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Este trabajo es una reelaboración del capítulo de la memoria de doctorado de Sánchez Vázquez, 2010, p.189-215, dedicado a la protección radiológica., En los debates sobre la controversia nuclear pocas veces se presenta en primera plana la cuestión de la seguridad laboral en las instalaciones radiactivas. Históricamente se ha priorizado la atención a los potenciales daños a la población general frente a la propia seguridad de los trabajadores empleados en instalaciones de riesgo. Con objeto de cubrir parcialmente ese vacío historiográfico, este trabajo pretende llevar a cabo un acercamiento al desarrollo de la protección radiológica laboral en España durante la dictadura del general Franco (1939-1975). Para ello repasaremos el surgimiento de las medidas de protección radiológica en el ámbito internacional y el posterior desarrollo legislativo en el caso español, proceso que fue paralelo al crecimiento del programa nuclear nacional. Para finalizar, exploraremos las principales evidencias del impacto de las radiaciones ionizantes sobre la población laboral española, In debates about nuclear controversy, the issue of occupational safety in radioactive facilities is rarely foregrounded; it has historically been relegated to second place compared to the attention given to potential harm to the general population. Aiming for, al least, partially filling this historiographical gap, this article deals with the development of occupational radiological protection in Spain under the dictatorship of General Franco (1939-1975). It covers the rise of radiological protection measures on an international level and the subsequent development of legislation in the case of Spain, a process that paralleled the growth of the nation’s nuclear program. Finally, it explores the main evidence of the impact of ionizing radiation on Spain’s working population.

In debates about nuclear controversy, the issue of occupational safety in radioactive facilities is rarely foregrounded; it has historically been relegated to second place compared to the attention given to potential harm to the general population. Aiming for, at least, partially filling this historiographical gap, this article deals with the development of occupational radiological protection in Spain under the dictatorship of General Franco (1939-1975). It covers the rise of radiological protection measures on an international level and the subsequent development of legislation in the case of Spain, a process that paralleled the growth of the nation s nuclear program. Finally, it explores the main evidence of the impact of ionizing radiation on Spain s working population.

Mestrado em Medicina Nuclear - Ramo de especialização: Tomografia por Emissão de Positrões A Tomografia por Emissão de Positrões (PET, do acrónimo em inglês, Positron Emission Tomography) mede quantitativamente a biodistribuição de radiotraçadores emissores de positrões in vivo. Sendo uma técnica de imagem quantitativa, esta requer procedimentos de controlo e garantia da qualidade para assegurar que são adquiridas imagens de elevado nível de qualidade e que estas imagens sejam aceitáveis e interpretáveis por qualquer especialista em qualquer hospital. A realização de um estágio de cariz profissional na área de especialização de Tomografia por Emissão de Positrões é de grande importância para aquisição de novas competências e conhecimentos técnicos que são relevantes para a minha formação enquanto Técnica de Medicina Nuclear. A formação na área da radiação médica e as experiências adquiridas neste terreno desenvolveram o gosto pelo trabalho em equipa e pelo domínio das tecnologias. Os principais objetivos propostos são o aprofundar de competências de PET/CT com 18FDG; adquirir novas competências no âmbito da prática clínica Avançada em PET/CT; familiarização com a legislação Inglesa no âmbito da Proteção e Segurança Radiológica em departamentos de PET/CT e, por fim, a elaboração e apresentação de casos clínicos. O conhecimento de novas realidades sociais, culturais e profissionais, o ritmo de trabalho e, sobretudo, enfrentar novos desafios são as motivações para a realização de um estágio. Acredito que este me tenha feito crescer a nível profissional, tendo sido uma oportunidade única para desenvolver conhecimentos já anteriormente adquiridos e também novas competências. ABSTRACT - Positron Emission Tomography (PET) quantitatively measures the biodistribution of positron emitting radiotracers in vivo. PET is a quantitative imaging technique and therefore requires a common quality control/quality assurance procedure to ensure that optimal images are acquired for our patients and that these images would be acceptable and interpretable by any clinician in any other hospital. The performance of a professional internship in the specialization area of Positron Emission Tomography is of a great importance in order to acquire new skills and experiences that are relevant to my training as a Nuclear Medicine technologist. The training in medical radiation and all the experiences obtained in this area have developed my taste for teamwork and the technology field. The main proposed goals are to further develop the skills on PET/CT with 18F-DG; acquire new skills in the field of Advanced Clinical Practice in PET/CT; familiarize myself with the English law on the Radiological Protection and Safety in departments of PET/CT and, finally, the preparation and presentation of clinical cases. The knowledge of new social, cultural and professional environments, the pace of work and, above all, the new challenges, were the motivations that made me choose an internship in this area. I believe that this experience made me grow professionally and it was a unique opportunity to develop knowledge previously acquired and new skills too.

El objetivo de este artículo es mostrar los principales resultados alcanzados en Chile durante los últimos 5 años en procedimientos de cardiología intervencionista (CI) pediátrica y discutir acciones futuras para mejorar la seguridad radiológica en esta práctica médica. Todos los sistemas de rayos X usados en procedimientos de CI pediátrica en Chile han sido caracterizados en términos de dosis y calidad de imagen. En conjunto con esto, se han medido las tasas de dosis de radiación dispersa a la posición de los ojos y tobillos de los médicos cardiólogos. En mayo de 2010, se celebró en Santiago de Chile, un taller organizado por la Agencia Internacional de Energía Atómica (IAEA) que fue el punto de partida para un programa piloto sobre dosimetría de pacientes y personal médico para América Latina y el Caribe, con participantes de 11 países. En forma paralela, se realizó un curso piloto de formación en Protección Radiológica. Los primeros valores de dosis a pacientes pediátricos reportados en el marco del programa piloto realizado por la IAEA en América Latina y el Caribe, incluyó 70 procedimientos de Chile que posteriormente, fueron ampliados a una muestra de 544 procedimientos. Para mantener y mejorar las prácticas aprendidas, pensamos que el primer y fundamental paso que se podría dar en Chile, sería revisar y actualizar la legislación que regula el uso de radiaciones ionizantes, donde se incorpore la implementación de programas de Garantía de Calidad y una formación en Protección Radiológica diferenciada de acuerdo a las necesidades del personal médico. Further actions to improve radiation safety in this medical practice are discussed. All the X-ray systems used in paediatric IC procedures in Chile have been characterized in terms of dose and image quality. In addition, dose rates of scattered radiation to the position of the eyes and ankles of cardiologists have been measured. In May 2010, in Santiago , Chile, a workshop organized by the International Atomic Energy Agency (IAEA) was the starting point for a pilot program on patient dosimetry and medical personnel for Latin America and the Caribbean, with participants from 11 countries. A pilot training course on Radiological Protection was given as part of the program. The first dose values reported for paediatric patients under the pilot program conducted by the IAEA in Latin America and the Caribbean included 70 procedures in Chile later extending to a total of 544 procedures. We think that a fundamental first step to improve IC radiation safety in Chile, would be to revise and update legislation on the use of ionizing radiation, including the implementation of quality assurance programs and training in radiation rrotection according to those involved in IC procedures.

