Three models have been developed and applied in the performance assessment of a final repository. They are based on accepted theories and experimental results for known and possible mechanisms that may dominate in the oxidative dissolution of spent fuel and the release of nuclides from a canister. Assuming that the canister is breached at an early stage after disposal, the three models describe three sub-systems in the near field of the repository, in which the governing processes and mechanisms are quite different. In the model for the oxidative dissolution of the fuel matrix, a set of kinetic descriptions is provided that describes the oxidative dissolution of the fuel matrix and the release of the embedded nuclides. In particular, the effect of autocatalytic reduction of hexavalent uranium by dissolved H2, using UO2 (s) on the fuel pellets as a catalyst, is taken into account. The simulation results suggest that most of the radiolytic oxidants will be consumed by the oxidation of the fuel matrix, and that much less will be depleted by dissolved ferrous iron. Most of the radiolytically produced hexavalent uranium will be reduced by the autocatalytic reaction with H2 on the fuel surface. It will reprecipitate as UO2 (s) on the fuel surface, and thus very little net oxidation of the fuel will take place. In the reactive transport model, the interactions of multiple processes within a defective canister are described, in which numerous redox reactions take place as multiple species diffuse. The effect of corrosion of the cast iron insert of the canister and the reduction of dissolved hexavalent uranium by ferrous iron sorbed onto iron corrosion products and by dissolved H2 are particularly included. Scoping calculations suggest that corrosion of the iron insert will occur primarily under anaerobic conditions. The escaping oxidants from the fuel rods will migrate toward the iron insert. Much of these oxidants will, however, be consumed by ferrous iron that comes from the corrosion of iron. The nonscavenged hexavalent uranium will be reduced by ferrous iron sorbed onto the iron corrosion products and by dissolved hydrogen. In the transport resistance network model, the transport of reactive actinides in the near field is simulated. The model describes the transport resistance in terms of coupled resistors by a coarse compartmentalisation of the repository, based on the concept that various ligands first come into the canister and then diffuse out to the surroundings in the form of nuclide complexes. The simulation results suggest that carbonate accelerates the oxidative dissolution of the fuel matrix by stabilizing uranyl ions, and that phosphate and silicate tend to limit the dissolution by the formation of insoluble secondary phases. The three models provide powerful tools to evaluate "what if" situations and alternative scenarios involving various interpretations of the repository system. They can be used to predict the rate of release of actinides from the fuel, to test alternative hypotheses and to study the response of the system to various parameters and conditions imposed upon it. / QC 20100521

