Uranium mining industry views on ICRP statement on radon

In 2009, the International Commission on Radiological Protection issued a statement on radon which stated that the dose conversion factor for radon progeny would likely double, and the calculation of risk from radon should move to a dosimetric approach, rather than the longstanding epidemiological approach. Through the World Nuclear Association, whose members represent over 90% of the world's uranium production, industry has been examining this issue with a goal of offering expertise and knowledge to assist with the practical implementation of these evolutionary changes to evaluating the risk from radon progeny. Industry supports the continuing use of the most current epidemiological data as a basis for risk calculation, but believes that further examination of these results is needed to better understand the level of conservatism in the potential epidemiological-based risk models. With regard to adoption of the dosimetric approach, industry believes that further work is needed before this is a practical option. In particular, this work should include a clear demonstration of the validation of the dosimetric model which includes how smoking is handled, the establishment of a practical measurement protocol, and the collection of relevant data for modern workplaces. Industry is actively working to address the latter two items.

Hypothetical mortality risk associated with spiral tomography of the maxilla and mandible prior to endosseous implant treatment

Radiation dose delivered from the SCANORA radiography unit during the cross-sectional mode for dentotangential projections was determined. With regard to oral implantology, patient situations of an edentulous maxilla and mandible as well as a single tooth gap in regions 16 and 46 were simulated. Radiation doses were measured between 0.2 and 22.5 mGy to organs and tissues in the head and neck region when the complete maxilla or mandible was examined. When examining a single tooth gap, only 8% to 40% of that radiation dose was generally observed. Based on these results, the mortality risk was estimated according to a calculation model recommended by the Committee on the Biological Effects of Ionizing Radiations. The mortality risk ranged from 31.4 x 10(-6) for 20-year-old men to 4.8 x 10(-6) for 65-year-old women when cross-sectional imaging of the complete maxilla was performed. The values decreased by 70% when a single tooth gap in the molar region of the maxilla was radiographed. The figures for the mortality risk for examinations of the complete mandible were similar to those for the complete maxilla, but the mortality risk decreased by 80% if only a single tooth gap in the molar region of the mandible was examined. Calculations according to the International Commission on Radiological Protection carried out for comparison did not reveal the decrease of the mortality risk with age and resulted in a higher risk value in comparison to the group of 35-year old individuals in calculations according to the Committee on the Biological Effects of Ionizing Radiations.

Hypothetical mortality risk associated with spiral computed tomography of the maxilla and mandible

In the present study, dose measurements have been conducted following examination of the maxilla and mandible with spiral computed tomography (CT). The measurements were carried out with 2 phantoms, a head and neck phantom and a full body phantom. The analysis of applied thermoluminescent dosimeters yielded radiation doses for organs and tissues in the head and neck region between 0.6 and 16.7 mGy when 40 axial slices and 120 kV/165 mAs were used as exposure parameters. The effective dose was calculated as 0.58 and 0.48 mSv in the maxilla and mandible, respectively. Tested methods for dose reduction showed a significant decrease of radiation dose from 40 to 65%. Based on these results, the mortality risk was estimated according to calculation models recommended by the Committee on the Biological Effects of Ionizing Radiations and by the International Commission on Radiological Protection. Both models resulted in similar values. The mortality risk ranges from 46.2 x 10.6 for 20-year-old men to 11.2 x 10(-6) for 65-year-old women. Using 2 methods of dose reduction, the mortality risk decreased by approximately 50 to 60% to 19.1 x 10(-6) for 20-year-old men and 5.5 x 10(-6) for 65-year-old women. It can be concluded that a CT scan of the maxillofacial complex causes a considerable radiation dose when compared with conventional radiographic examinations. Therefore, a careful indication for this imaging technique and dose reduction methods should be considered in daily practice.

