Spectroscopic orbital elements and/or related parameters have been determined for eight binary systems, using radial-velocity measurements that have a typical precision of about 15 ms⁻¹. The orbital periods of these systems range from about 10 days to 26 years, with a median of about 6 years. Orbital solutions were determined for the seven systems with shorter periods. The measurement of the mass ratio of the longest-period system, HD217166, demonstrates that this important astrophysical quantity can be estimated in a model-free manner with less than 10% of the orbital cycle observed spectroscopically.\\ Single-lined orbital solutions have been derived for five of the binaries. Two of these systems are astrometric binaries: β Ret and ν Oct. The other SB1 systems were 94 Aqr A, θ Ant, and the 10-day system, HD159656. The preliminary spectroscopic solution for θ Ant (P~18 years), is the first one derived for this system. The improvement to the precision achieved for the elements of the other four systems was typically between 1--2 orders of magnitude. The very high precision with which the spectroscopic solution for HD159656 has been measured should allow an investigation into possible apsidal motion in the near future. In addition to the variable radial velocity owing to its orbital motion, the K-giant, ν Oct, has been found to have an additional long-term irregular periodicity, attributed, for the time being, to the rotation of a large surface feature.\\ Double-lined solutions were obtained for HD206804 (K7V+K7V), which previously had two competing astrometric solutions but no spectroscopic solution, and a newly discovered seventh-magnitude system, HD181958 (F6V+F7V). This latter system has the distinction of having components and orbital characteristics whose study should be possible with present ground-based interferometers. All eight of the binary systems have had their mass ratio and the masses of their components estimated.\\ The following comments summarize the motivation for getting these results, and the manner in which the research was carried out. \\ The majority of stars exist in binary systems rather than singly as does the Sun. These systems provide astronomers with the most reliable and proven means to determine many of the fundamental properties of stars. One of these properties is the stellar mass, which is regarded as being the most important of all, since most other stellar characteristics are very sensitive to the mass. Therefore, empirical masses, combined with measurements of other stellar properties, such as radii and luminosities, are an excellent test for competing models of stellar structure and evolution.\\ Binary stars also provide opportunities to observe and investigate many extraordinary astrophysical processes that do not occur in isolated stars. These processes often arise as a result of direct and indirect interactions between the components, when they are sufficiently close to each other. Some of the interactions are relatively passive, such as the circularization of the mutual orbits, whilst others result from much more active processes, such as mass exchange leading to intense radiation emissions. \\ A complete understanding of a binary system's orbital characteristics, as well as the measurement of the all-important stellar masses, is almost always only achieved after the binary system has been studied using two or more complementary observing techniques. Two of the suitable techniques are astrometry and spectroscopy. In favourable circumstances, astrometry can deduce the angular dimensions of the orbit, the total mass of the system, and sometimes, its distance from us. Spectroscopy, on the other hand, can determine the linear scale of the orbit and the ratio of the stellar masses, based on the changing radial velocities of both stars. When a resolved astrometric orbital solution is also available, the velocities of both stars can allow the binary system's parallax to be determined, and the velocities of one star can provide a measure of the system mass ratio.\\ Unfortunately, relatively few binary systems are suited to these complementary studies. Underlying this difficulty are the facts that, typically, astrometrically-determined orbits favour those with periods of years or decades, whereas spectroscopic orbital solutions are more often measured for systems with periods of days to months. With the development of high-resolution astrometric and spectroscopic techniques in recent years, it is hoped that many more binary systems will be amenable to these complementary strategies.\\ Several months after this thesis began, a high-resolution spectrograph, HERCULES, commenced operations at the Mt John University Observatory, to be used in conjuction with the 1-metre McLellan telescope. For late-type stars, the anticipated velocity precision was ≲10 ms⁻¹. The primary goals of this thesis were: 1.~to assess the performance of HERCULES and the related reduction software that subsequently followed, 2.~to carry out an observational programme of 20 or so binary systems, and 3.~to determine the orbital and stellar parameters which characterize some of these systems. The particular focus was on those binaries that have resolved or unresolved astrometric orbital solutions, which therefore may be suited to complementary investigations.\\ HERCULES was used to acquire spectra of the programme stars, usually every few weeks, over a timespan of about three years. High-resolution spectra were acquired for the purpose of measuring precise radial velocities of the stars. When possible, orbital solutions were derived from these velocities, using the method of differential corrections.