The aim of this study is the development of a statistical denoising method, to reduce noise in scintigraphic images, preserving image quality characteristics such as contrast, and resolution. The method is based on principal component analysis (PCA) reduces the volume of image data, preserving a large amount of useful information, by considering that a small number of independent image components contain useful information (signal), whereas a large number of independent components contain statistical noise. Therefore, applying PCA and discarding the image components, which correspond to noise, noise reduction can be achieved. PCA is a multivariate correlation analysis technique which explains algebraically a variance-covariance structure of observed data sets with a few linear combinations of original variables [28-30]. The motivation behind PCA is to find a direction, or a few directions, that explain as much of the variability as possible. This is achieved because each direction is associated with a linear sum of the variables, which are linear sums of the initial variables. Thus, the first principal component is the linear sum corresponding to the direction of greatest variability. The search for the second principal component is restricted to variables that are uncorrelated with the first principal component. To assess the performance of the proposed denoising method was compared to four conventional noise reduction methods, employing quantitative image quality characteristics (noise and spatial resolution characteristics). Specifically, the linear filter (smooth 3x3 and smooth 5x5), and the non-linear filter (median 3x3 and median 5x5) were used. Additionally to demonstrate the applicability of the proposed method, it was applied to clinical planar scintigraphic images. / Ο όρος Πυρηνική Ιατρική περιγράφει τις διαγνωστικές και θεραπευτικές διαδικασίες, που απαιτούν την εισαγωγή ραδιοφαρμάκων στον οργανισμό. Οι απεικονιστικές τεχνικές της πυρηνικής ιατρικής αξιοποιούν το γεγονός ότι η ακτινοβολία των ραδιενεργών νουκλιδίων μπορεί να διαπεράσει τους ιστούς και να ανιχνευθεί εξωτερικά, καθιστώντας δυνατή τη μελέτη φυσιολογικών και βιοχημικών διαδικασιών εν εξελίξει σε ζωντανούς οργανισμούς. Η απεικόνιση πυρηνικής ιατρικής χρησιμοποιείται ευρέως στην κλινική πράξη. Σε σύγκριση με άλλες απεικονιστικές τεχνικές έχει το πλεονέκτημα ότι μπορεί να δώσει ταυτόχρονα ανατομικές και λειτουργικές πληροφορίες. Το μειονέκτημα όμως των εικόνων πυρηνικής ιατρικής είναι ο πολύ χαμηλός λόγος σήματος-προς-θόρυβο (signal-to-noise ratio-SNR) σε σχέση με εικόνες άλλων απεικονιστικών τεχνικών. Η εικόνα στην πυρηνική ιατρική αντιστοιχεί στην κατανομή ραδιενεργού υλικού μέσα στο σώμα του ασθενούς. Η τιμή κάθε pixel της εικόνας σχετίζεται με τον αριθμό των γ-φωτονίων που ανιχνεύονται σε μια περίοδο χρόνου. Οι τιμές αυτές ακολουθούν μια στατιστική κατανομή (κατανομή Poisson), λόγω της τυχαίας φύσης της διάσπασης του χορηγούμενου ραδιενεργού υλικού. Η διακύμανση μιας τυχαίας Poisson μεταβλητής ισούται με τη μέση τιμή της και συνεπώς για να μειωθεί η επίδραση του Poisson θορύβου, ο αριθμός των φωτονίων που ανιχνεύονται πρέπει να αυξηθεί. Αυτό μπορεί να επιτευχθεί με τρεις τρόπους. Πρώτον, με αύξηση του χρόνου καταγραφής, που συνεπάγεται όμως αυξημένο κίνδυνο μετακίνησης του ασθενή. Δεύτερον, με αύξηση της δόσης ραδιενεργού υλικού, που δίνεται στον ασθενή, κάτι που προφανώς είναι ανεπιθύμητο. Η τελευταία λύση είναι η χρήση γ-κάμερας με πολλαπλούς ανιχνευτές ή με πολύ ευαίσθητο ανιχνευτή, που συνεπάγεται αυξημένο κόστος και πολυπλοκότητα. Για το λόγο αυτό, τεχνικές ψηφιακής επεξεργασίας για μείωση θορύβου εικόνας μπορούν να συνεισφέρουν σημαντικά στη βελτίωση της εικόνας στην πυρηνική ιατρική. Οι κλασικές τεχνικές μείωσης θορύβου κάνουν χρήση γραμμικών φίλτρων εξομάλυνσης (smoothing filters) για την αντικατάσταση της τιμής κάθε εικονοστοιχείου (pixel) με μια μέση τιμή ,η οποία προκύπτει από τη γειτονιά του. Τα φίλτρα αυτά όμως έχουν το μειονέκτημα ότι μειώνουν την αντίθεση