El objetivo de este artículo es mostrar los principales resultados alcanzados en Chile durante los últimos 5 años en procedimientos de cardiología intervencionista (CI) pediátrica y discutir acciones futuras para mejorar la seguridad radiológica en esta práctica médica. Todos los sistemas de rayos X usados en procedimientos de CI pediátrica en Chile han sido caracterizados en términos de dosis y calidad de imagen. En conjunto con esto, se han medido las tasas de dosis de radiación dispersa a la posición de los ojos y tobillos de los médicos cardiólogos. En mayo de 2010, se celebró en Santiago de Chile, un taller organizado por la Agencia Internacional de Energía Atómica (IAEA) que fue el punto de partida para un programa piloto sobre dosimetría de pacientes y personal médico para América Latina y el Caribe, con participantes de 11 países. En forma paralela, se realizó un curso piloto de formación en Protección Radiológica. Los primeros valores de dosis a pacientes pediátricos reportados en el marco del programa piloto realizado por la IAEA en América Latina y el Caribe, incluyó 70 procedimientos de Chile que posteriormente, fueron ampliados a una muestra de 544 procedimientos. Para mantener y mejorar las prácticas aprendidas, pensamos que el primer y fundamental paso que se podría dar en Chile, sería revisar y actualizar la legislación que regula el uso de radiaciones ionizantes, donde se incorpore la implementación de programas de Garantía de Calidad y una formación en Protección Radiológica diferenciada de acuerdo a las necesidades del personal médico.

Artículo publicado en: Revista Chilena de Radiología 2013; 19(1): 05-11. El número de procedimientos radiológicos ha tenido un incremento acelerado durante la primera década del siglo XXI, obteniendo un impacto beneficioso sobre la salud. Sin embargo, este incremento conlleva a una mayor exposición a las radiaciones ionizantes. El uso de la radiación ionizante tiene un riesgo inherente, aun cuando el riesgo asociado a un examen radiológico es menor comparado con el riesgo natural, cualquier riesgo añadido, no importa cuán pequeño sea, es inaceptable si no se beneficia el paciente. El concepto de niveles de referencia diagnósticos se debe utilizar para reducir las variaciones en la práctica entre las instituciones y promover rangos óptimos, indicadores de dosis para los protocolos específcos de las diferentes modalidades. En general, los principios básicos de la protección radiológica (justifcación, optimización y límite de dosis) deben ser respetados para ayudar a contrarrestar el incremento injustifcado en el número de procedimientos que se realizan. The number of radiological procedures performed has had a rapid increase during the frst decade of the 21st century, achieving a benefcial impact on healthcare. However, this increase leads to a greater exposure to ionizing radiation. The use of ionizing radiation has an inherent risk. Although the risk associated with a radiological examination is minor compared to the natural risk, any added risk, no matter how small, is unacceptable if it does not beneft the patient. The concept of diagnostic reference levels should be used to reduce variations in practice among institutions and to promote optimal dose indicator ranges for specifc protocols of the different methods. In general, the basic principles of radiation protection (justifcation, optimization and dose limits) must be followed to reduce the unjustifed increase in the number of procedures being performed. 05-11 mavu@ula.ve

In France, the activities carried out by the "small-scale holders" of nuclear materials are organized by a specific regulatory system which defines in a detailed way their obligations and the means of control of the government. The first part of the article presents the legal framework relating to the use of nuclear materials by small-scale holders in civilian fields. The importance of the declaration of the nuclear material inventory is clearly emphasized and must be prepared and transmitted to the Institute for Radiological Protection and Nuclear Safety (IRSN) every year. The second part describes how this declaration is used to provide basic information for the competent Ministry and the inspectors to check the correct application of the regulatory requirements relating to physical protection and to the control of nuclear materials. Finally, the last part presents the on-site inspections carried out by sworn and accredited inspectors under the authority of the competent Authority, which provide an overall picture and allow an evaluation of the risks of theft, loss or diversion of these materials. © 2012 EDP Sciences.

During the course of a severe Pressurized Water Reactor accident, pressurization of the containment occurs and hydrogen can be produced by the reactor core oxidation and distributed in the containment according to convection flows and wall condensation. Filmwise wall condensation in the presence of non-condensable gases is a subject of many interests and extensive studies have been performed in the past. Some empirical correlations have demonstrated their limit for extrapolation under different thermal-hydraulic conditions and at different geometries/scales. The French Institute for Radiological Protection and Nuclear Safety (IRSN) has developed a numerical tool and an experimental facility in order to investigate free convection flows in the presence of condensation. The objective of this paper is to present numerical results obtained on different wall condensation tests in 7 m 3 volume vessel (TOSQAN facility), and to compare them with the experimental ones. Over eight tests are considered here, and codeexperiment comparison is performed on many different locations, giving an extensive insight of the code assessment for air-steam mixture flows involving wall condensation in the presence of non-condensable gases. © 2012 Elsevier B.V. All rights reserved.

This work deals with the control of radioactive aerosols emissions inside the nuclear medicine facilities. These emissions occur during pulmonary scintigraphy examinations using aerosols marked with 99mTc. Using a test chamber, we have developed a method permitting to quantify these emissions around the aerosol generator. A method dedicated to emissions measurement coming from the patient during the pulmonary ventilation is also described. The results obtained on one patient are exposed in this thesis. We characterized and modelled the ventilation of a complete nuclear medicine department with a CFD (Computational Fluid Dynamics) software. This permitted us to study the dissemination of the radioactive aerosol and to compare it with measures of ambient air activity. The numerical model of this department was then employed to test containment solutions and to help defining the best location for air contaminations sensors. An original method combining staff position information and the simulation of the dissemination for the aerosol released has been used to confirm the exposure levels for several professional groups and enhance the workplace studies., Ce travail traite de la maîtrise des émissions d'aérosols radioactifs en médecine nucléaire. Ces émissions ont lieu lors des examens de scintigraphie pulmonaire réalisés avec des aérosols marqués au technétium 99 métastable. Nous avons développé une méthode, utilisant une enceinte d'essai, qui permet de quantifier ces émissions au niveau du générateur. Nous avons mesuré une activité émise dans l'environnement. Une méthode dédiée à la mesure des émissions provenant du patient lors de la ventilation est également proposée et a été employée sur une patiente. Les résultats des différentes mesures et évaluations sont exposés dans ce mémoire. Nous avons caractérisé et modélisé la ventilation d'un service de médecine nucléaire entier à l'aide d'un logiciel de CFD (Computational Fluid Dynamics). Cela nous a permis d'étudier la dissémination de l'aérosol radioactif et de comparer les résultats à des mesures d'activité volumique de l'air ambiant. Le modèle numérique de ce service a été utilisé pour tester des solutions de confinement et aider à définir la position de capteurs de surveillance de la contamination de l'air. Une méthode originale combinant l'étude de position du personnel et la simulation de dissémination de l'aérosol émis, a servi à confirmer les niveaux d'exposition de plusieurs catégories professionnelles et enrichir les études de poste.

