Radiological Protection

A realização desta dissertação contou com vários apoios, que não poderia deixar de referir e aos quais quero expressar o meu reconhecimento e gratidão. Assim em primeiro lugar, desejo agradecer com imensa gratidão, respeito e estima ao Professor Doutor Carlos Alberto da Silva, pelo seu entusiasmo contagiante na investigação, pela partilha de saber e disponibilidade permanente com oportuno sentido crítico, às muitas sugestões e ideias que me ofereceu, à firmeza e dedicação colocados em todo o processo que conduziu à elaboração deste trabalho. Foi o apoio, amizade e perseverança do Professor Doutor Carlos Alberto da Silva que não me deixaram desistir quando surgiram os problemas, contrariedades e desânimos. O meu bem-haja por me ter aceite como orientanda a meio deste empreendimento. Agradeço reconhecidamente à Dr.ª Arminda Sustelo e suas colaboradoras Ana Neves e Dina Pereira do Centro de Documentação e Informação do Hospital Prof. Dr. Fernando Fonseca pela disponibilidade e ajuda preciosa nas várias pesquisas realizadas para escolha do tema e fundamentação do mesmo, assim como na obtenção dos muitos artigos indisponíveis nas bibliotecas portuguesas para a elaboração deste trabalho. Quero ainda deixar expresso o meu agradecimento aos Directores e Coordenadores dos locais em estudo e a todos os colegas que amavelmente colaboraram na distribuição e recolha dos questionários aos utentes dos vários locais. Aos amigos que me apoiaram e animaram nos momentos de desânimo. À amiga Paulinha Santos que sempre relembrou a importância de viver o "presente" o melhor possível. Às amigas Ana Nunes, Lisa Ribeiro, Cristina Anselmo e Rita Cabaço "Chapitô" pela enorme amizade e presença nos bons e maus momentos. Ao Francisco Alpendurada pela amizade repleta de boa disposição e forte sentido crítico. À prima Mónica Gonçalves pela amizade e companhia nos dias de estudo. À minha família, pelo apoio, carinho e incentivo que sempre deram e por acreditarem em mim.

In these times of danger of severe international conflicts with fear of the use of atomic weapons and accidents in nuclear power plants, radionuclide contamination in terrestrial ecosystems has nowadays reached a dangerous level. One of the most frequent and studied artificial radionuclide is cesium (137-Cs and 134-Cs), which is on the rise in the world. This orally ingested artificial radionuclide is a serious danger that can cause, in humans and animals, through inflammatory, carcinogenic, carcinogenic, necrotic mechanisms, functional deficiency as diabetes mellitus, cancer and congenital anomalies by DNA and mitochondrial damage. The Author reported autoradiographic and scintigraphic studies describing some, little-known, damage to organs of pancreas, salivary glands, colon, ovary and diabetes mellitus, whose incidence rate is gradually rising worldwide. But a controversy on tissues and organs damaged, by Low-Dose Radiations action, is frequently reported in medical literature.

To clarify whether medical radiation exposure, especially from head computed tomography (CT), increases the risk of brain tumours in young patients in Japan, which ranks the second highest in the world in the number of paediatric CT examinations following the US. From 2011 to 2015, we performed a case–control study of 120 brain tumour patients and 360 appendicitis patients as controls. Reasons, the number of brain and head CT scans date were available from interviews. A cumulative radiation dose to the brain was calculated as a sum of doses received from head CT scans and from conventional x-rays and estimated using a reference table derived from a literature review of published studies. We performed conditional logistic regression to assess the risk of brain tumours from brain and head CT, and from conventional head x-ray procedures. The case group received on average 1.8 CTs to the brain area and 2.2 CTs to the whole head, with a mean estimated brain dose of 32 ± 13 mGy. The odds ...

BSS Directive 2013/59 entered into force on the 6 February 2014 requiring the Member States to adopt legislation (laws, regulations and administrative provisions) in order to harmonise their national legislation with requirements of this Directive until 6 February 2018. This Directive explicitly defines "non-medical imaging exposure" as deliberate exposure of individuals for other than medical purposes. Those planned exposure situations, if justified need to be subject to the appropriate regulatory framework for optimization of protection, exemption, notification, authorisation, inspection and law enforcement in order to insure safety in operation. The most challenging part is a justification process of "non-medical imaging exposure" taking into account that regulatory radiation protection authorities have limited responsibility in decision making process. BSS Directive recommends regular periodical review of justified practices involving deliberate exposure of humans for non-medical imaging purposes taking into account new technologies available, magnitude of radiological exposure during screening and other screening objectives. Dose constrains for different categories of exposures (public exposure, occupational exposure) depending on particular application, should be established and used in the optimisation of protection. In addition, appropriate regulatory control should be established and enforced as well as the stakeholder dialoge and the provision of information responsive to stakeholders concerns.