και τη διακριτική ικανότητα της εικόνας. Μη γραμμικά φίλτρα, όπως το median φίλτρο, διατηρούν σε πολλές περιπτώσεις την αντίθεση των δομών, αλλά επίσης υποβαθμίζουν την ποιότητα εικόνας. Ένας από τους λόγους, που οι συμβατικές τεχνικές δεν έχουν ικανοποιητικά αποτελέσματα είναι ότι δεν αντιμετωπίζουν το γεγονός ότι ο θόρυβος σε κάθε pixel εξαρτάται από την ένταση του σήματος (signal dependent noise). Για το λόγο αυτό έχουν προταθεί πρασαρμοζόμενα (adaptive) φίλτρα μείωσης θορύβου. Η κατηγορία των φίλτρων αυτών χρησιμοποιεί στατιστικά κριτήρια για την επιλογή των γειτονικών pixels, που χρησιμοποιούνται για τον υπολογισμό της τιμής του κεντρικού pixel. Στη συγκεκριμένη διπλωματική εργασία υλοποιήθηκε μέθοδος μείωσης θορύβου, που βασίζεται στη Ανάλυση Κύριων Συνιστωσών (Principal Components Analysis, PCA), προσαρμοσμένη σε εικόνες πυρηνικής ιατρικής. Η μέθοδος αυτή στοχεύει στη μείωση του κβαντικού θορύβου Poisson κατανομής, που εμπεριέχεται σε εικόνες πυρηνικής ιατρικής. Η PCA είναι μια στατιστική τεχνική, που εξετάζει τις σχέσεις που διέπουν τις μεταβλητές ενός συνόλου δεδομένων και βρίσκει ένα υποσύνολο από τις πιο σημαντικές μεταβλητές. Οι νέες μεταβλητές περιγράφονται σαν γραμμικός συνδυασμός των αρχικών μεταβλητών και κατατάσσονται σε σειρά σημαντικότητας σε σχέση με τη διακύμανση των δεδομένων που η κάθε μια εκφράζει. Η πρώτη σημαντική συνιστώσα (principal component) είναι η μεταβλητή που εκφράζει το μέγιστο ποσό διακύμανσης. Η δεύτερη σημαντική συνιστώσα εκφράζει το επόμενο μεγαλύτερο ποσό διακύμανσης και είναι ανεξάρτητη από της πρώτης κ.ο.κ.. Ουσιαστικά, το σύνολο των αρχικών σχετιζόμενων μεταβλητών μετασχηματίζεται σε ένα σύνολο ασυσχέτιστων μεταβλητών, όπου οι λιγότερο σημαντικές μεταβλητές μπορούν να απομακρυνθούν χωρίς ουσιαστική απώλεια πληροφορίας. Η κύρια χρήση της PCA είναι να μειωθεί ο όγκος ενός συνόλου δεδομένων και να οδηγηθούμε σε μια βέλτιστη περιγραφή τους. Στην περίπτωση των εικόνων πυρηνικής ιατρικής μπορούμε να θεωρήσουμε ότι λόγω του στατιστικού χαρακτήρα του θορύβου η χρήσιμη πληροφορία περιέχεται σε μικρό αριθμό συνιστωσών, ενώ ο θόρυβος σε ένα μεγάλο αριθμό μη-σημαντικών συνιστωσών. Εφαρμόζοντας συνεπώς την PCA και αφαιρώντας τις συνιστώσες που αντιστοιχούν στον θόρυβο μπορούμε να επιτύχουμε σημαντική μείωση του. Επίσης πραγματοποιήθηκε συγκριτική αξιολόγηση μεταξύ της προτεινόμενης μεθόδου και άλλων μεθόδων μείωσης θορύβου σε εικόνες πυρηνικής ιατρικής. Συγκεκριμένα, η μέθοδος που βασίζεται στη PCA συγκρίθηκε με το φίλτρο εξομάλυνσης (smooth 3x3 και smooth 5x5) και το μη-γραμμικό φίλτρο (median 3x3 και median 5x5). Όλες οι μέθοδοι εφαρμόστηκαν σε πρότυπες εικόνες πυρηνικής ιατρικής, που αποκτήθηκαν με τη βοήθεια δυο ομοιωμάτων, ενός ομοιώματος με μικρές θερμές περιοχές (hot spots phantom) και ενός ομοιώματος μέτρησης διακριτικής ικανότητας (bar phantom) σε διαφορετικούς χρόνους. Στις επεξεργασμένες εικόνες μετρήθηκαν ο θόρυβος, η αντίθεση, ο λόγος αντίθεσης-προς-θόρυβο (Contrast-to-Noise-ratio, CNR) και το εύρος στο ήμισυ της μέγιστης τιμής (Full-Width-of-Half-Maximum, FWHM). Τα αποτελέσματα της σύγκρισης έδειξαν ότι η μέθοδος που βασίζεται στη PCA μειώνει σημαντικά το θόρυβο, ενώ ταυτόχρονα αυξάνει το λόγο αντίθεσης-προς-θόρυβο. Τέλος, πραγματοποιήθηκε πιλοτική μελέτη προτίμησης από δυο πυρηνικούς ιατρούς μεταξύ των μεθόδων μείωσης θορύβου σε δείγμα κλινικών εικόνων συγκεκριμένων εξετάσεων στατικών λήψεων (οστών, πνευμόνων, θυρεοειδούς, παραθυρεοειδούς και νεφρών). Η μελέτη αυτή έδειξε ότι η PCA μειώνει σημαντικά το θόρυβο, ενώ ταυτόχρονα βελτιώνει οπτικά τις ανατομικές δομές των εικόνων.