OBJETIVO: Determinar o nível de qualidade da proteção radiológica para os pacientes durante a realização de exames radiológicos e avaliar a efetividade de uma intervenção dirigida a melhorar a qualidade. MATERIAIS E MÉTODOS: Realizou-se um ciclo de melhoria em um serviço de radiologia da Administração Geral de Saúde do Algarve, Portugal. Utilizando seis critérios de qualidade, foram efetivadas uma avaliação, uma intervenção focada nos critérios mais problemáticos (durante oito meses) e uma reavaliação. As amostras foram aleatórias (n = 60), possibilitando a inferência sobre as estimativas pontuais e intervalos de confiança do cumprimento de cada critério, assim como o cálculo da significância estatística da melhoria identificada, através do teste Z. RESULTADOS: Na avaliação inicial, todos os critérios de qualidade apresentaram falhas. Após a intervenção, a melhoria relativa mínima foi de 33% em cinco dos seis critérios, sendo significativa (p < 0,05) em dois deles. A frequência absoluta de não conformidades diminuiu de 38 (primeira avaliação) para 21 (segunda avaliação), que corresponde a uma melhoria de 44,7%. CONCLUSÃO: O início do ciclo de avaliação institucional revelou uma margem de melhoria que antes parecia incipiente, porém, a intervenção implementada foi efetiva para estimular boas práticas e aumentar o nível de proteção radiológica para os pacientes. OBJECTIVE: To determine the level of quality in radiation protection of patients during radiological examination, evaluating the effectiveness of an intervention aimed at enhancing the quality of such a protection. MATERIALS AND METHODS: A quality improvement cycle was implemented in a radiology service of the Regional Health Administration, in Algarve, Portugal. Based on six quality criteria, an initial evaluation was performed and followed by an intervention focused on the most problematic points (over an eight-month period) and a subsequent quality reassessment. A random sampling (n = 60) has allowed the authors to infer the point estimates and confidence intervals for each criterion, as well as calculating the statistical significance of the results by means of the Z-test. RESULTS: Initially, deficiencies were observed in relation to all the quality criteria. After the intervention, a minimum relative improvement of 33% was observed in five of the six criteria, with statistical significance (p < 0.05) in two of them. The absolute frequency of non-compliance decreased from 38 (first evaluation) to 21 (second evaluation), corresponding to a 44.7% improvement. CONCLUSION: The first institutional evaluation cycle showed a seemingly incipient improvement margin. However, the implemented intervention was effective in stimulating good practices and improving the level of radiological protection of patients.

Mestrado em Radiações Aplicadas às Tecnologias da Saúde. Área de especialização: Proteção contra Radiações. O cancro da mama é o tipo de cancro mais comum nos membros do sexo feminino, sem considerar o cancro da pele, e corresponde à segunda causa de morte por cancro, na mulher. Atualmente em Portugal com uma população feminina de 5 milhões de habitantes, surgem 4.500 novos casos de cancro da mama por ano, ou seja 11 novos casos por dia, morrendo por dia 3 mulheres com esta doença. O objetivo deste estudo é verificar qual das combinações de Kv, mAs e ânodo/filtro cumpririam com os critérios de qualidade de imagem, segundo diretrizes europeias, com medição da kerma à entrada da pele e posterior cálculo da dose glandular média. Neste trabalho foi usado o sistema de mamografia digital direta, que permitiu observar qual das combinações é a mais benéfica em termos de qualidade de imagem, segundo critérios de qualidade já definidos recorrendo ao fantoma Leeds, modelo DMAM. Posteriormente foi calculada a dose de entrada na pele recorrendo a um detetor de leitura direta, Unfors Xi. Os resultados afirmam que o nível de contraste considerado aceitável permite uma considerável redução da exposição utilizada. A partir da medição da Kerma à superfície de entrada e dose glandular média verificou-se qual das combinações corresponde a uma menor dose para o paciente, que corresponde à combinação ânodo/filtro W/Rh a operar a 30kV, com uma exposição de 63mAs, conjugando assim uma baixa dose com um nível aceitável de contraste da imagem. Esta redução de dose num órgão radiossensível como a mama é uma grande vantagem neste tipo de exames. - ABSTRACT - Breast cancer is the most common type of cancer among women, apart from skin cancer, and corresponds to the second cause of death by cancer in women. Currently, in Portugal, with a female population of 5 million, there are 4,500 new cases of breast cancer per year, in other words 11 new cases per day, dying 3 women per day with this disease. The goal of this study was to check which combinations of Kv, mAs and anode/filter comply with the criteria for image quality, according to European guidelines and also to measure the entrance surface air kerma of the skin and subsequent determination of the mean glandular dose. We used the direct digital mammography system, which allowed to observe which of possible combinations is the more beneficial in terms of image quality, according to quality criteria already defined for the Leeds, DMAM model phantom Skin Entrance Surface Dose was later determined. It dose of skin entry performed using a direct read detector, Unfors Xi. The results show that for one acceptable contrast level a considerable reduction in exposure to nearly half of the one normally employed can be achieved. From measuring the input surface, Air Kerma and mean glandular dose, checked which of the combinations provides smaller doses we found that the combination is the optimal anode/filter W/Rh operating 30kV, with an exposure of 63mAs to combination dose of lowest with at acceptable level of image contrast. This dose reduction in a radio-sensitive organ such as the breast is a great advantage in this type of exams.