To improve the estimation of external gamma irradiation from deposited radioactivity in urban environments a model of a modern office or residential building with glass facades was set up with eleven different building heights. Kerma conversion factors for the floors inside the building from contamination on different types of surfaces were determined by using the Monte Carlo code MCNP6 for the primary gamma energies 0.3 MeV, 0.662 MeV and 3.0 MeV and for three different environmental scenarios. The kerma conversion factors were expressed as formulas for each possible deposition area for contaminants. The importance of the determined factors was shown by comparing them to previously generally used factors for multistorey house blocks.

In the recovery phase after a radioactive release incident, it is important to be able to focus decontamination operations on the areas that contribute most to the radiation dose. Monte Carlo simulations were applied to determine the shielding effect of a building against radiation from various directions, also giving information on the dose contributions at various locations inside the building from specific areas outside. The concept of the isodose was developed to optimize decontamination activities, and was applied as isodose lines to define the smallest areas that lead to a certain dose reduction through decontamination of areas surrounding the building. The shape and position of the isodose lines depend on the geometry of the building, the wall thickness and material, and the observation point inside the building. Calculations have been made with a surface resolution of 1 m 2 for four observation points in a modular building, assuming depositions of 137 Cs and 60 Co on the ground surface and on the roof, as well as 1 cm below the ground surface to represent ground penetration. For example, a ten times as larger area would have to be decontaminated to increase the dose reduction from 10 to 30 %, if it is assumed that all the contamination is located at a depth of 1 cm.

Radon is an inert gas that can transfer from rock, soil and accumulate in enclosed areas such as dwellings and mines. It is reported that exposure of miners to radon gas and its progenies can cause lung cancer. Therefore, monitoring of radon in underground mines is important to assess the health hazards to the miners. Keeping in view these facts measurement of radon in soil collected from chromite mines of Khanozai and Muslim Bagh, Balochistan was carried out using CR-39 track detector. The concentration of radon in soil collected from chromite mines of Khanozai was ranged 0.67 ± 0.06 to 1.94 ± 0.10 kBq/m 3 with an average of 1.23 ± 0.69 kBq/m 3 while in case of Muslim Bagh its values ranged from 0.49 ± 0.071 to 2.12 ± 0.11 kBq/m 3 with an average of 1.26 ± 0.08 kBq/m 3 . The average values of radon exhalation rate were 9.95 ± 0.6 and 10.20 ± 0.68 Bq/m 2 h from soil collected from chromite mines of Khanozai and Muslim Bagh, respectively. In addition to radon concentration and exhalation rate, radium activity ( 226 Ra) were also calculated. Average values of radium activity for Khanozai and Muslim Bagh chromite mines were found 3.02 and 3.09 Bq/kg, respectively. The values obtained for radon exhalation rate were found below the average value of 57.60 Bq/m 2 h recommended by UNSCEAR. Therefore, it is concluded that the mines understudy are safe from health hazards related to radon gas.

The relationship of soil gas radon Rn 222 and indoor radon was studied within the Quaternary fluvial sediments of the Czech Republic. The processing of data selection from the radon database of the Czech Geological Survey and indoor radon data (database of the National Radiation Protection institute) has proved the concentration dependence of radon in Quaternary fluvial sediments on deeper bedrock. The ArcGIS processing was accompanied by the field verification in five profiles, intersecting the granitoid Central Bohemian Plutonic Complex and its rim rock types. Both theoretical and experimental results show dependence of soil gas radon and indoor radon concentrations in Quaternary fluvial sediments on deeper geological basement, thus leading to the conclusion that the lateral transport of Quaternary sediments does not play such a dominant role in radon concentrations, as was thought previously. This fact will enable to determine precisely the radon index of Quaternary sediments (in the Czech radon mapping classified as an intermediate index) into three categories according to the lithology of their geological basement.

