L'étude des noyaux exotiques est un outil important pour sonder la structure nucléaire des noyaux éloignés de la stabilité. Pour des noyaux situés à la drip-line proton, l'émission directe de protons a été prédite depuis le début des années 1960. Ce travail de thèse est focalisé sur l'étude de la radioactivité 2-protons du noyau 45Fe. Un modèle théorique récent, dit modèle à trois corps, prévoit les corrélations énergétiques et angulaires qui doivent exister entre les protons émis. Afin d'étudier le processus d'émission, une Chambre à Projection Temporelle a spécialement été conçue pour reconstruire en trois dimensions la trajectoire des protons. Elle a été utilisée pendant une expérience sur le séparateur LISE3 du GANIL pour l'étude de 45Fe. Pour la première fois, les deux protons émis ont pu être détectés individuellement. Des outils d'analyse spécifiques ont permis de calculer les corrélations énergétiques entre les protons, montrant qu'ils partagent équitablement l'énergie disponible, tel que le prévoient les différents modèles théoriques. Les corrélations angulaires ont été étudiées, mais le manque de statistique ne permet pas de trancher définitivement sur le processus d'émission mis en jeu même si les données sont en accord avec les prévisions du modèle à trois corps. L'expérience a également permis d'étudier l'émission retardée de protons de 43Cr. L'émission beta-2p a été identifiée ; les corrélations énergétiques et angulaires sont en faveur d'une émission séquentielle des deux protons. Enfin, et pour la première fois, l'émission retardée de trois protons a été observée pour ce noyau. / The study of exotic nuclei is a powerful tool to probe the nuclear structure far from stability. For nuclei at the proton drip-line, the direct emission of protons has been predicted since the beginning of 1960s. This PhD thesis is focused on the study of the 2-proton radioactivity of 45Fe. A recent theoretical model, called three-body model, predicts the energetic and angular correlations which have to exist between the two protons emitted. In order to study the emission process, a Time Projection Chamber was especially developped to reconstruct the proton tracks in the three-dimension space. It was used during an experiment performed at the LISE3 separator of GANIL for the study of 45Fe. For the first time the two protons emitted were individually observed. A specific analysis allows us to calculate the energetic correlations between protons, showing they share equally the decay energy, as predicted by the whole theoretical models. The angular correlations were studied, but the lack of statistics does not allow us to determine definitively the emission process which occurs even though the data agree with the three-body model predictions. Moreover, the experiment allowed to study the proton delayed emission of 43Cr. The beta-2p emission was identified; the energetic and angular correlations favour a sequential emission of the two protons. Finally, the delayed emission of three protons was observed for the first time for this nucleus.

The aim of this diploma thesis is to analyse health and safety system in department of nuclear medicine in Kolín hospital and evaluate its compliance with czech legislation. The thesis is compsed of four chapters. Chapter One gives a general introduction to health and safety issues and describes most important aspect of general health and safety legislation. Chapter Two explains the basic terms of ionizing radiation and radioactivity and focuses mainly on radiation protection, which is closely linked to the health and safety area. Chapter Three defines the legislative and institutional framework of health and safety in the area of ionizing radiation. This chapter is a starting point for Chapter Four, which analyzes the health and safety system in department of nuclear medicine in Kolín hospital, compares it with legislation requirements and evaluates the compliance.