Mestrado em Radiações Aplicadas às Tecnologias da Saúde - Área de especialização: Proteção Contra Radiações A ortopantomografia é essencial para o diagnóstico, planeamento e monitorização do tratamento ou de lesões dentárias. A exposição e riscos devem ser considerados, uma vez que se trata de um exame que utiliza radiação ionizante. O efeito da radiação ionizante sobre a tiróide tem vindo a ser estudado ao longo de várias décadas. A associação à radiação de hipertiroidismo, hipotiroidismo, nódulos e cancro da tiróide é frequentemente relatada, contudo os limites de dose de radiação ainda não estão bem estabelecidos. Os objetivos principais deste trabalho são: registar a dose à entrada da pele (DEP) a nível da tiróide, de pacientes que efetuaram o exame de ortopantomografia, utilizando para a medição uma câmara de ionização cilíndrica e um eletrómetro. Verificar se existe diferença na dose à entrada da pele a nível da tiróide, com e sem a colocação da proteção da tiróide, através de um colar cervical de chumbo, concluindo assim a eficiência desta proteção. O alvo de recolha de dados ou amostra correspondeu a 2 pacientes do sexo masculino, 2 do sexo feminino e 2 crianças, em cada uma das três Clínicas (portanto, 6 pacientes por cada clínica e 18 no total). Dos pacientes que efetuaram o exame de ortopantomografia, foi medida a dose à entrada da pele, através de uma câmara de ionização cilíndrica e de um eletrómetro, ao nível da tiróide. Em metade da amostra – um dos pacientes do sexo masculino, um do sexo feminino e uma criança – foi medida a dose à entrada da pele a nível da tiróide sem proteção e a restante metade da amostra foi medida essa mesma dose com proteção da tiróide – um colar cervical (proteção de chumbo da tiróide), e verificada a diferença entre estes valores. Os resultados das doses nos pacientes sem proteção da tiróide variaram entre 0,0251 e 0,0839mGy e as doses com proteção da tiróide variaram entre 0,0139 e 0,0476mGy. Após estas medições foram verificadas e comparadas também as doses nas três clínicas, em fantomas de diferentes diâmetros, simulando assim os diferentes diâmetros do pescoço do homem, da mulher e da criança, com e sem proteção da tiróide. Os resultados das doses nos fantomas sem proteção da tiróide variaram entre 0,0051 e 0,0325mGy e as doses com proteção da tiróide variaram entre 0,0028 e 0,0164mGy. Os valores de DEP medidos neste estudo, a nível da tiróide, foram comparados aos valores propostos pelas European Guidelines (0,7 mGy). Os valores obtidos foram ainda comparados com referências internacionais, segundo White e Pharoah deve ser cerca de 0,074mGy e ainda segundo Oliveira, a dose recolhida nos fantomas foi de 0,002mGy e 0,003mGy. ABSTRACT - The panoramic radiography is essential for diagnosis, treatment planning and treatment monitoring or dental injuries. The exposure and risks should be considered, since this is a test which uses ionizing radiation. The effect of ionizing radiation on the thyroid has been studied over several decades. The association of hyperthyroidism, hypothyroidism, nodules and Thyroid cancer with radiation is often reported, but the radiation dose limits are not well established. The main objectives of this study are: to register the entrance skin dose (ESD) at the level of thyroid patients who performed the examination of panoramic radiography using for measuring a cylindrical ionization chamber and an electrometer and the other objective is to verify if there are differences in the entrance skin dose at the level of thyroid by placing the protective thyroid through a collar of lead, thus verifying the efficiency of protection. It was used as target data collection or sample 2 male, 2 female and 2 children, in each of the three Clinics. The patients who have performed the test of panoramic radiography dose were measured at the entrance to the skin through a cylindrical ionization chamber and an electrometer at the level of thyroid. In half of the sample - one of the males, one female and one child - was measured entrance skin dose at the thyroid without protection, and half the sample was measured that same dose with thyroid protection, a cervical collar (lead protection of thyroid), and investigate the difference between these values. The results of the doses in patients without thyroid protection ranged between 0.0251 and 0.0839 mGy and thyroid dose with protection ranged between 0.0139 and 0.0476 mGy. After these measurements were also checked and compared the doses in the three clinics in phantoms of different diameters, thus simulating the different diameters of the necks of men, women and children, with and without protection of the thyroid. The results of dose in unprotected thyroid phantoms ranged from 0.0051 to 0.0325 mGy and thyroid dose with protection ranged from 0.0028 to 0.0164 mGy. ESD values measured in this study, the level of the thyroid, were compared to the values proposed by the European Guidelines (0.7 mGy). The values obtained were compared with international benchmarks, according to White and Pharoah should be about 0.074 mGy and also according to Oliveira, phantoms collected in the dose were 0.002 and 0.003 mGy mGy.

This thesis is based on the assumption that the intersection of moral philosophy and practical risk management is a rewarding area to study. In particular, the thesis assumes that concepts, ideas, and methods that are used in moral philosophy can be of great benefit for risk analysis, but also that practices in risk regulation provide a useful testing ground for moral philosophical theories. The thesis consists of an introduction and five articles. Article I is a review article on social and ethical aspects of radiation protection related to nuclear power generation. The paper concludes that four areas of social and ethical issues stand out as central: The first is uncertainty and the influence of value judgments in scientific risk assessments. The second is the distributions of risks and benefits between different individuals, in both space and time. The third is the problem of setting limits when there is no known level of exposure associated with a zero risk. The fourth is related to stakeholder influence and risk communication. Article II discusses ethical issues related to the proposal that doses (or risks) below a certain level should be excluded from the system of radiation protection, without any regard for the number of people exposed. Different arguments for excluding small radiation doses from regulation are examined and a possible solution to the problem of regulating small risks is proposed in the article: Any exclusion of small doses (or risks) from radiation protection ought to be based on a case-by-case basis, with the condition that the expected value of harm remains small. Article III examines what makes one distribution of individual doses better than another distribution. The article introduces a mathematical framework based on preference logic, in which such assessments can be made precisely in terms of comparisons between alternative distributions of individual doses. Principles of radiation protection and from parallel discussions in moral philosophy and welfare economics are defined using this framework and their formal properties analyzed. Article IV argues that the ethical theory of “responsibility-catering prioritarianism” is well positioned to deal with the reasonable requirements in an ethical theory of risk. The article shows how responsibility-catering prioritarianism can be operationalized using a prioritarian social welfare function based on hypothetical utilities. For this purpose, a hypothetical utility measure called ‘responsibility-adjusted utility’ is proposed, which is based on the utility that would normally be expected given circumstances outside of the control of the individual. Article V was written as a response to the Fukushima disaster. Several authors have called the Fukushima disaster a ‘black swan.’ However, the article argues that the hazards of large earthquakes and tsunamis were known before the accident, and introduces and defines the concept of a ‘black elephant,’ as (i) a high-impact event that (ii) lies beyond the realm of regular expectations, but (iii) is ignored despite existing evidence. QC 20120816

