiu constatar uma realidade que pensávamos não ser possível existir: instituições públicas, cuja missão se baseia na promoção da saúde, ignorarem as não conformidades existentes nos diferentes serviços, no que diz respeito à proteção radiológica.OBJECTIVE: The present study was aimed at evaluating the importance given by radiology technicians to the implementation of a quality control program and the existence of radiological protection criteria in their centers. MATERIALS AND METHODS: The data for the present descriptive and cross-sectional study were collected by means of a four-module questionnaire, with data anonymity and confidentiality being assured. The sample consisted of 48 radiology technicians working in health institutions of the District of Vila Real (North of Portugal). RESULTS: Among the radiology technicians participating in the present study, 62.5% do not know what a quality control program is, although its implementation is considered as very important for their centers by 85.4% and 89.6% consider that its implementation would be a motivating factor. Also, the authors have observed that hospitals and health centers evaluated are not in compliance with the basic principles of radiation protection. CONCLUSION: Although the radiology technicians do not know what a quality control program is, they are willing to collaborate in the elaboration of this program. The present study has allowed the authors to testify a supposedly inexistent reality: public institutions whose mission is based on health promotion ignoring the non-compliance with principles of radiological protection.

OBJETIVO: Pretendeu-se averiguar que importância os técnicos de radiologia atribuem à implementação de um programa de controle de qualidade em radiologia, e conhecer a importância da existência de critérios de proteção. MATERIAIS E MÉTODOS: Estudo descritivo e transversal. Os dados foram recolhidos por meio de um questionário (quatro partes), tendo sido garantido o anonimato e a confidencialidade dos dados. Participaram neste estudo 48 técnicos de radiologia que exercem funções em instituições de saúde, situadas no Distrito de Vila Real (norte de Portugal). RESULTADOS: Dos técnicos de radiologia participantes do estudo, 62,5% não sabem em que consiste um programa de controle de qualidade em radiologia, mas 85,4% consideram muito importante a sua implementação nos seus serviços, e 89,6% consideram que a sua implementação seria um fator de motivação. Verificamos também que as instituições estudadas (hospitais e centros de saúde) não se encontram adequadas com os princípios básicos da radioproteção. CONCLUSÃO: Embora os técnicos de radiologia não saibam em que consiste um programa de controle de qualidade em radiologia, estariam dispostos a colaborar na sua elaboração. Este estudo permitiu constatar uma realidade que pensávamos não ser possível existir: instituições públicas, cuja missão se baseia na promoção da saúde, ignorarem as não conformidades existentes nos diferentes serviços, no que diz respeito à proteção radiológica. OBJECTIVE: The present study was aimed at evaluating the importance given by radiology technicians to the implementation of a quality control program and the existence of radiological protection criteria in their centers. MATERIALS AND METHODS: The data for the present descriptive and cross-sectional study were collected by means of a four-module questionnaire, with data anonymity and confidentiality being assured. The sample consisted of 48 radiology technicians working in health institutions of the District of Vila Real (North of Portugal). RESULTS: Among the radiology technicians participating in the present study, 62.5% do not know what a quality control program is, although its implementation is considered as very important for their centers by 85.4% and 89.6% consider that its implementation would be a motivating factor. Also, the authors have observed that hospitals and health centers evaluated are not in compliance with the basic principles of radiation protection. CONCLUSION: Although the radiology technicians do not know what a quality control program is, they are willing to collaborate in the elaboration of this program. The present study has allowed the authors to testify a supposedly inexistent reality: public institutions whose mission is based on health promotion ignoring the non-compliance with principles of radiological protection.