In this paper we present an atmospheric dispersion scenario for a proposed nuclear power plant in Pakistan involving the hypothetical accidental release of radionuclides. For this, a concept involving a Lagrangian stochastic particle model (LSPM) coupled with an Eulerian regional atmospheric modelling system (RAMS) is used. The atmospheric turbulent dispersion of radionuclides (represented by non-buoyant particles/neutral traces) in the LSPM is modelled by applying non-homogeneous turbulence conditions. The mean wind velocities governed by the topography of the region and the surface fluxes of momentum and heat are calculated by the RAMS code. A moving least squares (MLS) technique is introduced to calculate the concentration of radionuclides at ground level. The numerically calculated vertical profiles of wind velocity and temperature are compared with observed data. The results obtained demonstrate that in regions of complex terrain it is not sufficient to model the atmospheric dispersion of particles using a straight-line Gaussian plume model, and that by utilising a Lagrangian stochastic particle model and regional atmospheric modelling system a much more realistic estimation of the dispersion in such a hypothetical scenario was ascertained. The particle dispersion results for a 12 h ground release show that a triangular area of about 400 km 2 situated in the north-west quadrant of release is under radiological threat. The particle distribution shows that the use of a Gaussian plume model (GPM) in such situations will yield quite misleading results.

Background and purpose. The potential for unintended and adverse radiation exposure in radiotherapy (RT) is real and should be studied because RT is a highly complex, multistep process, which requires input from numerous individuals from different areas and steps of the RT workflow. The ‘Incident’ (I) is an event the consequence of which is not negligible from the point of view of protection or safety. A ‘near miss’ (NM) is defined as an event that is highly likely to happen but did not occur. The purpose of this work is to show that through systematic reporting and analysis of these adverse events, their occurrence can be reduced. Materials and methods. Staff were trained to report every type of unintended and adverse radiation exposure and to provide a full description of it. Results. By 2018, 110 worksheets had been collected, with an average of 6.1 adverse events per year (with 780 patients treated per year, meaning an average incident rate of 0.78%). In 2001–2009, 37 events wer...

The purpose of this investigation was to analyse incidents discovered in our radiation therapy department by means of human factor analysis and classification system (HFAC S). We adapted the original framework of the HFAC S and apply it to the analysis of incidents discovered in our radiotherapy department during a five-year period. Results showed that recurrent causal factors of incidents were attention failures and distracted/overconfidence behaviour as well as loss of situational awareness and mental fatigue. In our radiation therapy department the HFAC S allowed to highlight recurrent errors causal factors. Consequently we defined corrections factors for operators behaviour and implemented an operational protocol which improve operators attitude.

In this study, which is the first of its kind in the gulf region, eye doses of interventional cardiologists and nurses were measured using active dosimeters for left and right eyes, in 60 percutaneous coronary interventions in three main hospitals in Kuwait. The dose given in terms of H p (0.07) per procedure when ceiling suspended screens were used by main operators ranged from 18.5 to 30.3 µSv for the left eye and from 12.6 to 23.6 µSv for the right eye. Taking into account typical staff workload, the results show that the dose limit of 20 mSv/year to the eyes can be exceeded for interventional cardiologists in some situations, which demonstrates the need of using additional effective radiation protection tools, e.g. protective eye spectacles, in addition to the regular and proper use of ceiling suspended screens. With indications of increase in workload, the need for availability of a dedicated active dosimeter for the regular monitoring of eye doses is emphasized.

Con la presente investigación tratamos de contribuir al conocimiento de la comunidad educativa acerca de los riesgos que pueden ocurrir dentro de un aula, nos referimos a la polución por el radón que es peligroso en concentraciones elevadas: y estos riesgos dependen de varios factores como la ventilación, características geológicas y concentración de uranio y radio en el piso y paredes. El trabajo también incluye la determinación de la concentración de radón en dos instituciones educativas próximas al yacimiento uranífero más importante del Perú.