The emission of radiation from a contaminated body region is connected with the dose received by radiosensitive tissue through the specific absorbed fractions (SAFs) of emitted energy, which is therefore an essential quantity for internal dose assessment. A set of SAFs were calculated using the new adult reference computational phantoms, released by the International Commission on Radiological Protection (ICRP) together with the International Commission on Radiation Units and Measurements (ICRU). Part of these results has been recently published in ICRP Publication 110 (2009 Adult reference computational phantoms (Oxford: Elsevier)). In this paper, we mainly discuss the results and also present them in numeric form. The emission of monoenergetic photons and electrons with energies ranging from 10 keV to 10 MeV was simulated for three source organs: lungs, thyroid and liver. SAFs were calculated for four target regions in the body: lungs, colon wall, breasts and stomach wall. For quality assurance purposes, the simulations were performed simultaneously at the Helmholtz Zentrum München (HMGU, Germany) and at the Institute for Radiological Protection and Nuclear Safety (IRSN, France), using the Monte Carlo transport codes EGSnrc and MCNPX, respectively. The comparison of results shows overall agreement for photons and high-energy electrons with differences lower than 8%. Nevertheless, significant differences were found for electrons at lower energy for distant source/target organ pairs. Finally, the results for photons were compared to the SAF values derived using mathematical phantoms. Significant variations that can amount to 200% were found. The main reason for these differences is the change of geometry in the more realistic voxel body models. For electrons, no SAFs have been computed with the mathematical phantoms; instead, approximate formulae have been used by both the Medical Internal Radiation Dose committee (MIRD) and the ICRP due to the limitations imposed by the computing power available at this time. These approximations are mainly based on the assumption that electrons are absorbed locally in the source organ itself. When electron SAFs are calculated explicitly, discrepancies with this simplifying assumption are notable, especially at high energies and for neighboring organs where the differences can reach the same order of magnitude as for photon SAFs. © 2010 Institute of Physics and Engineering in Medicine.

Recent new insights about radon risk and increasing patient exposure due to medical imaging, as well as unexpected cardiovascular effects of ionizing radiation are challenging our classical radiological protection approaches and should be viewed in a larger public health perspective. Concepts as global indoor air quality, long term sustainability, risk awareness or precaution ask for a wider approach encompassing scientific vigilance, value judgements, risk communication and sociological participation in risk governance. Progress in radiological protection needs a new transdisciplinary framing of complexity where social sciences and humanities are more actively involved to complete scientific insight.

The Advisory Panel of the European Commission on Radiological Protection, referred to in Article 31 of EURATOM Treaty, adopted in late February of 2010 the most important aspects of the future directive. This new Directive also adpats into a single legislative text the five previous directives, it also includes protection against gas radon on which there was previously only a recommendation. The issues of greatest concern are the new recommendations related to emergency planning, the new framework of the protection system now based on all types of situations, planned, existing and emergency. In addition, specific aspects of processing industries naturally occurring radioactive materials (NORM) are fully integrated in the protection system has included a major overhaul of protection in medical applications including extending what is stated in the current directive on the subject , addresses the specific aspects for imaging non-medical reasons, which sets out new requirements with respect to radon in homes and workplaces and, finally, are issued new requirements for residential construction materials. El Grupo de Expertos Asesor de la Comisión Europea en Protección Radiológica, contemplado en el artículo 31 del Tratado EURATOM, aprobó a finales de febrero de 2010 los aspectos más importantes de la futura directiva. Esta nueva directiva, además de que refunde en un único texto legislativo las cinco directivas anteriores, incorpora también la protección con respecto al gas radón sobre el cual solo existía anteriormente una recomendación. Los aspectos de mayor interés son las nuevas recomendaciones relacionadas con la planificación de las emergencias, el nuevo marco del sistema de protección basado ahora en todos los tipos de situaciones, planificadas, existentes y de emergencias. Además, los aspectos específicos de industrias que procesan materiales radiactivos naturales (NORM) están integrados totalmente en el sistema de protección; se ha incluido una revisión importante de la protección en las aplicaciones médicas incluso ampliando lo que se establecía en la actual directiva sobre el tema; se tratan los aspectos específicos para la obtención de imágenes por motivos no médicos; se establecen nuevos requerimientos con respecto al radón en viviendas y lugares de trabajo y, por último, se dictan nuevos requerimientos para materiales de construcción de viviendas.

Dissertação de Mestrado em Gestão dos Serviços de Saúde O risco pode considerar-se minimizado quando a política de segurança radiológica da instalação estiver em conformidade com a legislação e as atitudes dos profissionais forem proactivas na aplicação dos princípios básicos da radioprotecção. A Comissão Internacional de Protecção Radiológica estabelece três princípios na radioprotecção, nomeadamente a justificação, a optimização e a limitação. Esta investigação tem como objectivo analisar o risco através da avaliação das atitudes nos procedimentos preventivos de Radioprotecção nos serviços de radiologia, no sector público/sector privado do Nordeste Transmontano. Para tal, procedeu-se à elaboração de um questionário com 30 questões, que foi aplicado em dois centros hospitalares, quatro Centros de Saúde e 8 clínicas. Responderam 96 técnicos de radiologia. Os dados obtidos foram posteriormente organizados de modo a serem tratados estatisticamente no software SPSS. Concluímos que, apesar de a maior parte dos técnicos de radiologia da região de Trás-os-Montes e Alto Douro actuarem de uma forma proactiva, alguns manifestam ainda atitudes reactivas no que diz respeito à sua e à protecção do utente. Os técnicos de radiologia não se protegem suficientemente face à radiação pois nem sempre usam os equipamentos de protecção individual quando necessário, e nem sempre usam o dosímetro individual. Já a radioprotecção para o utente também nem sempre é posta em prática, principalmente o uso de protecções nas zonas mais sensíveis (gónadas, mamas, tiróide e globo ocular). As instituições revelam algumas atitudes reactivas no cumprimento da aplicação da legislação. Torna-se, então, imperativo a consciencialização dos profissionais e responsáveis das instituições quanto aos potenciais riscos da radiação ionizante e a aplicação correcta dos regulamentos de protecção radiológica. Risk can be considered minimised when the policy of radiological security settlement is consistent with the legislation and the professionals’ attitudes are proactive as far as the appliance of the basic principles of radioprotection is concerned. The International Radiological Protection Commission sets therefore three core principles of radiological protection, namely justification, optimisation and the application of dose limits. The current research intends to analyse the risk by assessing the attitudes concerning the preventive radioprotection procedures in the radiological services of the both private and public sector located in North Eastern Portugal. In order to achieve this purpose, we did a 30-question survey applied in two hospital centres, four Health Centres and eight clinics. 96 radiology technicians responded to the questionnaire. Obtained data were subsequently organised in order to be statistically worked in SPSS software. We concluded that, even though the majority of the radiology technicians of the Trás-os-Montes and Alto Douro region works in a proactive way, there are those who still maintain a reactive attitude towards theirs and the patient’s protection. Radiology technicians do not follow the necessary measures to protect themselves against radiation, because they not always use individual protection equipment when needed as well as the individual dosimeter. Radioprotection for the patient is not always also put into practice, mainly the use of protection in the most sensitive areas (gonads, breasts, thyroid and ocular globe). The health institutions reveal thus reactive attitudes in the accomplishment of rules. It becomes then crucial to alert health professionals and the ones in charge of the health institutions to the potential risks of ionising radiation and to the correct application of the radiological protection rules.