OBJETIVO: Os objetivos deste trabalho são: a) avaliar os procedimentos radiográficos e estimar o valor do kerma no ar na superfície de entrada nos recém-nascidos prematuros submetidos a exames de tórax e abdome, realizados no setor de neonatologia de um hospital público de Belo Horizonte; b) estimar as doses nos órgãos e os respectivos riscos de ocorrência de câncer nesses órgãos em decorrência das exposições à radiação. MATERIAIS E MÉTODOS: Foram analisados os prontuários dos pacientes internados no setor de neonatologia desse hospital durante o período de maio a setembro de 2004, anotando-se os dados antropométricos, data de internação/alta, exames de raios X realizados. O kerma no ar na superfície de entrada foi determinado a partir do rendimento do tubo de raios X e dos parâmetros de irradiação utilizados nos exames. As doses nos órgãos foram estimadas com o software PCXMC e o risco, durante o restante da expectativa de vida, com o software IREP. RESULTADOS: O valor médio do kerma no ar na superfície de entrada por exame foi abaixo do nível de referência da publicação da Comunidade Européia. Para o paciente mais severamente irradiado, os órgãos mais suscetíveis à ocorrência de câncer foram fígado, mama e estômago, com valores máximos de excess relative risk, respectivamente, de 3,4%, 2,3% e 1,7%. CONCLUSÃO: Foi constatada a necessidade de otimização dos procedimentos radiográficos com vista à diminuição do risco para os recém-nascidos, que apesar de ser considerado baixo (comparativamente ao benefício), deve ser sempre diminuído para valores tão baixos quanto razoavelmente exeqüíveis.OBJECTIVE: The present study was aimed at: a) evaluating radiographic procedures and estimating entrance surface air kerma in preterm neonates submitted to chest and abdominal radiography at the unit of neonatology in a public hospital of Belo Horizonte, MG, Brazil; b) estimating the dose to organs and respective risks for cancer as a result from radiation exposure. MATERIALS AND METHODS: Records of patients admitted to the unit of neonatology of this hospital in the period between May and September 2004 were reviewed. Anthropometric data, admission/discharge dates and radiographic studies performed were recorded for each of the patients. The calculation of the entrance surface air kerma was based on the x-ray tube output and irradiation parameters adopted for examinations. Dose to organs was calculated with the aid of the software PCXMC, and the lifetime risk for cancer, with the software IREP. RESULTS: Mean entrance surface air kerma per examination was below the diagnostic reference levels recommended by the European Community. In the most severely irradiated patients, liver, breast and stomach were the organs at highest risk for cancer, with maximum excess relative risk of respectively 3.4%, 2.3%, and 1.7%. CONCLUSION: The present study demonstrated the need for optimization of radiographic procedures in order to reduce the risks for neonates that, in spite of being considered to be low as compared with the benefits, should be reduced to values as low as reasonably achievable.

OBJETIVO: Os objetivos deste trabalho são: a) avaliar os procedimentos radiográficos e estimar o valor do kerma no ar na superfície de entrada nos recém-nascidos prematuros submetidos a exames de tórax e abdome, realizados no setor de neonatologia de um hospital público de Belo Horizonte; b) estimar as doses nos órgãos e os respectivos riscos de ocorrência de câncer nesses órgãos em decorrência das exposições à radiação. MATERIAIS E MÉTODOS: Foram analisados os prontuários dos pacientes internados no setor de neonatologia desse hospital durante o período de maio a setembro de 2004, anotando-se os dados antropométricos, data de internação/alta, exames de raios X realizados. O kerma no ar na superfície de entrada foi determinado a partir do rendimento do tubo de raios X e dos parâmetros de irradiação utilizados nos exames. As doses nos órgãos foram estimadas com o software PCXMC e o risco, durante o restante da expectativa de vida, com o software IREP. RESULTADOS: O valor médio do kerma no ar na superfície de entrada por exame foi abaixo do nível de referência da publicação da Comunidade Européia. Para o paciente mais severamente irradiado, os órgãos mais suscetíveis à ocorrência de câncer foram fígado, mama e estômago, com valores máximos de excess relative risk, respectivamente, de 3,4%, 2,3% e 1,7%. CONCLUSÃO: Foi constatada a necessidade de otimização dos procedimentos radiográficos com vista à diminuição do risco para os recém-nascidos, que apesar de ser considerado baixo (comparativamente ao benefício), deve ser sempre diminuído para valores tão baixos quanto razoavelmente exeqüíveis. OBJECTIVE: The present study was aimed at: a) evaluating radiographic procedures and estimating entrance surface air kerma in preterm neonates submitted to chest and abdominal radiography at the unit of neonatology in a public hospital of Belo Horizonte, MG, Brazil; b) estimating the dose to organs and respective risks for cancer as a result from radiation exposure. MATERIALS AND METHODS: Records of patients admitted to the unit of neonatology of this hospital in the period between May and September 2004 were reviewed. Anthropometric data, admission/discharge dates and radiographic studies performed were recorded for each of the patients. The calculation of the entrance surface air kerma was based on the x-ray tube output and irradiation parameters adopted for examinations. Dose to organs was calculated with the aid of the software PCXMC, and the lifetime risk for cancer, with the software IREP. RESULTS: Mean entrance surface air kerma per examination was below the diagnostic reference levels recommended by the European Community. In the most severely irradiated patients, liver, breast and stomach were the organs at highest risk for cancer, with maximum excess relative risk of respectively 3.4%, 2.3%, and 1.7%. CONCLUSION: The present study demonstrated the need for optimization of radiographic procedures in order to reduce the risks for neonates that, in spite of being considered to be low as compared with the benefits, should be reduced to values as low as reasonably achievable.