The increasing number of industrial radiographers and their considerable occupational exposure has been one of the main concerns of the Iran Nuclear Regulatory Authority (INRA) in recent years. In 2002, a quantitative system of evaluating the safety performance of licensees and a complementary enforcement system was introduced by the National Radiation Protection Department (NRPD). Each parameter of the practice is given a weighting factor according to its importance to safety. Assessment of the licensees is done quantitatively by summing up their scores using prepared tables. Implementing this system of evaluation showed a considerable decrease in deficiencies in the various centres. Tables are updated regularly as a result of findings during the inspections. This system is used in addition to enforcement to promote safety performance and to increase the culture of safety in industrial radiography. affiliations

The current paper presents the methods and design of two case-control studies among Chernobyl liquidators -one of leukaemia and non-Hodgkin lymphoma, the other of thyroid cancer risk -carried out in Belarus, Estonia, Latvia, Lithuania and Russia. The specific objective of these studies is to estimate the radiation induced risk of these diseases among liquidators of the Chernobyl accident, and, in particular, to study the effect of exposure protraction and radiation type on the risk of radiation induced cancer in the low-to-medium-(0-500 mSv) radiation dose range.

Objetivo: Analizar el marco normativo de radioprotección en Chile, su alineación con estándares internacionales y los desafíos para su actualización frente a nuevas tecnologías y escenarios clínicos. Metodología: Revisión documental de la Ley N°16.744, Decretos Supremos N°3 y N°133, normativas del OIEA (GSR Part 3) y documentos técnicos del ISP (Nota Técnica N°34). Se contrastaron límites de dosis, definiciones de trabajadores expuestos y mecanismos de fiscalización con recomendaciones internacionales (ICRP/OIEA). Resultados: Chile cuenta con un marco regulatorio robusto, pero persisten discrepancias en la definición de Trabajadores Ocupacionalmente Expuestos (TOE), límites de dosis (ej. cristalino: 300 mSv/año vs. 20 mSv/año del OIEA) y fiscalización en contextos emergentes (quirófanos con fluoroscopía, residuos radiactivos). Conclusión: Se requieren actualizaciones normativas para incluir a todo personal en riesgo, armonizar límites de dosis con estándares globales y fortalecer la cultura de seguridad radiológica bajo el principio ALARA. Palabras Clave: Radioprotección, normativa chilena, trabajadores expuestos, límites de dosis, OIEA, principio ALARA. Los autores declaran no tener conflictos de interés relevantes para este trabajo. Este documento no recibió financiamiento externo específico.

A correction is required in table 8. The final two columns were mis-labelled as intake figures via inhalation (I inh ). However, for each individual (A, B, C, D and E), two successive rows were given in this table. The first relates to PM 100 and the second to PM 10 . The aerosol inhaled as PM 100 is taken to be transferred to the gastrointestinal tract and absorbed from there. This line therefore relates to intake via ingestion (I ing ) and not I inh . In the case of PM 10 , uptake is taken to be primarily from the respiratory tract, so these lines do correctly relate to I inh . I inh is therefore replaced by I with a note added at the bottom of the table specifying that intake figures via ingestion and inhalation were calculated from PM 10 and PM 100 data, respectively. The correct version is as follows.

Radiological exposures due to naturally occurring radioactive material (NORM) can occur during a wide range of work-related activities in the mineral processing and chemical industries. However, evaluation of such exposures in industrial settings remains a difficult exercise owing inter alia to the large number of personnel, operations and plants affected; assumptions that often have to be made concerning the actual duration and frequency of exposures; the complex chemistry and radioactive disequilibria involved and typically, the paucity of historical data. In our study, the challenges associated with assessing chronic exposure to fugitive dust enriched in (210)Pb and (210)Po and the determination of the associated internal dose by inhalation and ingestion are described by reference to a case study undertaken at an iron ore sintering plant between June 2013 and July 2015. The applicability of default dose coefficients and biokinetic models provided by the International Commission f...

In some areas of Estonia, groundwater contains a significant number of natural radionuclides, especially radium isotopes, which may cause radiation protection concern depending on the geological structure of the aquifer. Indeed, the parametric value of 0.1 mSv y⁻¹ for the total indicative dose established by European Directive 98/83/EC, adopted as a limit value in Estonian national legislation, is often exceeded. A Twinning Project between Estonia and Italy was carried out within the framework of the Estonian Transition Facility Programme, sponsored by the European Union. Its aims were to assess the radiological situation of Estonian groundwater and related health consequences. The first step was a study of Estonian aqueducts and the population served by them, and a thorough analysis of the radiological database for drinking water, from which the relevant effective doses for the population were obtained. Particular attention was devoted to doses to children and infants. Correlations...