The system of radiological protection of the environment that is currently under development is one contribution to the general need to adequately protect the environment against stress. Dominated by operational goals, it emphasizes conceptual and methodological approaches that are readily accessible today: reference organisms supported by individual-based traditional ecotoxicological data. Whilst there are immediate advantages to this approach (pragmatism, consistency with other approaches in use for man and biota), there are also clear limitations, especially in a longer run perspective, that need to be acknowledged and further considered. One can mention a few: uncertainties generated by the need for various extrapolations (from lower to higher levels of biological organisation, ...), various features missed such as potential ecological impact through impairment of ecosystem processes, trans-generational impacts as mediated through genomic instability, indirect effects mediated through trophic interactions or disruption of ecological balances,... Such limitations have already been faced in other fields of environmental protection against other stressors, pushing a number of environment professionals to assign stronger emphasis on more systemic approaches. This review discusses the advantages and limitations of the current approach designed for the radiological protection of non-human biota in the broader context of environment protection as a whole, with especial reference to upcoming trends and evolutions. This leads in particular to advocating the need to boost scientific and methodological approaches featuring the ecosystem concept as a mean to access a unified goal of protection: preserving life sustainability through protection of ecosystem structure and functioning. © 2009 Elsevier Ltd. All rights reserved.

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Made available in DSpace on 2018-06-27T18:56:32Z (GMT). No. of bitstreams: 2 Marcel Zago Botelho.pdf: 6878925 bytes, checksum: 22ad774a47cc0769a99676eb64ea10fe (MD5) Marcel Zago Botelho.pdf.jpg: 3401 bytes, checksum: 2e13d66eded5ce0245644489e795b21f (MD5) Previous issue date: 2009-03-30 Coordenação de Aperfeiçoamento de Pessoal de Nível Superior The aim of this study is to evaluate the attenuation properties of the nanocomposites in the energy range between 20 and 120 keV. In order to evaluate the efficiency of nanostructured materials in the attenuation of radiation the results will be compared to data obtained with the same material in the non-nanostructured form. The nanostructured materials are characterized by having a size of crystallites less than 100nm, and shows different properties with respect to conventional materials. The nanocomposites used in this study were produced through the aggregation of nanoparticles of copper oxide (CuO) and zinc oxide (ZnO) to beeswax. The concentration of nanoparticles in the composite was varied between 5% and 10%. For comparison purpose the copper oxide and zinc oxide in a non-aggregated nanoparticles were also agregated in a nonnanoparticulated form to beeswax in the same proportion as for nanostructured materials. Samples were produced with dimensions 10 cm x 10 cm and 2 mm in thicknesses. The attenuation properties of the samples produced were evaluated at high energy X-ray beams, emmited by a X-ray equipment used in conventional radiology, and the low energy x-ray beams are produced by a clinical mammography equipment. The air kerma values, for different material thicknesses, were measured with an ionization chamber for x-ray beam produced at 60 kV and 102 kV. Results shows that the attenuation provided by the copper oxide is slighly higher for the nanoestrured materials compared with for the non-nanoestrutured ones. In the case of the zinc oxide, the material in the non-nanometric form shows an increasing of the attenuation relative to the nanoparticulates ones. In the mammography energy range the study was carried out for beams generated at 22, 26 and 30 kV. It is observed that the copper oxide in nanometric structure attenuate at about 23% more radiation than the same material in the non-nanoparticulate form. In the case of the zinc oxide the attenuation is higher at about 7% for the material in the non-nanometric form. This study suggest that nanostructured materials show great potential for application in radiological protection, because it can be easily incorporated into different compounds allowing the development of new materials for use in radiological protection. Este estudo tem por objetivo determinar as propriedades de atenuação de nanocompósitos na faixa de energia entre 20 e 120 keV. Com o propósito de avaliar a eficiência dos materiais nanoestruturados na atenuação da radiação os resultados obtidos serão comparados aos dados obtidos com o mesmo material na forma não-nanoestruturada. Os materiais nanoestruturados são caracterizados por terem um tamanho de cristalito inferior a 100nm e apresentar propriedades diferenciadas em relação aos materiais convencionais. Os nanocompósitos utilizados neste trabalho foram obtidos a partir da agregação de nanopartículas de óxido de cobre (CuO) e óxido de zinco (ZnO) a cera de abelha alvejada. A concentração de nanopartículas nos compostos foi variada entre 5% e 10%. Para fins de comparação, o óxido de cobre e o óxido de zinco, na forma nãonanoparticulada também foram agregados na mesma proporção que os materiais nanoestruturados a cera de abelha alvejada. Foram produzidas amostras com dimensões 10 cm x 10 cm e 2 mm de espessura. As propriedades de atenuação destas amostras foram avaliadas em feixes de raios X produzidos por um equipamento de radiologia convencional, e por um equipamento clínico de mamografia. Na região de radiologia convencional foram realizadas medições de kerma no ar para diferentes espessuras de material para feixes de raios X gerados nas tensões de 60 e 102 kV. Os resultados obtidos mostraram uma leve tendência de maior atenuação da radiação pelo o óxido de cobre na forma nanométrica que o óxido de cobre na forma não-nanométrica. Observou-se uma tendência de maior atenuação pelo óxido de zinco na forma não-nanoparticulada. A atenuação da radiação para feixes de mamografia foi avaliada nas tensões de 22, 26 e 30 kV. Os dados obtidos mostraram que para o óxido de cobre na forma nanométrica a atenuação da radiação é maior em até 23% com relação às estruturas na forma não-nanométrica. Para o óxido de zinco a atenuação para o material não-nanométrico foi superior em até 7% relativo às estruturas na forma nanométrica. Os resultados obtidos neste trabalho sugerem que os materiais nanoestruturados mostram um grande potencial para aplicação em proteção radiológica, pois podem ser facilmente incorporados a diferentes compostos possibilitando o desenvolvimento de novos materiais.