O consumo de tabaco é uma das principais causas de doenças e morte prematuras no mundo; é a segunda droga mais consumida entre os adolescentes brasileiros, sendo considerado uma importante porta de entrada para o uso de drogas ilícitas. O Brasil é o segundo produtor mundial de tabaco e desde de 1993 destaca-se como o maior exportador. Os radionuclídeos naturais das séries do 232Th e 238U são encontrados no tabaco em baixas concentrações absorvidos diretamente do solo ou por deposição foliar. No ato de fumar ocorre a transferência desses radionuclídeos através da queima do tabaco para os tecidos e órgãos humanos podendo gerar lesões cancerígenas, sendo o mais relevante o câncer de pulmão. Existem poucos dados sobre a caracterização radiológica e elementar dos derivados do tabaco brasileiros, o que torna relevante o presente estudo que teve como objetivos a determinação da radioatividade natural e da concentração de elementos maiores e traços em derivados de tabaco produzidos e comercializados no Brasil. As técnicas analíticas empregadas foram alfa e beta total após separação radioquímica para os radionuclídeos 226Ra, 228Ra e 210Pb com determinação em detector proporcional de fluxo gasoso e baixa radiação de fundo, espectrometria alfa após separação radioquímica para o radionuclídeo 210Po, análise por ativação com nêutrons instrumental (INAA) e fluorescência por dispersão de raios X (EDXRF) para determinação de 238U, 232Th, elementos maiores e traços. Foram analisados produtos derivados da Nicotina tabacum L. de diferentes marcas adquiridas em tabacarias: cigarro não aromatizados, cigarro aromatizado, charuto, rapé, cigarro de palha e fumo de corda. Pela técnica de INAA foi possível determinar a concentração de 19 elementos e pela técnica de EDXRF de 31 elementos o que possibilitou uma ampla caracterização multielementar e as técnicas analíticas empregadas se mostraram complementares. Os elementos que apresentaram maiores valores de concentração foram o Ca e o K entre todas as amostras amostragem e entre todos os radionuclídeos naturais determinados o 228Ra apresentou maiores valores de concentração de atividade. A partir da concentração de atividade determinada foram calculadas a dose anual estimada e a dose anual efetiva para os radionuclídeos 210Pb e 210Po, levando-se em consideração um consumo anual de 3,65 kg de tabaco por ano. A dose anual efetiva variou de 69,5 μSv ano-1 à 121 μSv ano-1. Os produtos que apresentaram maiores valores de concentração e consequentemente maiores valores de dose anual efetiva, para a maioria dos radionuclídeos analisados, foram os cigarros de palha e fumos de corda. / Tobacco use is one of the leading causes of premature illness and death in the world; is the second most consumed drug among Brazilian adolescents, being considered an important gateway to the use of illicit drugs. Brazil is the second largest tobacco producer in the world and since 1993 it has been the largest exporter. The natural radionuclides from the 232Th and 238U series are found in tobacco at low concentrations absorbed directly from the soil or by foliar deposition. In the act of smoking occurs the transference of these radionuclides through the burning of the tobacco to the human tissues and organs and they can generate carcinogenic lesions, being the lung cancer the most relevant. There are few data on the elemental and radiological characterization of Brazilian tobacco products, which makes relevant the present study that had as objectives the determination of the natural radioactivity and the concentration of major and trace elements in tobacco products produced and marketed in Brazil. The analytical techniques employed were gross alpha and beta, after radiochemical separation for the radionuclides 226Ra, 228Ra and 210Pb with determination in a gaseous flow proportional detector of low background radiation, alpha spectrometry after radiochemical separation for the radionuclide 210Po, instrumental neutron activation analysis (INAA) and X-ray scattering fluorescence (EDXRF) for determination of 238U, 232Th, major and trace elements. Nicotine tabacum L. products from different brands acquired in cigar stores were analyzed: non-flavored cigarettes, flavored cigarettes, cigar, snuff, straw cigarettes and rope smoke. Using the INAA technique, it was possible to determine the concentration of 19 elements and with the EDXRF technique 31 elements, which enabled a wide multielementar characterization; the analytical techniques employed were complementary. The elements that presented the highest concentration values were Ca and K among all the samples and among all the natural radionuclides determined the 228Ra presented higher values of activity concentration. The estimated annual dose and annual effective dose for the 210Pb and 210Po radionuclides were calculated from the determined activity concentration, taking into account an annual consumption of 3.65 kg of tobacco per year. The effective annual dose ranged from 69.5 μSv y-1 to 121 μSv y-1. The products with the highest concentration values and hence the highest annual effective dose for the majority of the radionuclides analyzed were straw cigarettes and rope smoke.