This study has established local diagnostic reference levels (LDRLs). Dose report and scan parameters for the head was assessed during seven months at the three study centres. Data on CT Dose index (CTDIw) and dose length product (DLP) available and achieved on CT scanner control console was recorded for a minimum of 10 average-sized patients for each facility to establish a local Diagnostic reference level (LDRLs) and radiation dose optimization Data was collected using a purposive sampling technique, from 131 adult patients weighing 70±3kg) from Philip brilliance, Toshiba Alexion and General Electric (GE) CT scanners for this study. The collected data were analyzed using SPPSS version (20) statistical software. Third quartile values of the estimated LDRLs for CTDIw and DLP was determined as 49.8 mGy and 9639 mGy. The mean CTDIw obtained are lower to the reported data from the European Commission of 60mGy. The mean DLP are comparably lower than all the reported value from the Europ...

La fabrication de verre plombé n'a pas encore été développée en Colombie, ce qui entraîne des lacunes dans la recherche d'améliorations des composants pour la protection radiologique. Le Groupe de Physique Médicale de l'Université Nationale de Colombie a donc initié une étude en vue de développer différents échantillons de verre plombé qui soient adaptés à une utilisation comme blindage contre les rayonnements ionisants. Les caractéristiques optimales ont été trouvées pour une concentration de 50 % d'oxyde de plomb (PbO) dans un verre de plomb-silicate. Un pourcentage de PbO supérieur entraîne des difficultés techniques et une diminution de la clarté du verre. Pour cette fraction molaire nous avons trouvé un coefficient d'absorption linéaire de 0,35 cm -1 , c'est-à-dire que pour une énergie de 662 keV un centimètre de ce verre correspond à 3,0 mm de plomb pur ; avec cette même énergie la couche de demi-atténuation (CDA) de l'échantillon est égale à celle du ciment ferreux utilisé couramment dans les blindages radiologiques. Enfin il a également été observé que l'application d'une couche d'air de 1 cm entre les lames de verre diminue la transmission des photons jusqu'à 20 % pour le verre contenant 40 % de plomb.

Objectives: To assess radiation exposure-related work history and risk of cataract and cataract surgery among radiologic technologists assisting with fluoroscopically-guided interventional procedures (FGIP). Methods: This retrospective study included 35,751 radiologic technologists who reported being cataract-free at baseline (1994-1998) and completed a follow-up questionnaire (2013-2014). Frequencies of assisting with 21 types of FGIP and use of radiation protection equipment during five time periods (before

Gostaria de poder dirigir um agradecimento mais personalizado a todos os que, direta ou indiretamente, trouxeram um contributo positivo para a realização desta tese. Na impossibilidade natural de o fazer a todos, condiciono-me a fazê-lo aos que mais de perto me acompanharam. Ao Prof. Doutor António Barata Tavares, orientador e companheiro nesta grande caminhada. Um agradecimento muito especial pela, orientação científica, conhecimento, estímulo, saber, permanente disponibilidade e confiança que em mim depositou. Ao Prof. Doutor Pedro Vaz, um especial agradecimento pela partilha do seu vasto conhecimento científico em dosimetria e disponibilização de recurso, que permitiram a concretização dos objetivos traçados, tendo sido um companheiro e referencial neste percurso. Ao Prof. Doutor Florentino Serranheira pelo forte contributo na coorientação deste trabalho. À Prof.ª Doutora Carla Nunes agradeço os seus saberes e apoio concedido na análise estatística.

The technological and scientific advances in the field of medicine has encouraged the application of ionizing radiation with a considerable positive contribution in the areas of Nuclear Medicine, Radiology, Radiotherapy and other specialties related to medical intervention like Cardiology. The Health Organizations that arise the risk of occupational exposure to ionizing radiation and is their responsibility to ensure monitoring, according the law. To ensure the monitoring of controlled doses of exposure, the exposed works use an individual dosimeter and undergo medical supervision. The individual dosimetry readings of health-care professionals, is sometimes questionable for themselves, arising distrust and uncertainty about the values measured. Objective: evaluate the degree of confidence of health professionals, exposed to radiation, on the system of individual monitoring. Methods: Observational study of cross-type analysis by questionnaire. Sample of 190 of technologists of Cardio...