Dual energy versus single energy MDCT: measurement of radiation dose using adult abdominal imaging protocols

RATIONALE AND OBJECTIVES: The aim of this study was to measure the radiation dose of dual-energy and single-energy multidetector computed tomographic (CT) imaging using adult liver, renal, and aortic imaging protocols. MATERIALS AND METHODS: Dual-energy CT (DECT) imaging was performed on a conventional 64-detector CT scanner using a software upgrade (Volume Dual Energy) at tube voltages of 140 and 80 kVp (with tube currents of 385 and 675 mA, respectively), with a 0.8-second gantry revolution time in axial mode. Parameters for single-energy CT (SECT) imaging were a tube voltage of 140 kVp, a tube current of 385 mA, a 0.5-second gantry revolution time, helical mode, and pitch of 1.375:1. The volume CT dose index (CTDI(vol)) value displayed on the console for each scan was recorded. Organ doses were measured using metal oxide semiconductor field-effect transistor technology. Effective dose was calculated as the sum of 20 organ doses multiplied by a weighting factor found in International Commission on Radiological Protection Publication 60. Radiation dose saving with virtual noncontrast imaging reconstruction was also determined. RESULTS: The CTDI(vol) values were 49.4 mGy for DECT imaging and 16.2 mGy for SECT imaging. Effective dose ranged from 22.5 to 36.4 mSv for DECT imaging and from 9.4 to 13.8 mSv for SECT imaging. Virtual noncontrast imaging reconstruction reduced the total effective dose of multiphase DECT imaging by 19% to 28%. CONCLUSION: Using the current Volume Dual Energy software, radiation doses with DECT imaging were higher than those with SECT imaging. Substantial radiation dose savings are possible with DECT imaging if virtual noncontrast imaging reconstruction replaces precontrast imaging.

Childhood leukaemia risks: from unexplained findings near nuclear installations to recommendations for future research.

Recent findings related to childhood leukaemia incidence near nuclear installations have raised questions which can be answered neither by current knowledge on radiation risk nor by other established risk factors. In 2012, a workshop was organised on this topic with two objectives: (a) review of results and discussion of methodological limitations of studies near nuclear installations; (b) identification of directions for future research into the causes and pathogenesis of childhood leukaemia. The workshop gathered 42 participants from different disciplines, extending widely outside of the radiation protection field. Regarding the proximity of nuclear installations, the need for continuous surveillance of childhood leukaemia incidence was highlighted, including a better characterisation of the local population. The creation of collaborative working groups was recommended for consistency in methodologies and the possibility of combining data for future analyses. Regarding the causes of childhood leukaemia, major fields of research were discussed (environmental risk factors, genetics, infections, immunity, stem cells, experimental research). The need for multidisciplinary collaboration in developing research activities was underlined, including the prevalence of potential predisposition markers and investigating further the infectious aetiology hypothesis. Animal studies and genetic/epigenetic approaches appear of great interest. Routes for future research were pointed out.

A critical evaluation of secondary cancer risk models applied to Monte Carlo dose distributions of 2-dimensional, 3-dimensional conformal and hybrid intensity-modulated radiation therapy for breast cancer

The comparison of radiotherapy techniques regarding secondary cancer risk has yielded contradictory results possibly stemming from the many different approaches used to estimate risk. The purpose of this study was to make a comprehensive evaluation of different available risk models applied to detailed whole-body dose distributions computed by Monte Carlo for various breast radiotherapy techniques including conventional open tangents, 3D conformal wedged tangents and hybrid intensity modulated radiation therapy (IMRT). First, organ-specific linear risk models developed by the International Commission on Radiological Protection (ICRP) and the Biological Effects of Ionizing Radiation (BEIR) VII committee were applied to mean doses for remote organs only and all solid organs. Then, different general non-linear risk models were applied to the whole body dose distribution. Finally, organ-specific non-linear risk models for the lung and breast were used to assess the secondary cancer risk for these two specific organs. A total of 32 different calculated absolute risks resulted in a broad range of values (between 0.1% and 48.5%) underlying the large uncertainties in absolute risk calculation. The ratio of risk between two techniques has often been proposed as a more robust assessment of risk than the absolute risk. We found that the ratio of risk between two techniques could also vary substantially considering the different approaches to risk estimation. Sometimes the ratio of risk between two techniques would range between values smaller and larger than one, which then translates into inconsistent results on the potential higher risk of one technique compared to another. We found however that the hybrid IMRT technique resulted in a systematic reduction of risk compared to the other techniques investigated even though the magnitude of this reduction varied substantially with the different approaches investigated. Based on the epidemiological data available, a reasonable approach to risk estimation would be to use organ-specific non-linear risk models applied to the dose distributions of organs within or near the treatment fields (lungs and contralateral breast in the case of breast radiotherapy) as the majority of radiation-induced secondary cancers are found in the beam-bordering regions.