<p>Härtill 5 uppsatser</p> / digitalisering@umu

Fontes radioativas possuem radionuclídeos. Um radionuclídeo é um átomo com um núcleo instável, ou seja, um núcleo caracterizado pelo excesso de energia que está disponível para ser emitida. Neste processo, o radionuclídeo sofre o decaimento radioativo e emite raios gama e partículas subatômicas, constituindo-se na radiação ionizante. Então, a radioatividade é a emissão espontânea de energia a partir de átomos instáveis. A identificação correta de radionuclídeos pode ser crucial para o planejamento de medidas de proteção, especialmente em situações de emergência, definindo o tipo de fonte de radiação e seu perigo radiológico. Esta dissertação apresenta a aplicação do método de agrupamento subtrativo, implementada em hardware, para um sistema de identificação de elementos radioativos com uma resposta rápida e eficiente. Quando implementados em software, os algoritmos de agrupamento consumem muito tempo de processamento. Assim, uma implementação dedicada para hardware reconfigurável é uma boa opção em sistemas embarcados, que requerem execução em tempo real, bem como baixo consumo de energia. A arquitetura proposta para o hardware de cálculo do agrupamento subtrativo é escalável, permitindo a inclusão de mais unidades de agrupamento subtrativo para operarem em paralelo. Isso proporciona maior flexibilidade para acelerar o processo de acordo com as restrições de tempo e de área. Os resultados mostram que o centro do agrupamento pode ser identificado com uma boa eficiência. A identificação desses pontos pode classificar os elementos radioativos presentes em uma amostra. Utilizando este hardware foi possível identificar mais do que um centro de agrupamento, o que permite reconhecer mais de um radionuclídeo em fontes radioativas. Estes resultados revelam que o hardware proposto pode ser usado para desenvolver um sistema portátil para identificação radionuclídeos. / Radioactive sources include radionuclides. A radionuclide is an atom with an unstable nucleus, i.e. a nucleus characterized by excess of energy, which is available to be imparted. In this process, the radionuclide undergoes radioactive decay and emits gamma rays and subatomic particles, constituting the ionizing radiation. So, radioactivity is the spontaneous emission of energy from unstable atoms. Correct radionuclide identification can be crucial to planning protective measures, especially in emergency situations, by defining the type of radiation source and its radiological hazard. This project introduces the application of subtractive clustering method, in a hardware implemnetation, for an identification system of radioactive elements that allows a rapid and efficient identification. In software implementations, clustering algorithms, usually, are demanding in terms of processing time. Thus, a custom implementation on reconfigurable hardware is a viable choice in embedded systems, so as to achieve real-time execution as well as low power consumption. The proposed architecture for the hardware of subtractive clustering is scalable, allowing for the inclusion of more of subtractive clustering unit that operate in parallel. This provides greater flexibility to accelerate the hardware with respect to the time and area requirements. The results show that the expected cluster center can be identified with efficiently. The identification of these points can classify the radioactive elements present in a sample. Using the designed hardware, it is possible to identify more than one cluster center, which would lead to the recognition of more than one radionuclide in radioactive sources. These results reveal that the proposed hardware to subtractive cluster can be used to design a portable system for radionuclides identification.

Made available in DSpace on 2014-10-09T12:43:21Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:58:04Z (GMT). No. of bitstreams: 1 06428.pdf: 6304808 bytes, checksum: 564076d766d1209b8ce5d2f96ff4876b (MD5) / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

Fontes radioativas possuem radionuclídeos. Um radionuclídeo é um átomo com um núcleo instável, ou seja, um núcleo caracterizado pelo excesso de energia que está disponível para ser emitida. Neste processo, o radionuclídeo sofre o decaimento radioativo e emite raios gama e partículas subatômicas, constituindo-se na radiação ionizante. Então, a radioatividade é a emissão espontânea de energia a partir de átomos instáveis. A identificação correta de radionuclídeos pode ser crucial para o planejamento de medidas de proteção, especialmente em situações de emergência, definindo o tipo de fonte de radiação e seu perigo radiológico. Esta dissertação apresenta a aplicação do método de agrupamento subtrativo, implementada em hardware, para um sistema de identificação de elementos radioativos com uma resposta rápida e eficiente. Quando implementados em software, os algoritmos de agrupamento consumem muito tempo de processamento. Assim, uma implementação dedicada para hardware reconfigurável é uma boa opção em sistemas embarcados, que requerem execução em tempo real, bem como baixo consumo de energia. A arquitetura proposta