A Comissão Europeia irá lançar, num futuro próximo, uma nova directiva relativa à protecção radiológica - Basic Safety Standards – a qual irá substituir, num único documento, os actualmente existentes. Durante as últimas três décadas, em Portugal, a protecção radiológica contra radiações ionizantes tem sido regulada segundo cinco directivas, publicadas entre 1989 e 2003. Têm sido relatados vários incidentes ocorridos em ambiente clínico, nomeadamente naqueles que operam com radiação ionizante, pois na maioria dos casos, as regras, boas práticas e infra-estruturas não estão adequadas para esta finalidade. As questões ligadas com esta temática estão agora em análise e sob discussão pública. É, contudo, importante entender os desafios e requisitos da nova directiva para melhorar e assegurar a excelência dos resultados nas organizações de cuidados de saúde. Este novo documento reúne as abordagens da International Commission on Radiation Protection (ICRP), International Atomic Energy Age...

Introdução: O binómio de exposição profissional e repercussões negativas para a saúde e a segurança dos trabalhadores expostos, desde que não controlado, pode gerar graves problemas organizacionais, dos quais se pode salientar os custos financeiros inerentes: às despesas de saúde para com estes profissionais; a substituição destes profissionais no seu posto de trabalho; eventuais baixas da produção, associadas ao período de integração do novo profissional a contratar. Toda esta envolvente de custos financeiros associados e a responsabilidade legal que as Organizações de Saúde (OSs) têm, acresce às OSs em vigiar a saúde dos seus profissionais tendo como bases a sua responsabilidade civil e a legislação vigente. No entanto não basta, por parte das OSs, facultar todos os meios para que os seus profissionais expostos, neste caso a radiações ionizantes, estejam devidamente monitorizados com dosímetros individuais ou de área, mas também assegurar que esses profissionais os utilizam correctamente e têm formação em PSR. Objectivo: avaliar a vigilância dos profissionais de saúde, expostos a radiações ionizantes, pelas Organizações de Saúde. Material e Métodos: Estudo observacional do tipo analítico-transversal, por questionário. Amostra de 190 Técnicos de Diagnóstico e Terapêutica (TDT) de Cardiopneumologia, Medicina Nuclear, Radiologia, Radioterapia, expostos a radiações ionizantes, que exercem a sua actividade profissional em hospitais do concelho de Lisboa. Resultados: 40,2% das OSs apresentam plano de vigilância médica. Do grupo que apresenta um plano de vigilância médica anualmente, segundo o que está legislado, apenas 25,2% das OSs públicas e 30,6% das OSs privadas apresentam plano anual. 78,5% da amostra é notificada das suas leituras dosimétricas. A margem de erro associado ao estudo é de 5,09%, com um nível de confiança de 95%. Discussão: Com base na análise de dados, os TDTs referem que mais de dois terços das OSs não têm plano de vigilância médica. Das unidades hospitalares que apresentam esse plano a percentagem é superior nas unidades hospitalares privadas. Constatou-se, também que existe, no meio interno de cada unidade hospitalar uma grande falta de homogeneidade das respostas dos profissionais, isto é, na mesma unidade hospitalar existe uma grande discrepância entre os profissionais que referem a existência e inexistência desse plano de vigilância médica. Do grupo que existir um plano de vigilância médica na sua OS, foi avaliar-se se a periodicidade estava conforme o legislado e verificou-se que em mais de metade das OSs, púbicas e privadas, o plano é anual. Não se verificou uma associação estatisticamente significativa entre o tipo de OS e a existência de plano de vigilância médica. Conclusões: Propõem-se assim, que as entidades reguladoras desenvolvendo estratégias mais próactivas na fiscalização das OSs e dos profissionais, para o cumprimento do legislado e que as OSs desenvolvam ferramentas de comunicação entre os profissionais.

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.

In reviewing a video series that they created for the website of the Health Physics Society (HPS), past leaders of the Health Physics Society have treated as authoritative and trustworthy the scientific misconduct theories of University of Massachusetts Professor Edward Calabrese. No mention is made of detailed critiques of Calabrese's work. I show that Calabrese's historical work as presented by HPS's authors is unreliable because it overlooks key historical text and key statistical concepts about the limits of an early atomic bomb genetics study. When these errors are corrected, claims of scientific misconduct on the part of historical figures evaporate. Claims of threshold behavior in early radiation genetic experiments are wrong for atomic bomb data. Calabrese's unique claims about thresholds in early animal genetic data are not credible for human cancer, given the doses at which they were carried out (>30 R). Recent epidemiological studies of both acute and protracted exposure in humans fail to show dose-rate effects or a dose threshold above 30 R. Such results from human data should be more relevant for most regulators and review committees than Calabrese's claims about old data on animals. Disclaimers, errata, and links to critiques should be added to the HPS webpage hosting the 22-part video series. Failure to do so can cause damage to reputations and historical accuracy because it erroneously validates Calabrese's inflammatory claims of scientific misconduct against past scientists, including three Nobel Prize winners, members of the NAS, and presidents of the AAAS.