Nenhuma / Os municípios de Brumadinho e Nova Lima estão localizados na região metropolitana de Belo Horizonte. São municípios importantes por pertencer a uma Área de Proteção Ambiental inserida no Quadrilátero Ferrífero. Além da riqueza mineral, a região apresenta características geológicas que inclui conglomerados quartzítico associados ao urânio e um expressivo potencial hídrico subterrâneo com características hidrogeológicas bastante particulares e complexas como o aquífero quartzítico, pertencente à Formação Moeda. No presente trabalho foram realizadas medidas radiométricas em 44 amostras de água coletadas durante treze meses em quatro pontos distintos, três pontos situados em Brumadinho de natureza superficial e um ponto pertencente à Nova Lima de natureza subterrânea. Essas amostras tiveram o conteúdo de urânio e tório determinados a partir de um Espectrômetro de Massa com Plasma Acoplado Indutivamente. Foram avaliados as atividades de alfa total, beta total, radio 226, radio 228 e chumbo 210 usando a técnica de Espectrometria de Cintilação em Líquido no qual foi necessário a calibração do mesmo usando padrões de 241Am e 90Sr/90Y, de maneira a obter uma melhor discriminação / para determinação de alfa total e beta total. Os resultados obtidos foram comparados com as recomendações da Organização Mundial da Saúde, Ministério da Saúde e o Conselho Nacional do Meio Ambiente. Os níveis máximos de radioatividade natural da água encontrados foram 0,275 0,052 Bq.L-1 para alfa total, 0,130 0,046 Bq.L-1 para 226Ra e 0,096 0,005 Bq.L-1 para 228Ra. As concentrações de betal total e 210Pb ficaram abaixo do limite de detecção. Para as concentrações de urânio e tório os valores máximos encontrados foram 0,068 μg.L-1 e 0,027 μg.L-1 respectivamente. Palavras-chave: água, radioatividade natural, Espectrômetro de Massa com Plasma Acoplado Indutivamente, Espectrometria de Cintilação em Líquido. / The municipalities of Brumadinho and Nova Lima are located in the metropolitan area of Belo Horizonte city. They are of ecological interest since they belong to an Environmental Protection Area, which is located on a very important deposit of iron ore. In addition of mineral wealth, the region has a geological characteristic that includes quartzitic conglomerates associated with uranium and significant potential underground water with hydrogeological characteristics very particular and complex, as the Quartzite Aquifer, which belongs to a geological formation called the Moeda Formation. In the present work radiometric measurements were performed for 44 water samples. The samples were collected in four geographical points, three of them situated in Brumadinho (surface water) and one point situated in Nova Lima municipality (underground water). The period of sampling extended for a thirteen months period. Some of these locations was used as an alternative sampling point. Uranium and thorium concentrations of the samples were determined using an Inductively Coupled Plasma Mass Spectrometer. The content of gross alpha and gross beta activity, and the concentration of the radionuclides 226Ra,228Ra e 210Pb were determinate by using Spectrometer Liquid Scintillation. In this case was necessary to calibrate the spectrometer using 241Am e 90Sr/90Y standards. The resultants values were compared with those recommended by the World Health Organization, Ministry of Health and the National Council of the Environment. The maximum level of water natural radioactivity found was 0,275 0,052 Bq.L-1 for gross alpha radioation, 0,130 0,046 Bq.L-1 for 226Ra and 0,096 0,005 Bq.L-1 for 228Ra. The levels of gross beta activity and 210Pb were below the detection limit. The maximum concentrations of uranium and thorium found were 0,068 μg.L-1 and 0.027 μg.L-1 respectively.

O consumo de tabaco é uma das principais causas de doenças e morte prematuras no mundo; é a segunda droga mais consumida entre os adolescentes brasileiros, sendo considerado uma importante porta de entrada para o uso de drogas ilícitas. O Brasil é o segundo produtor mundial de tabaco e desde de 1993 destaca-se como o maior exportador. Os radionuclídeos naturais das séries do 232Th e 238U são encontrados no tabaco em baixas concentrações absorvidos diretamente do solo ou por deposição foliar. No ato de fumar ocorre a transferência desses radionuclídeos através da queima do tabaco para os tecidos e órgãos humanos podendo gerar lesões cancerígenas, sendo o mais relevante o câncer de pulmão. Existem poucos