137Cs Inventory in sedimentary columns from continental shelf of São Paulo State

137Cs is an artificial radioactive isotope produced by 235U fission. This radionuclide has a high fission yield and a half-life of 30 years. It has been detected in the environment since 1945 and its principal contamination source has been nuclear tests in the atmosphere. There are other sources of 137Cs contamination in the environment, such as: release from nuclear and reprocessing plants, radioactive dumping and nuclear accidents (Chernobyl, for example). This paper presents an inventory of 137Cs on the Continental Shelf of São Paulo State, a region located between Cabo de Santa Marta Grande (Santa Catarina state) and Cabo Frio (Rio de Janeiro state). In this area, 9 cores were collected by the Instituto Oceanográfico da Universidade de São Paulo (São Paulo University Institute of Oceanography). The cores were sliced at every 2 cm; sub-samples were lyophilized, grinded and stored in plastic containers. 137Cs was determined by 661 keV photopeak using a gamma spectrometry detector (Ge hyperpure). The analysis was performed by efficiency and background in different counting times. 137Cs concentration activities varied from 0.3 to 3.6 Bq kg-1 with a mean value of 1.2±0.6 Bq kg-1. The inventory of 137Cs in this area was 13±7 Bq m-2. Values obtained are in agreement with the Southern Hemisphere, a region contaminated by atmospheric fallout due to past nuclear explosions.

Natural radionuclides distribution in the shelf and upper slope off southeast Brazil

In recent decades, Oceanography has been using a variety of radionuclides as tracers to understand the ocean dynamic processes, handling and disposal of sediments of seabed. In this context, the determination of natural radionuclides distributions (238U, 232Th and 40K) has been carried out with sediments samples from the shelf and upper slope off Southeast Brazil using a gamma spectrometry technique. The samples were sliced into strata of 2 cm, dried, ground and properly packed to be analysed. The concentration of activities was performed in a hyperpure Ge detector with a resolution of 1,9 keV for the peak of 1332,3 keV of 60Co, model GEM50P by EGG&ORTEC. The study area is located between latitudes 28°40'S and 23°00'S and extends from Cabo Frio (RJ) to Cabo de Santa Marta Grande (SC). The activity concentrations varied from 0,6 to 52,8 BqKg-1 for 238U, from 1,6 to 50,9BqKg-1 for 232Th and from 65,4 to 873,3 BqKg-1 for 40K. From these results it is possible to establish a correlation between the depositional area dynamics and the samples size parameters

Caracterización computacional de un detector de germanio hiperpuro de rango extendido (HPGe- XtRa) con simulación Montecarlo y optimización con un algoritmo evolutivo

Máster Universitario en Sistemas Inteligentes y Aplicaciones Numéricas en Ingeniería (SIANI)

Diffusion of HTO, Br-, I-, Cs+, Sr-85(2+) and Co-60(2+) in a clay formation: Results and modelling from an in situ experiment in Opalinus Clay

The migration of radioactive and chemical contaminants in clay materials and argillaceous host rocks is characterised by diffusion and retention processes. Valuable information on such processes can be gained by combining diffusion studies at laboratory scale with field migration tests. In this work, the outcome of a multi-tracer in situ migration test performed in the Opalinus Clay formation in the Mont Terri underground rock laboratory (Switzerland) is presented. Thus, 1.16 x 10(5) Bq/L of HTO, 3.96 x 10(3) Bq/L of Sr-85, 6.29 x 10(2) Bq/L of Co-60, 2.01 x 10(-3) mol/L Cs, 9.10 x 10(-4) mol/L I and 1.04 x 10(-3) mol/L Br were injected into the borehole. The decrease of the radioisotope concentrations in the borehole was monitored using in situ gamma-spectrometry. The other tracers were analyzed with state-of-the-art laboratory procedures after sampling of small water aliquots from the reservoir. The diffusion experiment was carried out over a period of one year after which the interval section was overcored and analyzed. Based on the experimental data from the tracer evolution in the borehole and the tracer profiles in the rock, the diffusion of tracers was modelled with the numerical code CRUNCH. The results obtained for HTO (H-3), I- and Br- confirm previous lab and in situ diffusion data. Anionic fluxes into the formation were smaller compared to HTO because of anion exclusion effects. The migration of the cations Sr-85(2+), Cs+ and Co-60(2+) was found to be governed by both diffusion and sorption processes. For Sr-85(2+), the slightly higher diffusivity relative to HTO and the low sorption value are consistent with laboratory diffusion measurements on small-scale samples. In the case of Cs+, the numerically deduced high diffusivity and the Freundlich-type sorption behaviour is also supported by ongoing laboratory data. For Co, no laboratory diffusion data were yet available for comparison; however, the modelled data suggests that Co-60(2+) sorption was weaker than would be expected from available batch sorption data. Overall, the results demonstrate the feasibility of the experimental setup for obtaining high-quality diffusion data for conservative and sorbing tracers. (C) 2007 Elsevier Ltd. All rights reserved.