Naar aanleiding van de aanstelling van het nieuwe bureau van de wetenschappelijke verniging voor stralingsbescherming schetst de voorzitter de voorbije activiteiten en de nieuwe programmatie met aandacht voor de nieuwe wetenschappelijke indicaties die de perspectieven van dit transdisciplinair vakgebied zullen kleuren. Hierbij werd vooral gerapporteerd uit de IRPA conferentie in Buenos Aires en de EC seminaries over het stralingsrisico voor de gezondheid

Over the last decade a number of models and approaches have been developed for the estimation of the exposure of non-human biota to ionising radiations. In some countries these are now being used in regulatory assessments. However, to date there has been no attempt to compare the outputs of the different models used. This paper presents the work of the International Atomic Energy Agency's EMRAS Biota Working Group which compares the predictions of a number of such models in model-model and model-data inter-comparisons. © 2008 IAEA.

In 2000, abnormally high ray fluxes have been detected on some beaches of Camargue. Then, sands of these beaches have been studied from a radiological point of view, showing on the one hand mean levels of uranium-238 and thorium-232 activity about some tens of Bq kg-1, and on the other hand some hot spots with more of 1000 Bq kg-1; and even more on two beaches: one to the east of the Beauduc lighthouse, the other to the east of Espiguette lighthouse. This radioactivity, of natural origin, is responsible of exposure of the public frequenting these two secluded beaches, but nevertheless open to everybody. The Institute for radiological protection and nuclear safety has carried out a dose assessment for people likely to frequent these beaches, taking into account local measurements and samples, in establishing the solubility of sands in the gastric and intestinal fluids, and with assumptions for site frequentation (scenarios). The maximal annual effective dose is about 0.8 mSv for adults and about 0.5 mSv for children; very wise values, in which external exposure widely predominates. © 2008 EDP Sciences.; En 2000, des flux de rayonnement anormalement élevés ont été détectés sur certaines plages du littoral camarguais. Les sables du littoral camarguais ont alors fait l’objet d’une caractérisation radiologique montrant des activités moyennes de quelques dizaines de Bq kg-1 en uranium-238 et thorium-232 d’une part, et l’existence de points chauds à plus de 1000 Bq kg-1 d’autre part ; voire plus sur deux plages : l’une située à l’Est du phare de Beauduc, l’autre située à l’Est du phare de l’Espiguette. Cette radioactivité, d’origine naturelle, est responsable de l’exposition des personnes fréquentant ces deux dernières plages relativement isolées, mais néanmoins accessibles à tout public. L’Institut de radioprotection et de sûreté nucléaire a réalisé une évaluation des doses susceptibles d’être reçues par des personnes fréquentant ces deux dernières plages, en se basant sur des mesures et des prélèvements effectués in situ, en établissant expérimentalement la solubilité des sables dans les fluides gastrique et intestinal, et en formulant des hypothèses sur la fréquentation des lieux (scénarios). La dose annuelle maximale ainsi évaluée est de l’ordre de 0,8 mSv pour des adultes et 0,5 mSv pour les enfants ; valeurs vraisemblablement très prudentes dans lesquelles la dose par exposition externe prédomine largement.

Journal of Cultural Heritage, nº 9 (2008), p. 64-68 The presence of uraniumglass objects in museum and private collections has raised radiation protection concerns resulting from possible exposure to ionizing radiation emitted by this type of object. Fourteen glass objects with different uranium contents were studied. Dose rates (b þ g radiation)were measured with a beta/gamma probe at several distances fromthe glass objects. In general, the determined dose rates did not raise any concern as long as some precautions were taken. Radon (222Rn), usually the most important contributor for the overall natural dose exposure resulting from radium (226Ra) decay in the uraniumnatural series, was also evaluated and it was found to be within the background values. Non-invasive analyses of the uranium content were made using micro-EDXRF analysis, measuring the radiation emitted by the objects and fluorescence spectroscopy.

The assessment of absorbed, equivalent and effective doses after internal exposure is based on activity measurement by in vivo counting or bioassay. A dose value is derived from this measurement by means of biokinetic and dosimetric models which describe the behaviour of radionuclides in the body of a reference man and the subsequent deposition of energy. To enforce regulatory dose limits, monitoring programs are designed. The doses can be estimated from the measurement data according to a standard procedure as proposed by the IDEAS group. However, a significant uncertainty is associated with the dose estimate, due to the uncertainties of measurement, to the incomplete knowledge of the conditions of exposure and to the imperfect realism of the models. In addition to this uncertainty, the extrapolation to low dose of biological effects observed at higher dose, the chemical toxicity of radionuclides and the heterogeneous energy deposition make the estimation of the risk following an internal exposure very difficult. As a conclusion, it should be reminded that the effective dose is a tool for the management of radiological protection but not a quantitative indicator of the individual risk. © 2007 EDP Sciences.; Protéger l’environnement est aujourd’hui une problématique globale qui concerne toutes les activités de l’homme. Il s’agit donc d’être capable de démontrer la compatibilité de ces activités avec la protection des milieux naturels, mais aussi si nécessaire d’agir pour pallier à un risque potentiel ou avéré, et ce généralement dans le cadre d’une réglementation de plus en plus stricte. Dans le domaine chimique, la prise en compte de cette problématique se traduit par l’existence de méthodes dédiées à l’évaluation du risque environnemental. Dans le domaine radiologique, la nécessité de disposer de tels outils s’est accentuée récemment, afin de pouvoir justifier aux yeux du public et en toute transparence le rejet de substances radioactives dans l’environnement, de répondre aux exigences des nouvelles réglementations en matière de protection de l’environnement et enfin d’harmoniser les approches entre radioprotection humaine et radioprotection de l’environnement, mais aussi entre polluants chimiques et radioactifs, simultanément présents par exemple dans les rejets de routine des centres nucléaires de production d’électricité. Dans cette optique d’harmonisation, les démarches d’évaluation du risque à l’environnement lié à la présence de radionucléides ou de substances chimiques sont présentées depuis les concepts théoriques jusqu’à leur mise en œuvre comparative, approche nouvelle en cours de développement dont les premiers résultats sont présentés.