En el campo de la protección radiológica, una de las áreas a la que se está dedicando gran atención es al estudio de los efectos biológicos de las radiaciones ionizantes. En este ámbito se dispone de información y medios en cuanto a efectos de dosis elevadas en irradiaciones agudas. El objetivo de este proyecto es estudiar un irradiador que permita irradiaciones a dosis bajas (~50 μGy/h) durante periodos de tiempo de semanas o meses. Concretamente se busca que estas irradiaciones se lleven a cabo con fuentes o equipos emisores de radiación fotónica en el rango de energías de 60 a 662 keV. Para llevar a cabo el proyecto, se comienza con la selección del emisor de radiación más adecuado a la situación buscando cumplir los criterios establecidos en el planteamiento del problema, calculando además, el blindaje y la geometría necesarios para conseguir el mejor diseño. Posteriormente se trata de encontrar elementos comerciales para el desarrollo del irradiador teniendo en cuenta que sería de interés que el dispositivo cuente con la opción de modificar las condiciones ambientales en su interior. Tras esto, se propone la solicitud de autorización administrativa de la instalación, un estudio de costes y otro de impacto ambiental.

International Commission on Radiological Protection (ICRP), an independent international organization established in 1925, develops, maintains, and elaborates radiological protection standards, legislation, and guidelines. United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) provides scientific evidence. World Health Organization (WHO) and International Atomic Energy Agency (IAEA) utilise the ICRP recommendations to implement radiation protection in practice. Finally, radiation protection agencies in each country adopt the policies, and adapt them to each situation. In Korea, Nuclear Safety and Security Commission is the governmental body for nuclear safety regulation and Korea Institute of Nuclear Safety is a public organization for technical support and R&D in nuclear safety and radiation protection.

Foi elaborado um Programa de Monitoração Ocupacional em radiologia médica para o Hospital Universitário Clementino Fraga Filho da Universidade Federal do Rio de Janeiro, seguindo as normas e legislação nacional. Para a construção do Programa, realizou-se um levantamento de todos os Serviços e funcionários diretamente expostos às radiações ionizantes. Constatou-se que a maioria desses funcionários não era monitorada, que apenas três Serviços mantinham um controle de dose de trabalhadores com contratos de prestação de serviço independentes e que não havia controle para os casos de doses elevadas. Com a implantação do Programa, os passos seguintes foram a contratação da uma nova empresa que prestasse o serviço de monitoração pessoal, reduzindo significativamente o custo anual de operação com o contrato único para o hospital; a inclusão de mais sete Serviços que trabalham com radiações ionizantes, aumentando em mais de 60% o número de trabalhadores monitorados; o controle de doses elevadas, principalmente no setor de Hemodinâmica, que apresentou a maior média de dose (0,32 mSv/mês); e a monitoração de área, que foi realizada em períodos intercalados nos pontos considerados de maior risco para a população e os trabalhadores. Paralelamente, o Programa de Monitoração Ocupacional foi informatizado, sendo construído um banco de dados com o propósito de controlar e armazenar as doses funcionais. Com a implantação do Programa, começa-se a compreender os riscos de se trabalhar com radiações ionizantes, a partir dos conceitos de proteção radiológica, e conscientiza-se quanto ao uso correto dos monitores de dose. An occupational monitoring program in diagnostic radiology was implemented at the "Hospital Universitário Clementino Fraga Filho - UFRJ", Rio de Janeiro, Brazil, in accordance with the Brazilian legislation. Previously, a survey of all personnel involved with ionizing radiation was performed. Many problems were observed: the great majority of the workers were not properly monitored; only three departments of the hospital kept an independent survey of the occupational doses; there was not a follow-up control of the high doses. With the implementation of the program, a new laboratory was chosen to read the dosemeters and this initiative resulted in reduction of the hospital costs. The inclusion of seven more departments in the program represented an increase of 60% in the number of monitored workers. The program also provided a system to control the high doses, especially in the Hemodynamics department, which presented the highest mean dose value (0.32 mSv/month). An area survey program was performed during different periods in places considered of high risk for the workers and for the public as well. At the same time, a software was used to build a database with the aim of controlling all personnel data. The implementation of the program provided all personnel involved a better knowledge of the risks associated with ionizing radiation and of radioprotection, and also awareness of the need of correct use of the personal dose monitors.