Physical properties, pore water geochemistry, 210Pb-dating of sediment cores GeoB16426-1, GeoB16427-1, GeoB16429-1

We present differential bathymetry and sediment core data from the Japan Trench, sampled after the 2011 Tohoku-Oki (offshore Japan) earthquake to document that prominent bathymetric and structural changes along the trench axis relate to a large (~27.7 km**2) slump in the trench. Transient geochemical signals in the slump deposit and analysis of diffusive re-equilibration of disturbed SO4**2- profiles over time constrain the triggering of the slump to the 2011 earthquake. We propose a causal link between earthquake slip to the trench and rotational slumping above a subducting horst structure. We conclude that the earthquake-triggered slump is a leading agent for accretion of trench sediments into the forearc and hypothesize that forward growth of the prism and seaward advance of the deformation front by more than 2 km can occur, episodically, during a single-event, large mega-thrust earthquake.

Diseño y evaluación de un procedimiento on-line para la biorremediación de aguas radiactivas en centrales nucleares

Recientemente se ha demostrado la existencia de microorganismos en las piscinas de almacenamiento de combustible nuclear gastado en las centrales nucleares utilizando técnicas convencionales de cultivo en el laboratorio. Estudios posteriores han puesto de manifiesto que los microorganismos presentes eran capaces de colonizar las paredes de acero inoxidable de las piscinas formando biopelículas. Adicionalmente se ha observado la capacidad de estas biopelículas de retener radionúclidos, lo que hace pensar en la posibilidad de utilizarlas en la descontaminación de las aguas radiactivas de las piscinas. En la presente tesis se plantea conocer más profundamente la biodiversidad microbiana de las biopelículas utilizando técnicas de biología molecular como la clonación, además de desarrollar un sistema de descontaminación a escala piloto con el objetivo de valorar si el proceso podría resultar escalable a nivel industrial. Para ello se diseñaron y fabricaron dos biorreactores en acero inoxidable compatibles con las condiciones específicas de seguridad sísmica y protección frente a la radiación en la zona controlada de una central nuclear. Los biorreactores se instalaron en la Central Nuclear de Cofrentes (Valencia) en las proximidades de las piscinas de almacenamiento de combustible nuclear gastado y precediendo a las resinas de intercambio iónico, de forma que reciben el agua de las piscinas permitiendo el análisis in situ de la radiación eliminada del agua de las mismas. Se conectó una lámpara de luz ultravioleta a uno de los biorreactores para poder comparar el desarrollo de bipelículas y la retención de radiactividad en ambas condiciones. En estos biorreactores se introdujeron ovillos de acero inoxidable y de titanio que se extrajeron a diversos tiempos, hasta 635 días para los ovillos de acero inoxidable y hasta 309 días para los ovillos de titanio. Se analizaron las biopelículas desarrolladas sobre los ovillos por microscopía electrónica de barrido y por microscopía de epifluorescencia. Se extrajo el ADN de las biopelículas y, tras su clonación, se identificaron los microorganismos por técnicas independientes de cultivo. Asimismo se determinó por espectrometría gamma la capacidad de las biopelículas para retener radionúclidos. Los microorganismos radiorresistentes identificados pertenecen a los grupos filogenéticos