Introduction to the book of contributions presented during a conference organised by CITES,UCL and PISA, SCKCEN after 2 years of preparing discussions on a number of ethical issues in radiological protection and radioactive waste management. The context of the dynamics in ICRP recommendations is pictured and all contributions situated.

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

Since its foundation in 1928, the International Commission on Radiological Protection (ICRP) has regularly produced recommendations on the protection against ionising radiation; these recommendations are currently taken up by international organisations and by states. Since 1990, date of issue of the most recent recommendations (Publication 60), advances in scientific knowledge, technical developments, feedback and desire to meet modern societal developments, have incited the ICRP to modify its system of protection. The latest draft, which was recently presented openly for consultation and proposals, is described and discussed. © 2005 EDP Sciences.

International audience; Long chronological series of atmospheric radioactivity observatory is used for the understanding of radionuclide behavior in the atmospheric compartment. Artificial radionuclides have been introduced in the environment after nuclear weapons tests, nuclear industries and nuclear accident such as Chernobyl (1986). The artificial radionuclide storage compartment evolution could also be understood by the behavior of natural radionuclides (i.e. 7Be, cosmogenic radionuclide). The Institute for Radiological Protection and Nuclear Safety (IRSN)'s atmospheric radioactivity observatory has begun in 1959. Nowadays, aerosol samples are collected on 6 stations located in the France (mainland) and 2 stations in the south hemisphere. In 2002, 137Cs levels in aerosols are around 0.4 μBq m-3 in France (mainland) and 10 times lower at Tahiti. For 7Be, levels are similar whatever the station location and are around 3 200 μBq m-3. © 2004 EDP Sciences.; Les longues séries temporelles d'observation de la radioactivité dans l'atmosphère (au niveau du sol) permettent d'étudier l'évolution de ce réservoir après les injections des expérimentations nucléaires militaires, de l'activité industrielle, ou suite aux accidents tel que celui de Tchernobyl (1986). Conjointement à l'observation des radionucléides d'origine artificielle, les radionucléides formés par l'interaction du rayonnement cosmique dans la haute atmosphère, comme 7Be, sont quantifiés. La corrélation entre les composantes naturelles et artificielles permet de mieux comprendre l'évolution globale de la radioactivité dans l'atmosphère. L'observatoire de la radioactivité dans l'atmosphère de l'Institut de radioprotection et de sûreté nucléaire (IRSN) a débuté en 1959. Actuellement les aérosols sont prélevés dans 6 stations localisées en Métropole et dans 2 stations en Outre-mer (hémisphère sud). Les concentrations de 137Cs dans les aérosols en 2002 sont de l'ordre de 0,4 μBq m-3 en métropole et 10 fois moins à Tahiti. Les activités du 7Be, de l'ordre de 3 200 μBq m-3, sont similaires en métropole et à Tahiti.

International audience; ICRP publication 73 (Radiological Protection and Safety in Medicine) introduced the concept of "diagnostic reference levels" (DRL), for medical exposures specifically. Because dose limits should not be applied for diagnostic or therapeutic irradiation, the approach to radiological protection is slightly different from that in occupational or public exposures. Reference levels, that are neither optimum levels, nor dose limits, are a tool for optimisation. DRL are set for standard procedures, for groups of patients or standard phantom and not for special exposures and individual patients. They act as a test for identifying situations where patient doses are becoming unusually high and local review of procedures and equipment is required. Within the framework of implementation of Directive 97/43, the Health Directorate entrusted its radiation protection agency (past OPRI, at present time DGSNR and IRSN) to determine the national reference dose levels in diagnostic radiology in close cooperation with relevant scientific and professional societies. The pragmatic way, recommended by European Commission, to assess DRL values is to use the third quartile values observed in wide scale surveys of typical doses for common procedures. In the absence of recent and wide-ranging data for France, in a first step, European DRL have been adopted as starting points. To go further, a campaign of patient dose measurements has been launched by a steering committee (OPRI, SFR and SFPM) to allow the actual establishment of national reference values and to prepare their periodic review in a continuous process of optimization. © 2003 EDP Sciences.

International audience; This paper presents the first reflections of the Working Group which was created by the French Society for Radiation Protection (SFRP) on key issues which will be addressed by the International Commission on Radiological Protection (ICRP) when developing new recommendations on radiological protection. Based on the analysis of the ICRP Memorandum published in the Journal of Radiological Protection in June 2001, and on the experience of the members, the following topics are being considered: - general reflections on the new system proposed by the ICRP, - considerations on individual and collective dimensions of risk management, - comparison with the management of chemical risks, - radiological protection of the environment, - dosimetric units. © 2002 EDP Sciences.

Radiological protection of the environment has been intensively discussed in recent years. Much progress has been made recently with regard to the development of models: (i) to estimate the uptake of radionuclides by flora and fauna in different habitats and ecosystems; (ii) to calculate internal and external exposures for a wide range of terrestrial and aquatic organisms; and (iii) in investigating and analyzing the effects of radiation exposures to biota. This paper gives an overview of the current status of this work. Furthermore, the current status of the integration of environmental protection into the radiation protection system is also summarized. Received: 8 November 2013; Revised: 23 December 2013; Accepted: 30 December 2013

In preparation for the preliminary safety assessment of potential radioactive waste repositories in Croatia, radiological protection criteria are defined. They are based on the international standards (ICRP, IAEA) and Croatian regulations.

Pregled objavljenih podataka i zapažanja o radioaktivnim zagađivačima u atmosferi poslije nuklearnih eksplozija ili ispuštanja radionuklida iz nuklearnih postrojenja koji izlažu ljude ionizirajućem zračenju i povećavaju mogućnost štetnog djelovanja na zdravlje. Kao posebno važni, u slučaju nezgoda nuklearnih reaktora, izdvajaju se 131^I, 134^Cs, 137^Cs, 89^Sr i 90^Sr. Osim prikaza veličina koje se primjenjuju u radiološkoj zaštiti navode se i preporuke Međunarodne komisije za ostvarenje optimalne radiološke zaštite., Review of data and observations relative to radioactive contaminants after nuclear explosions or reactor accidents exposing mankind to ionizing radiation increasing risk of detrimental health effects. In case of reactor accidents as extra-important could be set aside 131^I, 134^Cs, 137^Cs, 89^Sr and 90^Sr. Besides a survey of measures applied in radiological protection International Commission's recommendations are quoted relevant to realisation of optimal radiological protection.