Radiation is omnipresent. It has many interesting applications: in medicine, where it allows curing and diagnosing patients; in communication, where modern communication systems make use of electromagnetic radiation; and in science, where it is used to discover the structure of materials; to name a few. Physically, radiation is a process in which particles or waves travel through any kind of material, usually air. Radiation can be very energetic, in which case it can break the atoms of ordinary matter (ionization). If this is the case, radiation is called ionizing. It is known that ionizing radiation can be far more harmful to living beings than non-ionizing radiation. In this dissertation, we are concerned with ionizing radiation. Naturally occurring ionizing radiation in the form of radioactivity is a most natural phenomenon. Almost everything is radioactive: there is radiation emerging from the soil, it is in the air, and the whole planet is constantly undergoing streams of energetic cosmic radiation. Since the beginning of the twentieth century, we are also able to artificially create radio-active matter. This has opened a lot of interesting technological opportunities, but has also given a tremendous responsibility to humanity, as the nuclear accidents in Chernobyl and Fukushima, and various accidents in the medical world have made clear. This has led to the elaboration of a radiological protection system. In practice, the radiological protection system is mostly implemented using a methodology that is indicated with the acronym ALARA: As Low As Reasonably Achievable. This methodology consists of justifying, optimizing and limiting the radiation dose received. This methodology is applied in conjunction with the legal limits. The word "reasonably" means that the optimization of radiation exposure has to be seen in context. The optimization is constrained by the fact that the positive effects of an operation might surpass the negative effects caused by the radiation. Several industrial and scientific procedures give rise to facilities with ionizing radiation. Most technical and scientific facilities also need maintenance operations. In the spirit of ALARA, these interventions need to be optimized in terms of the exposure of the maintenace workers to ionizing radiation. This optimization cannot be automated since the feasibility of the intervention tasks requires human assessment. The intervention planning could however be facilitated by technical-scientific means, e.g. software tools. In the context sketched above, this thesis provides technical-scientific considerations and the development of technical-scientific methodologies and software tools for the implementation of radiation protection.In particular, this thesis addresses the need for an interactive visual intervention planning tool in the context of high energy particle accelerator facilities., Les radiations sont omniprésentes. Elles ont de nombreuses applications dans des domaines variés: en médecine, elles permettent de réaliser des diagnostiques et de guérir des patients; en communication, tous les systèmes modernes utilisent des formes de rayonnements électromagnétiques; et en science, les chercheurs les utilisent pour découvrir la composition et la structure des matériaux, pour n'en nommer que quelques-unes. Concrètement, la radiation est un processus au cours duquel des particules ou des ondes voyagent à travers différents types de matériaux. La radiation peut être très énergétique, et aller jusqu'à casser les atomes de la matière ordinaire. Dans ce cas, on parlera de radiation ionisante. Il est communément admis que la radiation ionisante peut être bien plus nocif pour les êtres vivants que la radiation non ionisante. Dans cette dissertation, nous traiterons de la radiation ionisante. La radioactivité est le processus d'émission des radiations ionisantes. Elle existe sous forme naturelle, et est présente dans les sols, dans l'air et notre planète entière est bombardée en permanence de rayonnements cosmiques énergétiques. Depuis le début du XXe siècle, les chercheurs sont capables de créer artificiellement de la matière radioactive. Cette découverte a offert de multiples avancées technologiques, mais a eu également de lourdes conséquences pour l'humanité comme l'ont démontrés les évènements de Tchernobyl et de Fukushima ou d'autres accidents dans le monde médical. Cette dangerosité a conduit à l'élaboration d'un système de radioprotection. Dans la pratique, la radioprotection est principalement mise en œuvre en utilisant la méthode ALARA. Cette méthodologie consiste à justifier, optimiser et limiter les doses reçues. Elle est utilisée conjointement avec les limites légales. Le facteur d'optimisation est contraint par le fait que l'exposition volontaire d'un travailleur aux radiations lors d'une opération doit être plus bénéfique que si aucune intervention humaine n'était conduite dans une situation donnée. Dans le monde industriel et scientifique, il existe des infrastructures qui émettent des rayonnements ionisants. La plupart d'entre elles nécessitent des opérations de maintenance. Dans l'esprit du principe ALARA, ces interventions doivent être optimisées pour réduire l'exposition des travailleurs aux rayonnements ionisants. Cette optimisation ne peut pas être réalisée de manière automatique car la faisabilité des interventions nécessite dans tous les cas une évaluation humaine. La planification des interventions peut cependant être facilitée par des moyens techniques et scientifiques comme par exemple un outil informatique. Dans le contexte décrit ci-dessus, cette thèse regroupe des considérations techniques et scientifiques, et présente la méthodologie utilisée pour développer des outils logiciels pour la mise en œuvre de la radioprotection.