Alpha-proteobacteria, Gamma-proteobacteria, Actinobacteria, Deinococcus-Thermus y Bacteroidetes. Las secuencias de estos microorganismos se han depositado en el GenBank con los números de acceso KR817260-KR817405. Se ha observado una distribución porcentual ligeramente diferente en relación con el tipo de biorreactor. Las biopelículas han retenido fundamentalmente radionúclidos de activación. La suma de Co-60 y Mn-54 ha llegado en ocasiones al 97%. Otros radionúclidos retenidos han sido Cr-51, Co-58, Fe-59, Zn-65 y Zr-95. Se sugiere un mecanismo del proceso de retención de radionúclidos relacionado con el tiempo de formación y desaparición de las biopelículas. Se ha valorado que el proceso escalable puede ser económicamente rentable. ABSTRACT The existence of microorganisms in spent nuclear fuel pools has been demonstrated recently in nuclear power plants by using conventional microbial techniques. Subsequent studies have revealed that those microorganisms were able to colonize the stainless steel pool walls forming biofilms. Additionally, it has been observed the ability of these biofilms to retain radionuclides, which suggests the possibility of using them for radioactive water decontamination purposes. This thesis presents deeper knowledge of microbial biofilms biodiversity by using molecular biology techniques such as cloning, and develops a decontamination system on a pilot scale, in order to assess whether the process could be scalable to an industrial level. Aiming to demonstrate this was feasible, two stainless steel bioreactors were designed and manufactured, both were compatible with seismic and radiation protection standards in the controlled zone of a nuclear plant. These bioreactors were installed in the Cofrentes Nuclear Power Plant (Valencia) next to the spent nuclear fuel pools and preceding (upstream) ion exchange resins. This configuration allowed the bioreactors to receive water directly from the pools allowing in situ analysis of radiation removal. One ultraviolet lamp was connected to one of the bioreactors to compare biofilms development and radioactivity retention in both conditions. Stainless steel and titanium balls were introduced into these bioreactors and were removed after different time periods, up to 635 days for stainless steel balls and up to 309 days for titanium. Biofilms developed on the balls were analyzed by scanning electron microscopy and epifluorescence microscopy. DNA was extracted from the biofilms, was cloned and then the microorganisms were identified by independent culture techniques. Biofilms ability to retain radionuclides was also determined by gamma spectrometry. The identified radioresistant organisms belong to the phylogenetic groups Alphaproteobacteria, Gamma-proteobacteria, Actinobacteria, Deinococcus-Thermus and Bacteroidetes. The sequences of these microorganisms have been deposited in GenBank (access numbers KR817260-KR817405). A different distribution of microorganisms was observed in relation to the type of bioreactor. Biofilms have essentially retained activation radionuclides. Sometimes the sum of Co-60 and Mn-54 reached 97%. Cr-51, Co-58, Fe-59, Zn-65 and Zr-95 have also been retained. A radionuclide retention process mechanism related to biofilms formation and disappearance time is suggested. It has been assessed that the scalable process can be economically profitable.

Estudo de metodologias de controle de qualidade do Mo-99 utilizado no preparo de geradores de Mo-99/Tc-99m