para o hardware de cálculo do agrupamento subtrativo é escalável, permitindo a inclusão de mais unidades de agrupamento subtrativo para operarem em paralelo. Isso proporciona maior flexibilidade para acelerar o processo de acordo com as restrições de tempo e de área. Os resultados mostram que o centro do agrupamento pode ser identificado com uma boa eficiência. A identificação desses pontos pode classificar os elementos radioativos presentes em uma amostra. Utilizando este hardware foi possível identificar mais do que um centro de agrupamento, o que permite reconhecer mais de um radionuclídeo em fontes radioativas. Estes resultados revelam que o hardware proposto pode ser usado para desenvolver um sistema portátil para identificação radionuclídeos. / Radioactive sources include radionuclides. A radionuclide is an atom with an unstable nucleus, i.e. a nucleus characterized by excess of energy, which is available to be imparted. In this process, the radionuclide undergoes radioactive decay and emits gamma rays and subatomic particles, constituting the ionizing radiation. So, radioactivity is the spontaneous emission of energy from unstable atoms. Correct radionuclide identification can be crucial to planning protective measures, especially in emergency situations, by defining the type of radiation source and its radiological hazard. This project introduces the application of subtractive clustering method, in a hardware implemnetation, for an identification system of radioactive elements that allows a rapid and efficient identification. In software implementations, clustering algorithms, usually, are demanding in terms of processing time. Thus, a custom implementation on reconfigurable hardware is a viable choice in embedded systems, so as to achieve real-time execution as well as low power consumption. The proposed architecture for the hardware of subtractive clustering is scalable, allowing for the inclusion of more of subtractive clustering unit that operate in parallel. This provides greater flexibility to accelerate the hardware with respect to the time and area requirements. The results show that the expected cluster center can be identified with efficiently. The identification of these points can classify the radioactive elements present in a sample. Using the designed hardware, it is possible to identify more than one cluster center, which would lead to the recognition of more than one radionuclide in radioactive sources. These results reveal that the proposed hardware to subtractive cluster can be used to design a portable system for radionuclides identification.

INTRODUÇÃO: O câncer infantil é a primeira causa de morte em crianças, nos países desenvolvidos. Nos últimos 40 anos, graças ao desenvolvimento da Oncopediatria e de drogas como as antraciclinas (ATC), a taxa de cura tem atingido até 80%. Isto repercutiu em significativo aumento da sobrevida e, consequentemente, nos efeitos deletérios da quimioterapia com ATC, como a cardiotoxicidade. A fim de estudar os efeitos tardios da quimioterapia com ATC sobre o sistema nervoso cardíaco simpático (SNS), foi realizado estudo de cintilografia com 123I-mIBG (meta-iodobenzilguanedina ligado ao iodo123) e comparado com dose dos ATCs e fração de ejeção do ventrículo esquerdo (FEVE), através da ventriculografia radioisotópica (VR). As variáveis analisadas pela cintilografia com 123I-mIBG foram a relação coração/mediastino (C/M) e a taxa de clareamento (TC) que sinalizam o funcionamento neuronal cardíaco. MÉTODOS: realizado estudo transversal de pacientes assintomáticos submetidos à quimioterapia com ATC na infância e adolescência, com período de 2 a 21 anos, após o término do tratamento, e com ecocardiograma (ECO) normal. Dos 118 pacientes participantes recrutados, 27 foram excluídos (motivos: radioterapia torácica, desistência e uso de cardioprotetores). Os dados clínicos e patológicos dos 91 pacientes participantes foram coletados dos prontuários ou através de anamnese. Simultaneamente foi estudado um grupo controle (40 voluntários), e, com as avaliações de imagens com 123I-mIBG e VR, foi preenchida uma ficha de coleta padronizada previamente elaborada e digitada em banco de dados no Software IBM® SPSS® Statistics 20.0.1 for Windows, para posterior análise. Os achados dos pacientes foram analisados e comparados aos do grupo controle. RESULTADOS: Neste grupo, a média de acúmulo da 123I-mIBG - 3,5h, avaliada pela relação C/M, foi de 2,23 com IC [95%] (2,17-2,29). A média da TC foi de 10,27% com IC [95%] (7,52-13,03). Para ambas as informações, os valores apresentaram-se dentro da normalidade. Ao se comparar com o grupo controle (40 voluntários, 28 homens e 14 mulheres, idade: 3 a 36 anos), onde a relação C/M foi de 2,26 com IC [95%] (2,18-2,34) e a média da TC foi de 9,64% com IC [95%] (5,76-13,52), não houve diferença significativa. Ressalte-se que 6,6% do total de pacientes, apesar de não alterarem significativamente a média do grupo na análise estatística, apresentaram relação C/M <1,9 (valor considerado cut off). Em relação à variável FEVE da VR, houve uma diferença de -3,68, onde o p valor foi < 0,01 e o IC (-5,99; -1,37), sendo a FEVE do