Maternal ingestion of radon-222 in drinking water and the absorbed radiation dose to the embryo

Maternal ingestion of high concentrations of radon-222 (Rn-222) in drinking during pregnancy may pose a significant radiation hazard to the developing embryo. The effects of ionizing radiation to the embryo and fetus have been the subject of research, analyses, and the development of a number of radiation dosimetric models for a variety of radionuclides. Currently, essentially all of the biokinetic and dosimetric models that have been developed by national and international radiation protection agencies and organizations recommend calculating the dose to the mother's uterus as a surrogate for estimating the dose to the embryo. Heretofore, the traditional radiation dosimetry models have neither considered the embryo a distinct and rapidly developing entity, the fact that it is implanted in the endometrial layer of the uterus, nor the physiological interchanges that take place between maternal and embryonic cells following the implantation of the blastocyst in the endometrium. The purpose of this research was to propose a new approach and mathematical model for calculating the absorbed radiation dose to the embryo by utilizing a semiclassical treatment of alpha particle decay and subsequent scattering of energy deposition in uterine and embryonic tissue. The new approach and model were compared and contrasted with the currently recommended biokinetic and dosimetric models for estimating the radiation dose to the embryo. The results obtained in this research demonstrate that the estimated absorbed dose for an embryo implanted in the endometrial layer of the uterus during the fifth week of embryonic development is greater than the estimated absorbed dose for an embryo implanted in the uterine muscle on the last day of the eighth week of gestation. This research provides compelling evidence that the recommended methodologies and dosimetric models of the Nuclear Regulatory Commission and International Commission on Radiological Protection employed for calculating the radiation dose to the embryo from maternal intakes of radionuclides, including maternal ingestion of Rn-222 in drinking water would result in an underestimation of dose. ^

¿Impact from road transport of radioactive wastes in Spain?

Transports of radioactive wastes in Spain are becoming issues of renewed interest, due to the increased mobility of these materials which can be expected after the building and operation of the planned central repository for this country in a near future. Such types of residues will be mainly of the medium and high activity classes and have raised concerns on the safety of the operations, the radiological protection of the individuals, the compliance with the legal regulations and their environmental consequences of all kind. In this study, relevant information for the assessment of radiological risk of road transport were taken into account, as the sources and destination of the radioactive transports, the amount of traveling to be done, the preferred routes and populations affected, the characterization of the residues and containers, their corresponding testing, etc. These data were supplied by different organizations fully related with these activities, like the nuclear power stations, the companies in charge of radioactive transports, the enterprises for inspection and control of the activities, etc., as well as the government institutions which are responsible for the selection and location of the storage facility and other decisions on the nuclear policies of the country. Thus, we have developed a program for computing the data in such a form that by entering the radiation levels at one meter of the transport loads and by choosing a particular displacement, the computer application is capable to calculate the corresponding radiological effects, like the global estimated impact, its relevance to the population in general or on those people living and driving near the main road routes, the doses received by the most exposed individuals (e.g. the workers for loading or driving the vehicle), or the probability of detrimental on the human health. The results of this work could be of help for a better understanding and management of these activities and their related impacts; at the same time that the generated reports of the computer application are considered of particular interest as innovative and complementary information to the current legal documentation, which is basically required for transporting radioactive wastes in the country, according with the international safety rules (like IAEA and ADR).Though main studies are still in progress, as the definite location for the Spanish storage facility has not been decided yet, preliminary results with the existing transports of residues of medium activity indicate that the radiological impact is very low in conventional operations. Nevertheless, the management of these transports is complex and laborious, making it convenient to progress further in the analysis and quantification of this kind of events, which constitutes one of the main objectives of the present study for the radioactive road mobility in Spain.

Evolução das doses no ambiente do Reator IEA-R1 e tendências com base nos resultados atuais