O 99mTc é o radionuclídeo mais utilizado em medicina nuclear. No Brasil os geradores de 99Mo/99mTc são produzidos exclusivamente pelo Centro de Radiofarmácia do IPEN-CNEN/SP, com 99Mo importado de diferentes fornecedores. O 99Mo (t1/2 = 66 h), por ser um produto de fissão do 235U, pode conter impurezas radionuclídicas prejudiciais à saúde humana. Dessa forma, para que o gerador seja utilizado de forma segura, é necessário que o 99Mo seja avaliado por ensaios de controle de qualidade e atenda à alguma especificação descrita em farmacopeia. A Farmacopeia Europeia (FE) apresenta monografia, com parâmetros (identificação, pureza radioquímica e pureza radionuclídica), métodos de análise, e limites, para avaliação da qualidade da solução de [99Mo] na forma de molibdato de sódio, que é utilizada como matéria-prima no preparo dos geradores de 99Mo/99mTc. No entanto, observa-se uma dificuldade na implementação e execução dos métodos por parte dos produtores de geradores, com pouca literatura sobre o assunto, provavelmente devido à falta de praticidade dos métodos propostos e à extensa lista de reagentes utilizados. Nesse trabalho foram avaliados vários parâmetros de qualidade do 99Mo descritos na monografia da FE. Foram estudados métodos de separação do 99Mo de suas impurezas radionuclídicas por extração em fase sólida (SPE) e por TLC. Após separação por SPE, foi proposta a quantificação de metais por ICP-OES para avaliar a porcentagem de retenção de Mo e a porcentagem de recuperação de Ru e Te e Sr em diversos tipos de cartuchos, em substituição ao uso de radiotraçadores. Observou-se que a marca de cartucho de SPE para separação do 99Mo recomendada pela FE apresentou baixa recuperação para Ru, quando comparado aos outros cartuchos de troca aniônica disponíveis no mercado. Amostras de 99Mo de diferentes fornecedores mundiais foram analisadas. Observou-se que é possível realizar a quantificação de 103Ru em amostras de 99Mo mesmo com tempos de decaimento acima de 4 semanas. Um método alternativo de separação do 99Mo do 131I por TLC apresentou resultados promissores. Não foi feita a quantificação das impurezas radionuclídicas emissoras beta e alfa. Todas as amostras analisadas apresentaram resultados dentro das especificações da FE para pureza radioquímica (>95%) e pureza radionuclídica.

Radiological impact of cement, concrete and admixtures in Spain

It has been analyzed samples of portland cement (PC) with and without admixtures, samples of calcium aluminate cement (CAC) with different content of Al2O3 and specimens of concrete made with PC and CAC using High Resolution Gamma Spectrometry. The activity concentration index (I) is much less than 0.5 mSv y-1 for all the concrete specimens according to the Radiation protection document 112 of the European Commission. The PC without admixtures (CEM I 52,5 R) and the PC with addition of limestone (CEM II/BL 32,5 N) also have an I value much lower than 0.5 and the PC with the addition of fly ash and blast furnace slag (CEM IV/B (V) 32,5 N and III/A 42.5 N/SR) have an I value close to 0.6. The I value of the CAC used in the manufacture of structural precast concrete is of the order of 1 mSv y-1. Some of the CAC used in refractory concrete reaches a value close to 2 mSv y-1.

Madrepora oculata and Lophelia pertusa mass and 210Pb-226Ra chronology, Røst Reef, Norway, 2011