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.

Le recours à l'énergie électronucléaire pour diminuer les émissions anthropiques de CO2 nécessite des avancées technologiques majeures. Les réacteurs nucléaires de IVe génération doivent répondre à plusieurs contraintes, telles qu'une sûreté améliorée, la régénération du combustible et la minimisation de la production de déchets radioactifs. De ce point de vue, l'utilisation du Cycle Thorium en Réacteurs à Sel Fondu semble prometteuse. Cet axe de recherche, étudié dans le passé, avait cependant débouché sur un concept dont les défauts ont empêché la réalisation. Une nouvelle réflexion est menée afin de trouver des solutions et d'aboutir au concept de Thorium Molten Salt Reactor. Le couplage d'un code de transport de neutrons avec un code d'évolution des matériaux permet de simuler le comportement d'un coeur nucléaire, et de suivre son évolution tout au long de sa vie. Par cette méthode, nous avons étudié un large éventail de configurations de réacteurs. Les performances de ces systèmes ont été évaluées, grâce à un jeu de contraintes qu'ils doivent satisfaire au mieux. Ce travail a permis de comprendre bon nombre de phénomènes physiques régissant le comportement de ces réacteurs. Grâce à cette nouvelle compréhension, la recherche de configurations acceptables a pu aboutir à des solutions satisfaisantes, apportant un souffle nouveau dans le domaine des Réacteurs à Sel Fondu.

Dans l'éventualité d'une contribution significative du nucléaire aux besoins énergétiques mondiaux, le problème de la gestion des déchets actuels remet en question la pérennité de la liere REP. En complément des recherches sur le stockage et l'incinération de ces déchets, il convient donc d'envisager des systemes innovants dédiés à une production d'énergie nucléaire durable, aussi sobre, propre et sûre que possible. Nous nous intéressons ici au concept de réacteur à sels fondus, dont le combustible est liquide. Cette particularité autorise un retraitement en ligne pyrochimique, qui peut permettre de s'affranchir de certaines limites neutroniques. Le projet MSBR (Molten Salt Breeder Reactor) d'un réacteur à sels fluorures et à modérateur graphite a ainsi montré à la fin des années 1960 que la surgénération en cycle thorium et en spectre thermique est accessible avec un retraitement en ligne approprié.<br> A l'aide d'outils de simulation développés autour du code Monte Carlo MCNP, nous réévaluons dans un premier temps les performances d'un système de référence inspiré du projet MSBR. L'étude complète de la phase de mise à l'équilibre de ce réacteur d'une puissance de 2500 MWth, démarré en 232Th/233U, nous permet de valider nos choix de référence. L'équilibre obtenu montre une réduction importante des inventaires et des radiotoxicités induites par rapport aux autres cycles possibles. Le retraitement en ligne associé est suffisamment efficace pour rendre le systeme surgénérateur, avec un temps de doublement d'une trentaine d'années à l'équilibre.<br> A partir du système de référence, nous testons ensuite différentes options en termes d'économie de neutrons, de transmutation et de contrôle de la réactivité. Il en ressort que c'est le retraitement en ligne qui apporte le plus de flexibilité à ce système particulièrement bien adapté à la production d'énergie en cycle thorium. L'étude de scenarios de transition à cette filière quantifie les limites d'un éventuel déploiement à partir du parc français actuel, et montre enfin qu'une gestion raisonnée du plutonium disponible serait nécessaire dans tous les cas.