The benefits of cardiac imaging are immense, and modern medicine requires the extensive and versatile use of a variety of cardiac imaging techniques. Cardiologists are responsible for a large part of the radiation exposures every person gets per year from all medical sources. Therefore, they have a particular responsibility to avoid unjustified and non-optimized use of radiation, but sometimes are imperfectly aware of the radiological dose of the examination they prescribe or practice. This position paper aims to summarize the current knowledge on radiation effective doses (and risks) related to cardiac imaging procedures. We have reviewed the literature on radiation doses, which can range from the equivalent of 1-60 milliSievert (mSv) around a reference dose average of 15 mSv (corresponding to 750 chest X-rays) for a percutaneous coronary intervention, a cardiac radiofrequency ablation, a multidetector coronary angiography, or a myocardial perfusion imaging scintigraphy. We provide a European perspective on the best way to play an active role in implementing into clinical practice the key principle of radiation protection that: 'each patient should get the right imaging exam, at the right time, with the right radiation dose'. © The Author 2014.

To obtain a better understanding on how non-human biota are affected by exposure to environmental radioactivity, it is essential to link observed effects to a correct estimate of absorbed ionising radiation dose. Current wildlife dose rate and risk assessment tools are not set up to assess changes in dose rate during organism development. This paper presents a dosimetry model for assessing dose rate and absorbed dose during seedling development of the model plant Arabidopsis thaliana. We included growth and radionuclide absorption dynamics into the dose calculations. This model was subsequently used to compare the dose and dose rate calculations for three radionuclides, 241Am (α-radiation), 90Sr (β-radiation) and 133Ba (γ-radiation), in a standard exposure scenario. We show that growth influences dose and dose rate and that this influence depends on the radionuclide and the organ involved. The use of dynamic dosimetry models greatly improves the dose calculations for effect studies. This research was funded by the Research Foundation Flanders (FWO) grant no. 1.1.763.10N in joint funding with SCK.CEN.

Both knowledge of the radiological protection and attention to it are indispensable for physicians performing endovascular treatment to avoid occurrence of radiation injuries. The system of radiological protection is recommended by the International Commission on Radiological Protection: justification, optimization, and individual dose and risk limits. Measured radiation dose in 12 patients who underwent neuroradiological endovascular treatments in the Niigata University Hospital ranged from 0.3Gy to1.9Gy, which was lower than the threshold dose for temporal epilation (3～5Gy), or cataract (2Gy). However, the principle of ALARA (as low as reasonably achievable) should be kept in any procedures of endovascular treatment to minimize the stochastic effect without a threshold, such as an effect on leukemia or genetic damage.