Here we show the use of the 210Pb-226Ra excess method to determine the growth rate of corals from one of the world's largest known cold-water coral reef, the Røst Reef off Norway. Two large branching framework-forming cold-water coral specimens, one Lophelia pertusa and one Madrepora oculata were collected alive at 350 m water depth from the Røst Reef at ~67° N and ~9° E. Pb and Ra isotopes were measured along the major growth axis of both specimens using low level alpha and gamma spectrometry and the corals trace element compositions were studied using ICP-QMS. Due to the different chemical behaviors of Pb and Ra in the marine environment, 210Pb and 226Ra were not incorporated the same way into the aragonite skeleton of those two cold-water corals. Thus to assess of the growth rates of both specimens we have here taken in consideration the exponential decrease of initially incorporated 210Pb as well as the ingrowth of 210Pb from the decay of 226Ra. Moreover a~post-depositional 210Pb incorporation is found in relation to the Mn-Fe coatings that could not be entirely removed from the oldest parts of the skeletons. The 226Ra activities in both corals were fairly constant, then assuming constant uptake of 210Pb through time the 210Pb-226Ra chronology can be applied to calculate linear growth rate. The 45.5 cm long branch of M. oculata reveals an age of 31 yr and a~linear growth rate of 14.4 ± 1.1 mm yr-1, i.e. 2.6 polyps per year. However, a correction regarding a remaining post-depositional Mn-Fe oxide coating is needed for the base of the specimen. The corrected age tend to confirm the radiocarbon derived basal age of 40 yr (using 14C bomb peak) with a mean growth rate of 2 polyps yr-1. This rate is similar to the one obtained in Aquaria experiments under optimal growth conditions. For the 80 cm-long specimen of L. pertusa a remaining contamination of metal-oxides is observed for the middle and basal part of the coral skeleton, inhibiting similar accurate age and growth rate estimates. However, the youngest branch was free of Mn enrichment and this 15 cm section reveals a growth rate of 8 mm yr-1 (~1 polyp every two to three years). However, the 210Pb growth rate estimate is within the lowermost ranges of previous growth rate estimates and may thus reflect that the coral was not developing at optimal growth conditions. Overall, 210Pb-226Ra dating can be successfully applied to determine the age and growth rate of framework-forming cold-water corals, however, removal of post-depositional Mn-Fe oxide deposits is a prerequisite. If successful, large branching M. oculata and L. pertusa coral skeletons provide unique oceanographic archive for studies of intermediate water environmentals with an up to annual time resolution and spanning over many decades.

Radiological characterization of clay mixed red mud in particular as regards its leaching features

The reuse of industrial by-products such as red mud is of great importance. In the case of the building material industry the reuse of red mud requires a cautious attitude, since the enhanced radionuclide content of red mud can have an effect on human health. The natural radionuclide content of red mud from the Ajka red mud reservoir and the clay sample from a Hungarian brick factory were determined by gamma spectrometry. It was found that maximum 27.8% red mud content can be added to fulfil the conditions of the EU-BSS. The effect of heat treatment was investigated on a red mud-clay mixture and it was found that in the case of radon and thoron exhalation the applied heat reduced remarkably the exhalation capacities. The leaching features of red mud and different mixtures were studied according to the MSZ-21470-50 Hungarian standard, the British CEN/TS 14429 standard and the Tessier sequential extraction method. The Tessier method and the MSZ-21470-50 standard are suitable for the characterization of materials; however, they do not provide enough information for waste deposition purposes. To this end, we propose using the CEN/TS 14429 method, because it is easy to use, and gives detailed information about the material's behaviour under different pH conditions, however, further measurements are necessary.

Usability of clay mixed red mud in Hungarian building material production industry

The naturally occurring radionuclide (²²⁶Ra,²³²Th and⁴⁰K) content of building Materials (NORM) contributes to the total radiation dose experienced by humans. In this survey 27 clay and 68 red mud samples were surveyed with gamma spectrometry and screened according to European Basic Safety Standards (BSS) I-index. It was found that average I-index of clays was 0.6 (0.4–0.8) less than the I-index of 1, which makes them suitable for building material production. The average I-index of red mud 2.3 (1.3–3.0). The maximal mixing ratio of red mud was calculated, varied between 12 and 39 %, with 23 % average.

Radiological and material characterization of high volume fly ash concrete

The main goal of research presented in this paper was the material and radiological characterization of high volume fly ash concrete (HVFAC) in terms of determination of natural radionuclide content and radon emanation and exhalation coefficients. All concrete samples were made with a fly ash content between 50% and 70% of the total amount of cementitious materials from one coal burning power plant in Serbia. Physical (fresh and hardened concrete density) and mechanical properties (compressive strength, splitting tensile strength and modulus of elasticity) of concrete were tested. The radionuclide content (226Ra, 232Th and 40K) and radon massic exhalation of HVFAC samples were determined using gamma spectrometry. Determination of massic exhalation rates of HVFAC and its components using radon accumulation chamber techniques combined with a radon monitor was performed. The results show a beneficial effect of pozzolanic activity since the increase in fly ash content resulted in an increase in compressive strength of HVFAC by approximately 20% for the same mass of cement used in the mixtures. On the basis of the obtained radionuclide content of concrete components the I -indices of different HVFAC samples were calculated and compared with measured values (0.27e0.32), which were significantly below the recommended 1.0 index value. The prediction was relatively close to the measured values as the ratio between the calculated and measured I-index ranged between 0.89 and 1.14. Collected results of mechanical and radiological properties and performed calculations clearly prove that all 10 designed concretes with a certain type of fly ash are suitable for structural and non-structural applications both from a material and radiological point of view.