O Ipen/Cnen-SP possui um Reator de Pesquisa(IEA-R1) em operação desde 1957. Ele utiliza água leve como blindagem, moderador e como fluido refrigerante, o volume desta piscina é de 273m3. Até 1995 a operação do Reator era descontinua, ou seja, operava diariamente sendo desligado no final do dia, a uma potência de 2,0 MW. A partir daquele ano, após algumas modificações de segurança, o Reator passou a operar de forma continua, ou seja, de segunda-feira a quarta-feira sem ser desligado, totalizando 64 horas semanais. A potência também foi aumentando até 4,5 MW em 2012. Em virtude dessas alterações, a saber, operação contínua e do aumento da potência, as doses dos trabalhadores aumentaram e por isso foram realizados vários estudos para diminui-las. Estudos demonstraram que uma das principais limitações para operação de um reator em potência elevada, provém das radiações gama emitidas pelo sódio-24. Outros elementos como magnésio-27, Alumínio-28, Argônio-51, contribuem de forma considerável para a atividade da água da piscina. A introdução de uma camada de água quente em sua superfície, estável e isenta de elementos radioativos com 1,5m a 2m de espessura constituiria uma blindagem às radiações provenientes dos elementos radioativos dissolvidos na água. Estudos de otimização provaram que a instalação da camada quente não era necessária para o regime e potência atual de operação do Reator, pois outros procedimentos adotados eram mais eficazes. A partir desta decisão o serviço de Proteção Radiológica do Reator IEA-R1, montou um programa de avaliação das doses para certificar-se de que elas se mantinham em valores razoáveis baseados em princípios estabelecidos em normas nacionais e internacionais. O intuito deste trabalho é realizar uma análise das doses individuais dos IOE (Individuo Ocupacionalmente Expostos), considerando as mudanças no regime de operação do Reator e sugerir opções de proteção e segurança, viáveis em primeira instância, para reduzir as doses analisadas, visando se chegar aos níveis de referencia de 3 mSv/ano adotados pela instalação em apreço.

Avaliação da radioatividade natural em tintas de uso comercial no Brasil

A radioatividade natural presente em solos, rochas e materiais de construção, devida ao 40K e às séries radioativas do 232Th e 238U é a principal contribuição à exposição externa aos seres humanos. Neste trabalho, determinou-se as concentrações de atividade de 226Ra (da série do 238U), 232Th e 40K presentes em 50 amostras de tintas látex de cor branca comercializadas no Brasil, especificamente, 15 do tipo econômico, 15 do tipo standard, 20 do tipo premium e em uma amostra de dióxido de titânio. As amostras foram seladas e armazenadas por um período mínimo de 30 dias para se alcançar o equilíbrio radioativo secular nas séries do 238U e do 232Th e medidas pela técnica analítica de espectrometria gama de alta resolução. As concentrações de atividade foram calculadas utilizando-se as médias ponderadas pelas incertezas do 214Pb e 214Bi para o 226Ra e médias ponderadas pelas incertezas do 228Ac, 212Pb e 212Bi para o 232Th. A concentração de atividade do 40K foi determinada pela sua transição única de 1460,8 keV. Fatores de autoatenuação gama foram calculados e utilizados para correção da concentração de atividade das amostras com densidade maior que 1,0 g.cm-3. Os índices radiológicos equivalente em rádio (Raeq), índice de concentração de atividade (Iγ), índice de risco à exposição gama interna (Hin), o índice de risco à exposição gama externa (Hex) e a taxa de dose (D) e dose efetiva anual (Def) foram calculados a partir das concentrações de atividade do 226Ra, 232Th e 40K. As concentrações de atividade de 226Ra das tintas variaram entre valores abaixo da atividade mínima detectável e 38,7 Bq.kg-1, as de 232Th variaram entre valores abaixo da atividade mínima detectável e 101,2 Bq.kg-1 e as de 40K variaram entre valores abaixo da atividade mínima detectável e 256 Bq.kg-1. O Raeq variou entre 1,41 Bq.kg-1 e 203 Bq.kg-1, o Iγ variou entre 0,0047 e 0,720, o Hin variou entre 0,0076 e 0,653 e o Hex variou entre 0,0038 e 0,549. A taxa de dose variou de 0,170 nGy.h-1 a 21,3 nGy.h-1 e a dose efetiva anual variou entre 0,83 μSv.a-1 e 104,2 μSv.a-1. Estes resultados mostram que as concentrações de atividades das tintas utilizadas neste estudo estão abaixo dos limites recomendados por Hassan et al. para Raeq (370 Bq.kg-1), pela Comissão Européia para o Iγ (limite de 2 para materiais superficiais) e pela Organização para Cooperação Econômica e Desenvolvimento para Hin e para Hex (ambos com limite de 1), para todas as 50 amostras estudadas, mostrando assim a segurança destas tintas com relação a proteção radiológica.