que em tão tenra idade, é portadora de uma força, felicidade e serenidade. Pelo tempo que não te dei, para hoje escrever aqui…. Ao meu marido, por seres parte de mim! Aos meus pais, pelo seu amor, disponibilidade e por fazerem de mim a pessoa que sou hoje….espero um dia ser para a Alice aquilo que vocês são para mim! Ao meu irmão, que mesmo longe, está sempre por perto. À minha avó, a matriarca da família, a visão da vida humana, da experiência de vida, dos meus! Aos meus colegas de trabalho, sem a vossa colaboração, este trabalho não teria sido possível. À Professora Carina, pela sua simpatia e disponibilidade.

Caves' atmosphere is a special environment where it is necessary taking into account some of its characteristics to assess the radon dose. Equilibrium factor between radon and its progeny and, especially its unattached fraction are key parameters in radon dose evaluation. In order to consider the specific features of the Altamira Cave atmosphere, the radon and particles concentration has been measured. The mean annual radon concentration inside the cave over the period 2013-2019 is around 3500 Bq m-3 with an standard deviation of 1833 Bq m-3 and exhibits seasonal variations. This value surpass all international (WHO, IAEA, ICRP) upper action and reference levels (occupational and non occupational). Dose rate levels expressed in µSv h-1 were estimated for four different equilibrium scenarios between radon and its progenies 218 Po, 214 Pb, 214 Bi and 214 Po. Newest dose conversion factors (DCF) have been used and the contribution made to the dose by the unattached fraction of radon progeny has been also assessed from the particle concentration. The results suggest that the mean annual dose levels show variations of up to 500% due to the range of the equilibrium factors (F), and the unattached fraction (fp) considered in this study. Given the high radon concentrations usually found in show caves, the best way to reduce this variability and its associated uncertainty in dose assessment is to conduct specific studies aimed to determine both the equilibrium factor and the unattached fraction of progenies.

The results of the Information System on Occupational Exposure in Medicine, Industry and Research (ISEMIR) worldwide survey on current occupational radiation protection in industrial radiography are being used to develop the ISEMIR international database and a "road map". The "road map" is a software tool that will enable NDT companies to assess their own performance in radiation protection against accepted practice. A NDT company would answer the questions in the road map, based on current practice in their company. The response to each question is then scored by comparing it with a measure of good practice. Different weightings are applied to questions, depending on their relative importance. The scores are summed and the results presented to the user, including a graphical schematic that gives a quick visual overview of how the NDT company compares with current good practice. Areas that have been identified as being below par could then be addressed by the NDT company to improve occupational radiation protection in their facility. The road map tool will be available on the ISEMIR pages of the IAEA's ORPNET website at: http://www-ns.iaea.org/tech-areas/communication-networks/norp/isemir-web.htm The ISEMIR international database is being developed to provide a tool that can be used by end-users to improve their implementation of optimization in occupational radiation protection in particular targeted areas, including industrial radiography. For each participating NDT company, the database will contain anonymized data on individual industrial radiographers, including their occupational doses, radiographic workloads, level of NDT training, radiation protection training, sources used, percentage of site radiography, use of collimators and survey meters, and number of incidents. The metric for assessing optimization of radiation protection will be occupational dose per radiographic exposure. NDT facilities will be able to benchmark their own facility and individual radiographers' performances against global or regional data. The industrial radiography section of the database will also have a module devoted to incidentsaccidents, near misses and deviations from normaland will provide information, examples and analyses that should lead to a reduction in the occurrence of incidents in industrial radiography. Once developed, NDT facilities all around the world will be encouraged to actively participate in the database to enable it to become a viable tool for implementing optimization of occupational radiation protection.

A Working Group on Industrial Radiography developed and distributed three questionnaires to gain insight into occupational radiation protection in industrial radiography world-wide – one addressed to individual industrial radiographers, another to non-destructive testing (NDT) companies, and a third to national or state regulatory bodies. The questionnaires were distributed widely over a one year period. Responses were received from 432 industrial radiographers from 31 countries, 95 NDT companies from 29 countries, and 59 regulatory bodies. The questionnaires addressed qualification and training of radiographers in radiation protection, learning from incidents, systems and procedures in place for safe operation, emergency preparedness and response, and individual monitoring. In this paper some of the main findings are discussed.