dados sobre a caracterização radiológica e elementar dos derivados do tabaco brasileiros, o que torna relevante o presente estudo que teve como objetivos a determinação da radioatividade natural e da concentração de elementos maiores e traços em derivados de tabaco produzidos e comercializados no Brasil. As técnicas analíticas empregadas foram alfa e beta total após separação radioquímica para os radionuclídeos 226Ra, 228Ra e 210Pb com determinação em detector proporcional de fluxo gasoso e baixa radiação de fundo, espectrometria alfa após separação radioquímica para o radionuclídeo 210Po, análise por ativação com nêutrons instrumental (INAA) e fluorescência por dispersão de raios X (EDXRF) para determinação de 238U, 232Th, elementos maiores e traços. Foram analisados produtos derivados da Nicotina tabacum L. de diferentes marcas adquiridas em tabacarias: cigarro não aromatizados, cigarro aromatizado, charuto, rapé, cigarro de palha e fumo de corda. Pela técnica de INAA foi possível determinar a concentração de 19 elementos e pela técnica de EDXRF de 31 elementos o que possibilitou uma ampla caracterização multielementar e as técnicas analíticas empregadas se mostraram complementares. Os elementos que apresentaram maiores valores de concentração foram o Ca e o K entre todas as amostras amostragem e entre todos os radionuclídeos naturais determinados o 228Ra apresentou maiores valores de concentração de atividade. A partir da concentração de atividade determinada foram calculadas a dose anual estimada e a dose anual efetiva para os radionuclídeos 210Pb e 210Po, levando-se em consideração um consumo anual de 3,65 kg de tabaco por ano. A dose anual efetiva variou de 69,5 μSv ano-1 à 121 μSv ano-1. Os produtos que apresentaram maiores valores de concentração e consequentemente maiores valores de dose anual efetiva, para a maioria dos radionuclídeos analisados, foram os cigarros de palha e fumos de corda. / Tobacco use is one of the leading causes of premature illness and death in the world; is the second most consumed drug among Brazilian adolescents, being considered an important gateway to the use of illicit drugs. Brazil is the second largest tobacco producer in the world and since 1993 it has been the largest exporter. The natural radionuclides from the 232Th and 238U series are found in tobacco at low concentrations absorbed directly from the soil or by foliar deposition. In the act of smoking occurs the transference of these radionuclides through the burning of the tobacco to the human tissues and organs and they can generate carcinogenic lesions, being the lung cancer the most relevant. There are few data on the elemental and radiological characterization of Brazilian tobacco products, which makes relevant the present study that had as objectives the determination of the natural radioactivity and the concentration of major and trace elements in tobacco products produced and marketed in Brazil. The analytical techniques employed were gross alpha and beta, after radiochemical separation for the radionuclides 226Ra, 228Ra and 210Pb with determination in a gaseous flow proportional detector of low background radiation, alpha spectrometry after radiochemical separation for the radionuclide 210Po, instrumental neutron activation analysis (INAA) and X-ray scattering fluorescence (EDXRF) for determination of 238U, 232Th, major and trace elements. Nicotine tabacum L. products from different brands acquired in cigar stores were analyzed: non-flavored cigarettes, flavored cigarettes, cigar, snuff, straw cigarettes and rope smoke. Using the INAA technique, it was possible to determine the concentration of 19 elements and with the EDXRF technique 31 elements, which enabled a wide multielementar characterization; the analytical techniques employed were complementary. The elements that presented the highest concentration values were Ca and K among all the samples and among all the natural radionuclides determined the 228Ra presented higher values of activity concentration. The estimated annual dose and annual effective dose for the 210Pb and 210Po radionuclides were calculated from the determined activity concentration, taking into account an annual consumption of 3.65 kg of tobacco per year. The effective annual dose ranged from 69.5 μSv y-1 to 121 μSv y-1. The products with the highest concentration values and hence the highest annual effective dose for the majority of the radionuclides analyzed were straw cigarettes and rope smoke.