Avaliação dos níveis de radiação ambiental no laboratório de tomografia por emissão de pósitrons acoplada a tomografia computadorizada, microPET/CT

O sistema microPET/CT é um importante equipamento utilizado nas pesquisas de imagem diagnóstica em pequenos animais. O radiofármaco mais usado nesta tecnologia é o fluordeoxiglicose marcado com flúor-18. Este estudo tem como objetivo efetuar o controle radiológico no laboratório de pesquisa microPET/CT do Centro de Radiofarmácia do IPEN-CNEN/SP, de forma a satisfazer tanto as normas nacionais como as recomendações internacionais. O laboratório está classificado pela equipe de radioproteção da instalação como área supervisionada, nas quais embora não seja obrigatória a adoção de medidas específicas de proteção e segurança, devem ser submetidas reavaliações regulares das condições do ambiente de trabalho. Visando assegurar a proteção radiológica dos trabalhadores diretamente envolvidos no manuseio do equipamento, realizou-se o monitoramento do local de trabalho e a avaliação do controle de dose individual. Inicialmente foi feito o monitoramento pré-operacional, isto é, o levantamento radiométrico no laboratório. Além disso, mediu-se nível de radiação externa nas instalações do laboratório e suas adjacências, por meio da colocação de nove dosímetros termoluminescentes (TL) de CaSO4:Dy, em locais previamente selecionados. Os indivíduos ocupacionalmente expostos foram avaliados mensalmente por meio do uso de dosímetros TL posicionados no tórax e por medidas de corpo inteiro, tomadas a cada seis meses. O período do estudo foi de dois anos, com início em abril de 2014. Para o controle do microPET/CT realizou-se testes de desempenho de acordo com o protocolo padrão do equipamento e em conformidade com a norma desenvolvida pela força tarefa para estudos com PET em animais Animal PET Standard Task Force. O presente estudo permitiu demonstrar que os níveis de radiação das áreas (estimativas de dose ambiente e dose efetiva), assim como a blindagem do equipamento estão adequados de acordo com os limites da exposição ocupacional. Ressalta-se a importância de se seguir rigorosamente os princípios de radioproteção, já que se trata de pesquisas com fontes radioativas não seladas.

Social and scientific issues in the acceptibility of radiation risks

Ionising radiation hazards are perhaps the most documented and regulated occupational and environmental hazard. In the radiological protection field a single expert advisory organisation has had an unusually large influence on the international standard setting process. This is the International Commission on Radiological Protection (ICRP). Two common, and opposing views, exist over the formulation of protection recommendations by the ICRP. The first, and most widely accepted, is that its recommendations are scientifically determined. The second view, is that its recommendations are politically or socially determined. Neither of these analyses adequately accounts for the complex process in which protection recommendations are formulated. A third view, provided by studies of the origins of scientific controversy, suggests that both science and social factors are important in the assessment and limitation of risk. The aim of this thesis is not simply to examine the origin of controversy. Issues of equal, if not more, importance are the resolution of controversy, the formation of consensus and the maintenance of expert authority and influence. These issues form the central focus of this thesis. The aim is to assess the process through which the ICRP formulates its radiological protection recommendations and comment on the extent that these are influenced by the affiliations of its members. This thesis concludes that the ICRP's recommendations have been shaped by a complex relationship of scientific and social considerations, in which a socio-technical commitment to nuclear energy has played a key role. The Commission has responded to new scientific data by making complex changes to its philosophy and methods of describing risk. Where reductions in numerical limits have been applied they have been accompanied by practical measures designed to limit the impact of the change and provide continuity with the old limits and flexibility in the application of the new recommendations.

Radon in Groundwater of the Northeastern Gran Canaria Aquifer

[EN]Rn has been detected in 28 groundwater samples from the northeast of Gran Canaria (Canary Islands, Spain) utilizing a closed loop system consisting of an AlphaGUARD monitor that measures radon activity concentration in the air by means of an ionization chamber, and an AquaKIT set that transfers dissolved radon in the water samples to the air within the circuit. Radon concentration in the water samples studied varies between 0.3 and 76.9 Bq/L. Spanish radiological protection regulations limit the concentration of 222Rn for drinking water to 100 Bq/L, therefore the values obtained for all the analyzed samples are below this threshold. The hydrogeological study reveals a significant correspondence between the radon activity concentration and the material characteristics of the aquifer.