The results of the Information System on Occupational Exposure in Medicine, Industry and Research (ISEMIR) worldwide survey on current occupational radiation protection in industrial radiography are being used to develop the ISEMIR international database and a “road map”. The “road map” is a software tool that will enable NDT companies to assess their own performance in radiation protection against accepted practice. A NDT company would answer the questions in the road map, based on current practice in their company. The response to each question is then scored by comparing it with a measure of good practice. Different weightings are applied to questions, depending on their relative importance. The scores are summed and the results presented to the user, including a graphical schematic that gives a quick visual overview of how the NDT company compares with current good practice. Areas that have been identified as being below par could then be addressed by the NDT company to improve ...

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El Centro de Protección e Higiene de las Radiaciones fue fundado en 1985 para sustentar la aplicación segura de las tecnologías nucleares en Cuba. En la actualidad la institución es considerada como una referencia nacional y regional en materia de seguridad radiológica, gracias a una sólida estrategia institucional que aporta de manera sostenida soluciones a problemas prioritarios del país. Este trabajo presenta una reseña de los principales resultados del centro hasta la fecha.

The presence of uranium glass 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 from the glass objects. In general, the determined dose rates did not raise any concern as long as some precautions were taken. Radon (222 Rn), usually the most important contributor for the overall natural dose exposure resulting from radium (226 Ra) decay in the uranium natural 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.

Working Group (WG) 6 "Computational Dosimetry" of the European Radiation Dosimetry Group (EURADOS) promotes good practice in the application of computational methods for radiation dosimetry in radiation protection and the medical use of ionizing radiation. Its cross-sectional activities within the association cover a large range of current topics in radiation dosimetry, including more fundamental studies of radiation effects in complex systems. In addition, WG 6 also performs scientific research and development as well as knowledge transfer activities, such as training courses. Monte Carlo techniques, including the use of anthropomorphic and other numerical phantoms based on voxelized geometrical models, have a strong part in the activities pursued in WG 6. However, other aspects and techniques, such as neutron spectra unfolding, play an important role as well. A number of intercomparison exercises have been carried out in the past to provide information on the accuracy with which computational methods are applied and whether best practice is being followed. Within the exercises that are still ongoing, the focus has changed towards assessing the uncertainty that can be achieved with these computational methods. Furthermore, the future strategy of WG 6 also includes an extension of the scope toward experimental benchmark activities and evaluation of cross-sections and algorithms, with the vision of establishing a gold standard for Monte Carlo methods used in medical and radiobiological applications.

h i g h l i g h t s Strength of Concretes with EAF slags is higher than that of conventional concrete. Small attenuation difference between concretes with EAF slags and those with barite. Attenuation of concretes with EAF slags is valid for radiological protection. The friability of barite compromises the mechanical properties of concrete.

Purpose: Definition of new national diagnostic reference levels (DRLs) for volume computed tomography dose index (CTDIvol) and dose length product (DLP) for neuropaediatric CT examinations depending on the medical indication. Methods: Paediatric cranial CT data sets acquired between January and December were retrospectively collected between July 2016 and March 2017 from the eight largest university and cantonal hospitals that perform most of the neuro-paediatric CTs in Switzerland. A consensus review of CTDIvol and DLP was undertaken for the three defined anatomical regions: brain, facial bone and petrous bone; each with and without contrast medium application. All indications for cranial CT imaging in paediatrics were assigned to one of these three regions. Descriptive statistical analysis of the distribution of the median values for CTDIvol and DLP yielded minimum, maximum, 25th percentile (1st quartile), median (2nd quartile) and 75th percentile (3rd quartile). New DRLs for neuro-paediatric CT examinations in Switzerland were based on the 75th percentiles of the distributions of the median values of all eight centres. Where appropriate, values were rounded such that the DRLs increase or at least remain constant as the age of the patient increases. Results: Our results revealed DRLs for CTDIvol and DLP up to 20% lower than the DRLs used so far in Switzerland and elsewhere in Europe. Conclusions: This study provides Swiss neuro-paediatric CT DRL values to establish optimum conditions for paediatric cranial CT examinations. Periodic national updates of DRLs, following international comparisons, are essential.