<p>The positron emitting radionuclide ⁶⁸Ga (T_1/2 = 68 min) might become of practical interest for clinical positron emission tomography (PET). The metallic cation, ⁶⁸Ga(III), is suitable for complexation with chelators, either naked or conjugated with biological macromolecules. Such labelling procedures require pure and concentrated preparations of ⁶⁸Ga(III), which cannot be sufficiently fulfilled by the presently available ⁶⁸Ge/⁶⁸Ga generator eluate. This thesis presents methods to increase the concentration and purity of ⁶⁸Ga obtained from a commercial ⁶⁸Ge/⁶⁸Ga generator. The use of the preconcentrated and purified ⁶⁸Ga eluate along with microwave heating allowed quantitative ⁶⁸Ga-labelling of peptide conjugates within 15 min. The specific radioactivity of the radiolabelled peptides was improved considerably compared to previously applied techniques using non-treated generator eluate and conventional heating. A commercial ⁶⁸Ge/⁶⁸Ga generator in combination with the method for preconcentration/purification and microwave heated labelling might result in an automated device for ⁶⁸Ga-based radiopharmaceutical kit production with quantitative incorporation of ⁶⁸Ga(III).</p><p>Macromolecules were labelled with ⁶⁸Ga(III) either directly or via a chelator. The bifunctional chelator, DOTA, was conjugated in solution to peptides, an antibody and oligonucleotides. The peptides had varied pI values, constitution, and length ranging from 8 to 53 amino acid residues. The oligonucleotides were of various sequences and length with modifications in backbone, sugar moiety and both 3' and 5' ends with a molecular weight up to 9.8 kDa. The bioconjugates were labeled with ⁶⁸Ga(III), and the resulting tracers were characterised chemically and biologically. The identity of the ⁶⁸Ga-labelled bioconjugates was verified. The tracers were found to be stable and their biological activity maintained. Specific radioactivity was shown to be an important parameter influencing the feasibility of accurate imaging data quantification.</p><p>Furthermore, ⁶⁸Ga-labelled peptide imaging was shown to be a useful tool to study peptide adsorption to microstructures in a chemical analysis device.</p>

The positron emitting radionuclide 68Ga (T1/2 = 68 min) might become of practical interest for clinical positron emission tomography (PET). The metallic cation, 68Ga(III), is suitable for complexation with chelators, either naked or conjugated with biological macromolecules. Such labelling procedures require pure and concentrated preparations of 68Ga(III), which cannot be sufficiently fulfilled by the presently available 68Ge/68Ga generator eluate. This thesis presents methods to increase the concentration and purity of 68Ga obtained from a commercial 68Ge/68Ga generator. The use of the preconcentrated and purified 68Ga eluate along with microwave heating allowed quantitative 68Ga-labelling of peptide conjugates within 15 min. The specific radioactivity of the radiolabelled peptides was improved considerably compared to previously applied techniques using non-treated generator eluate and conventional heating. A commercial 68Ge/68Ga generator in combination with the method for preconcentration/purification and microwave heated labelling might result in an automated device for 68Ga-based radiopharmaceutical kit production with quantitative incorporation of 68Ga(III). Macromolecules were labelled with 68Ga(III) either directly or via a chelator. The bifunctional chelator, DOTA, was conjugated in solution to peptides, an antibody and oligonucleotides. The peptides had varied pI values, constitution, and length ranging from 8 to 53 amino acid residues. The oligonucleotides were of various sequences and length with modifications in backbone, sugar moiety and both 3' and 5' ends with a molecular weight up to 9.8 kDa. The bioconjugates were labeled with 68Ga(III), and the resulting tracers were characterised chemically and biologically. The identity of the 68Ga-labelled bioconjugates was verified. The tracers were found to be stable and their biological activity maintained. Specific radioactivity was shown to be an important parameter influencing the feasibility of accurate imaging data quantification. Furthermore, 68Ga-labelled peptide imaging was shown to be a useful tool to study peptide adsorption to microstructures in a chemical analysis device.

No description available.

The role of scalar mesons in radiative vector meson decays is investigated. The effects of scalar-isoscalar f_{0}(980) and scalar-isovector a_{0}(980) mesons are studied in the mechanism of the radiative Phi-&gt / pi{+}pi{-}gamma and phi-&gt / pi{0}eta gamma decays, respectively. A phenomenological approach is used to study the radiative phi-&gt / pi{+}p{-}gamma decay by considering the contributions of sigma-meson, rho-meson and f_{0}-meson. The interference effects between different contributions are analyzed and the branching ratio for this decay is calculated. The radiative phi-&gt / pi{0}eta gamma decay is studied within the framework of a phenomenological approach in which the contributions of rho-meson, chiral loop and a_{0}-meson are considered. The interference effects between different contributions are examined and the coupling constants g_{phi a_{0} gamma} and g_{a_{0}K{+}K{-}} are estimated using the experimental branching ratio for the phi-&gt / pi{0}eta gamma decay. Furthermore, the radiative rho{0}pi{+}pi{-}gamma$ and rho{0}-&gt / pi{0}pi{0}gamma decays are studied to investigate the role of scalar-isoscalar sigma-meson. The branching ratios of the rho{0}-&gt / pi{+}pi{-}gamma and rho{0}-&gt / pi{0}pi{0}gamma decays are calculated using a phenomenological approach by adding to the amplitude calculated within the framework of chiral perturbation theory and vector meson dominance the amplitude of sigma-meson intermediate state. In all the decays studied the scalar meson intermediate states make important contributions to the overall amplitude.