Em medicina nuclear, os trabalhadores diretamente envolvidos nos exames são frequentemente expostos à radiação ionizante. Neste estudo, utilizou-se um detector Geiger-Mueller (GM) para medir as doses da radiação ocupacional durante a realização de algumas das etapas mais críticas para a exposição à radiação em exames de cintilografia de perfusão miocárdica (CPM), são elas: 1) fracionamento das atividades no preparo das seringas; 2) administração do radiofármaco Tecnécio99m-sestamibi nas etapas de repouso e estresse; e 3) aquisição das imagens diagnósticas na sala de exames. Na avaliação, procurou-se discriminar e relacionar o tempo de experiência profissional às doses medidas. Para isso, foi acompanhado um total de 494 procedimentos entre os meses de outubro e dezembro de 2012, sendo 229 seringas preparadas no fracionamento das atividades, 165 administrações de radiofármaco (55 na etapa de repouso realizadas por profissionais com tempo de experiência superior a 2 anos, 55 na etapa de repouso realizada por profissionais com tempo de experiência inferior a 1 ano, e 55 na etapa de estresse), e 100 aquisições de imagem (50 na etapa de repouso e 50 na etapa de estresse). Foram avaliados também os registros das doses obtidas na monitoração individual por dosimetria termoluminescente (TLD), realizada entre julho de 2010 e dezembro de 2012. Os resultados obtidos com o detector GM, quando extrapolados para o acúmulo de doses no período de um ano, mostraram-se significantes em relação ao limite anual de 20 mSv determinado pela legislação brasileira para uma média em cinco anos consecutivos. As doses médias acumuladas nos procedimentos avaliados corresponderam aos seguintes percentuais em relação a esse limite: 1) 13%, no fracionamento das atividades; 2) 8% e 35%, na administração dos radiofármacos das etapas de repouso e estresse, respectivamente; e 3) 4% e 10%, na aquisição das imagens das etapas de repouso e estresse, respectivamente. Esses valores foram compatíveis com os resultados da monitoração individual por TLD, cujos valores registrados foram superiores (34,6% a 63,2% do limite de 20 mSv) pelo fato de não discriminar as doses em cada procedimento. Em virtude dos valores de dose encontrados, o uso de equipamentos de proteção individual e a agilidade na realização dos procedimentos, ligada a experiência profissional, contribuem de forma efetiva para a redução destes valores de dose. In nuclear medicine, workers directly involved in the exams are frequently exposed to ionizing radiation. In this study, a Geiger-Mueller detector was used to measure the occupational radiation doses while conducting some of the steps with critical radiation exposure during myocardial perfusion scintigraphy exams, which are: 1) fractionation of radiopharmaceutical activities in single-dose syringes, 2) Technetium99m-sestamibi administration during rest and stress steps, and 3) diagnostic images acquisition in the exam room. In the evaluation, it was sought to distinguish and relate the length of professional experience to measured doses. For that reason a total of 494 procedures were followed up including 229 fractionation of radiopharmaceutical activities in single-dose syringes, 165 radiopharmaceutical administrations (55 during rest step performed by professionals with experience time above two years, 55 during rest step performed by professionals with experience time below one year, and 55 during stress step), and 100 image acquisitions (50 during rest step and 50 during stress step). Dose records obtained during individual monitoring by thermoluminescent dosimetry (TLD) conducted between July 2010 and December 2012 were also evaluated. The results obtained by the GM detector, when extrapolated for dose accumulation over one year, proved to be significant in relation to the 20 mSv annual limit determined by Brazilian regulations to an average over five consecutive years. The mean accumulated doses evaluated during the procedures correspond to the following percentages relative to the annual limit value: 1) 13%, at the fractionation of radiopharmaceutical activities, 2) 8% and 35%, during rest and stress steps of radiopharmaceuticals administration, respectively, and 3) 4% and 10%, during rest and stress images acquisition, respectively. These values are consistent to the results of individual monitoring by TLD. These values were consistent to the results of individual monitoring by TLD, whose registered values were higher (34.6% to 63.2% of the limit of 20 mSv) due to the fact that they don't discriminate the dose by each procedure. Because of the dose values found, the use of personal protective equipment and the agility in procedures, linked to professional experience, effectively contribute to the reduction of these dose values.