grupo de pacientes menor que a FEVE do grupo controle. CONCLUSÃO: Os valores da relação C/M e TC, encontrados com a cintilografia cardíaca com 123I-mIBG no grupo de pacientes, não mostraram diferença significativa com o grupo controle. No entanto, 6,6% dos pacientes submetidos ao tratamento com ATC apresentaram alterações neuronais cardíacas (relação C/M), abaixo do valor mínimo. Além disso, a média da FEVE foi menor, apesar de ainda encontrar-se com valores absolutos dentro da normalidade. Tais achados podem ser um indício de alterações clínicas relevantes no futuro / INTRODUCTION: Child cancer is the first cause of children\'s death in developed countries. In the last 40 years, thanks to the development of the pediatric oncology and drugs like the Anthracyclines (ATC), cure rate has reached up to 80%. This reflected a significant improvement in survival and as a consequence the deleterious effects from chemotherapy, like cardiotoxicity, has emerged. In order to study the later effects of the chemotherapy with ATC on the sympathetic nervous system (SNS) cardiac 123I-mIBG (123Imetaiodobenzylguanidine) scintigraphy was performed and compared to the left ventricle ejection fraction (LVEF), through radionuclide ventriculography (RV). The variables analized by the 123I-mIBG scintigraphy were the heart/mediastinum ratio (H/M) and the washout rate (WR). METHODS: This is a transversal study of asymptomatic patients undergoing ATC chemotherapy in childhood and adolescence, ages varying from 2 to 21 years after the end of the treatment and normal echocardiogram (ECO). From the 118 recruted participant subjects, 27 were excluded ( thoracic radiotherapy, abandonment and use of cardioprotectors). The clinical and pathological data from the 91 patients were collected from medical records or clinical history. A control group of 40 healthy volunteers(28 male, 14 females; ages varying from 3 to 36) was studied simultaneously and evaluated as well with 123I-mIBG and RV. All data collected were stored in a databank for later analysis, patients findings versus control group. RESULTS: In the patient group the average H/M ratio from the late 123I-mIBG image was 2,23 with CI [95%] (2,17-2,29), and average WR was 10,27% with CI [95%] (7,52-13,03). The control group had the H/M ratio of 2,26 with CI [95%] (2,18-2,34) and the WR rate of 9,64% with CI [95%] (5,76-13,52). The comparison between groups was not significant. However, it has to be highlighted that 6,6% of all the patients had abnormal H/M values which were below the cutoff considered of <1,9. On the other hand, when comparing the mean LVEF, there was a difference of -3,68 with p < 0,01 and CI (-5,99; -1,37), being the LVEF in the patient group lower than the control. CONCLUSION: Although there was no significance in the intergroup comparison for H/M and WR, there was a small proportion of patients who presented neuronal cardiac alterations (H/M ratio) below the minimum value. Besides that, the LVEF average was lower, despite still having absolute values within the normality. Such findings can be an indication of the clinical alterations as relevant in the future

Made available in DSpace on 2014-10-09T12:37:34Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:03:32Z (GMT). No. of bitstreams: 1 05177.pdf: 1071515 bytes, checksum: 549d323670762fe6597fcda6cf7ea4fc (MD5) / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

Made available in DSpace on 2014-10-09T12:38:37Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:05:27Z (GMT). No. of bitstreams: 1 06044.pdf: 6865948 bytes, checksum: a08cf9df31bad7efc0884ad8cc855442 (MD5) / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

In this thesis I target the assesment of a volume activity of gamma ray nuclides in the environment and the examination of the operation the Nuclear Power Station (NPS) Temelín in term of emitting the gamma ray nuclides and their environmental impact. There were collected data of several sorts of environmental samples for statistical analysis. The activity of gamma ray nuclides released by nuclear power plants to the environment after its initiation was compared to the activity of gamma ray nuclides contained it the environment before the initiation of the NPS. It was chosen five exemplary samples - , aerosoles, sediments, milk, soil and surface moisture, which have been scanning in years 1995 and 2005. In these samples, that have sufficient amount of data (sorts of milk, aerosoles and surface moisture) so the statistical analysis was relevant, it was proved, by the non-parametrical Mann-Whitney statistical testing, that there were no statistical difference between the data before and after the initiation of the NPS. The environmental impact wasn´t demonstrated. In these samples, that haven´t sufficient amount of data (sediments and soil), they were also tested (parametrical t. test) and it was proved that there were no statistical difference between the data before and after the initiation of the NPS. Because of very low quality of the testing, we have to use the box plot to ascertain the influence of NPS. In these plots the environmental impact wasn´t demonstrated as well.