Emissions of radionuclides to the atmosphere can lead to wet deposition on plants in theevent of rainfall. An increased level of radioactivity in the plants may occur due tointerception and retention of the radionuclides. If the content of the plants is above thethreshold limit value, entire yields may have to be destroyed. In order to preventcontamination or decrease the content countermeasures can be taken. The impact of thebiomass, leaf area index (LAI) and growth stage of the plant on the interception andretention is important to know in order to decide which countermeasures to use.Weather may also be an important factor. In this work the interception and retention of 134Cs and 85Sr by spring wheat, ley andspring oil-seed rape was studied. The impact of the biomass, LAI and growth stage ofthe plant and precipitation after deposition was also studied. The work was conducted asa field study with plots of the size 1 x 1 m. The plants were wet deposited with 134Cs and 85Sr by using a rain simulator. A total activity of 40 kBq/m2 for both radionuclideswas deposited on each plot. Depositions were performed during four different growthstages and the plants were sampled approximately four hours, one and five days afterdeposition. Activities of the dried plant samples were measured with a High PurityGermanium (HPGe) detector. Finally the interception fraction and the retention factorwere calculated. The study showed that the interception fraction was highest for the third growth stagefor both wheat and oil-seed rape; dough ripeness for wheat and ripening for oil-seedrape. Ley, which was harvested after two depositions, had the highest interceptionfraction at the second growth stage, flowering. Oil-seed rape and ley seemed to have aslightly higher interception fraction for 85Sr at all growth stages. There was a positiverelationship for the biomass and interception fraction, for the LAI and interceptionfraction the relationship wasn’t significant. The retention showed a weak trend ofdecreasing with time, with the decrease being largest during the first day after theinterception. However, the standard deviation was large and consequently the values uncertain. / Utsläpp av radionuklider till atmosfären kan genom regn leda till att de våtdeponeras påväxter. Radionukliderna kan då fångas upp av växterna och hållas kvar vilket kanresultera i förhöjda halter av radioaktivitet hos växterna. Om detta leder till attgränsvärden överskrids kan kassering av växter som används vid livsmedelsproduktionvara nödvändig. Motåtgärder kan vidtas för att undvika kontaminering eller minskahalterna. För att veta vilka motåtgärder som ska användas är det viktigt att veta hurväxtens biomassa, bladyteindex (LAI), utvecklingsstadium samt väderförhållandenpåverkar uppfångningen och kvarhållningen. I detta arbete undersöktes uppfångningen och kvarhållningen av 134Cs och 85Sr hosvårvete, vall och vårraps. Inverkan av växtens biomassa, LAI och utvecklingsstadiumsamt nederbörd efter deponering undersöktes också. Arbetet genomfördes som ettfältförsök med försöksrutor med storleken 1 x 1 m. Växterna våtdeponerades med 134Csoch 85Sr med hjälp av en regnsimulator. En total aktivitet på 40 kBq/m2 för bådaradionukliderna deponerades per försöksruta. Deponeringar skedde under fyra olikaväxtutvecklingsstadier och växtprover togs ungefär fyra timmar efter deponering samtett och fem dygn senare. Aktiviteten hos de torkade växtproverna mättes med en HighPurity Germanium (HPGe) detektor. Därefter beräknades uppfångningsfraktioner ochkvarhållningsfaktorer. Försöket visade att uppfångningsfraktionen var störst vid det tredjeväxtutvecklingsstadiet för både vete och raps; degmognad för vete och fröutveckling förraps. Vallen, som slogs av efter två deponeringar, uppvisade störst uppfångningsfraktionvid andra växtutvecklingsstadiet, blomning. Hos raps och vall verkadeuppfångningsfraktionen för 85Sr vara något högre vid samtliga växtutvecklingsstadier.För biomassan och uppfångningsfraktionen fanns ett positivt samband, för LAI ochuppfångningsfraktionen var sambandet inte signifikant. Kvarhållningen visade en svagtrend att minska med tiden, minskningen var störst under det första dygnet efteruppfångningen. Dock var standardavvikelsen stor och värden därmed osäkra.