Study of environmental radioactivity in Las Canteras beach

[EN]In this final degree work an assessment of the impact of environmental radioactivity, mainly on bathers of the most important beach in Las Palmas de Gran Canaria (Las Canteras), has been done. For this purpose, the main radionuclides contained in intertidal superficial sand samples have been measured by using gamma spectrometry analysis. Also alpha activity of the beach water was determinated by means of ZnS(Ag) scintillation detector. The radioactivity detected was due to the natural occurring radionuclides 226Ra (238U- series), 232Th and 40K in sand samples with an average activity concentrations of 14.6±1.0, 17.4±1.0 and 528±24 Bq/kg, respectively. From these values, the outdoor annual effective dose was of 0.047 mSv/y, which is below to the world’s average value (0.07 mSv/y)

Medidas de concentração de radônio proveniente de argamassas de cimento portland, gesso e fosfogesso

Portland cement being very common construction material has in its composition the natural gypsum. To decrease the costs of manufacturing, the cement industry is substituting the gypsum in its composition by small quantities of phosphogypsum, which is the residue generated by the production of fertilizers and consists essentially of calcium dihydrate and some impurities, such as fluoride, metals in general, and radionuclides. Currently, tons of phosphogypsum are stored in the open air near the fertilizer industries, causing contamination of the environment. The 226 Ra present in these materials, when undergoes radioactive decay, produces the 222Rn gas. This radioactive gas, when inhaled together with its decay products deposited in the lungs, produces the exposure to radiation and can be a potential cause of lung cancer. Thus, the objective of this study was to measure the concentration levels of 222Rn from cylindrical samples of Portland cement, gypsum and phosphogypsum mortar from the state of Paraná, as well as characterizer the material and estimate the radon concentration in an environment of hypothetical dwelling with walls covered by such materials. Experimental setup of 222Rn activity measurements was based on AlphaGUARD detector (Saphymo GmbH). The qualitative and quantitative analysis was performed by gamma spectrometry and EDXRF with Au and Ag targets tubes (AMPTEK), and Mo target (ARTAX) and mechanical testing with x- ray equipment (Gilardoni) and the mechanical press (EMIC). Obtained average values of radon activity from studied materials in the air of containers were of 854 ± 23 Bq/m3, 60,0 ± 7,2 Bq/m3 e 52,9 ± 5,4 Bq/m3 for Portland cement, gypsum and phosphogypsum mortar, respectively. These results extrapolated into the volume of hypothetical dwelling of 36 m3 with the walls covered by such materials were of 3366 ± 91 Bq/m3, 237 ± 28 Bq/m3 e 208 ± 21 Bq/m3for Portland cement, gypsum and phosphogypsum mortar, respectively. Considering the limit of 300 Bq/m3 established by the ICRP, it could be concluded that the use of Portland cement plaster in dwellings is not secure and requires some specific mitigation procedure. Using the results of gamma spectrometry there were calculated the values of radium equivalent activity concentrations (Raeq) for Portland cement, gypsum and phosphogypsum mortar, which were obtained equal to 78,2 ± 0,9 Bq/kg; 58,2 ± 0,9 Bq/kg e 68,2 ± 0,9 Bq/kg, respectively. All values of radium equivalent activity concentrations for studied samples are below the maximum level of 370 Bq/kg. The qualitative and quantitative analysis of EDXRF spectra obtained with studied mortar samples allowed to evaluate quantitate and the elements that constitute the material such as Ca, S, Fe, and others.