La datation non destructive de formations carbonatées a été entreprise par spectrométrie y du déséquilibre de la famille 238*U (limité par 230Th - Ionium - 75 ka). Un nouveau spectromètre y Ge-HP à bas bruit-de-fond <10 ppb U - équivalent) a permis de dater des échantillons de faible teneur en U (> 0,1 ppm) et peu contaminé en Th < 5% U par comparaison avec des étalons en équilibre radioactif. - Une nouvelle méthode de datation par dosimétrie RPE comparative a été appliquée sur l'émail dentaire de mammifères fossiles. Cette méthode semble pouvoir être utilisée de ~ 0,1 à plus de 10 Ma. - Application à la Caune de l'Arago (Tautavel, France) : L'âge - Ionium de la formation supérieure - 120 ka (10%) - indique une mise en place pendant la fin du Riss. La formation intermédiaire contaminée (Th/u ~ 50%) n'a pu être datée. - L'âge - RPE de l'émail de EQUUS mosbachensis est : - 400 ka (10%) pour le sol G - associé à H. erectus Arago XXI _ - 600 ka (10%) pour le sol Q - ~ 1 m. au-dessus de la formation inférieure dont l'âge - Ionium est plus ancien que 350 ka.

第23回名古屋大学年代測定総合研究センターシンポジウム平成22(2010)年度報告

Objective of this project was the study of basic interaction and migration processes of actinides in the environment in presence of humic acids (HA). To obtain more basic knowledge on these interaction processes synthetic HA with specific functional properties as well as 14C-labeled HA were synthesized and applied in comparison to the natural HA Aldrich. One focus of the work was on the synthesis of HA with distinct redox functionalities. The obtained synthetic products that are characterized by significantly higher Fe(III) redox capacities than Aldrich HA were applied to study the redox properties of HA and the redox stability of U(VI) humate complexes. It was confirmed that phenolic OH groups play an important role for the redox properties of HA. However, the results indicate that there are also other processes than the single oxidation of phenolic OH groups and/or other functional groups contributing to the redox behavior of HA. A first direct-spectroscopic proof for the reduction of U(VI) by synthetic HA with distinct redox functionality was obtained. The complexation behavior of synthetic and natural HA with actinides (Th, Np, Pu) was studied. Structural parameters of Pu(III), Th(IV), Np(IV) and Np(V) humates were determined by X-ray absorption spectroscopy (XAS). The results show that carboxylate groups dominate the interaction between HA and actinide ions. These are predominant monodentately bound. The influence of phenolic OH groups on the Np(V) complexation by HA was studied with modified HA (blocked phenolic OH groups). The blocking of phenolic OH groups induces a decrease of the number of maximal available complexing sites of HA, whereas complex stability constant and Np(V) near-neighbor surrounding are not affected. The effects of HA on the sorption and migration behavior of actinides was studied in batch and column experiments. Th(IV) sorption onto quartz and Np(V) sorption onto granite and its mineral constituents are affected by the pH value and the presence of HA. HA exhibits a significant influence on the transport of U(IV) and U(VI) in a laboratory quartz sand system. In order to provide the basis for a more reliable modeling of the actinide transport, the metal ion complexation with HA has to be integrated into existing geochemical speciation codes. Within this project the metal ion charge neutralization model was embedded into the geochemical modeling code EQ3/6. In addition to that, a digital data base was developed which covers HA complexation data basing on the charge neutralization model.

The present knowledge of angular distributions of neutron-induced fission is limited to a maximal energy of 15 MeV, with large discrepancies around 14 MeV. Only 238U and 232Th have been investigated up to 100 MeV in a single experiment. The n_TOF Collaboration performed the fission cross section measurement of several actinides (232Th, 235U, 238U, 234U, 237Np) at the n_TOF facility using an experimental set-up made of Parallel Plate Avalanche Counters (PPAC), extending the energy domain of the incident neutron above hundreds of MeV. The method based on the detection of the 2 fragments in coincidence allowed to clearly disentangle the fission reactions among other types of reactions occurring in the spallation domain. I will show the methods we used to reconstruct the full angular resolution by the tracking of fission fragments. Below 10 MeV our results are consistent with existing data. For example in the case of 232Th, below 10 MeV the results show clearly the variation occurring at the first (1 MeV) and second (7 MeV) chance fission, corresponding to transition states of given J and K (total spin and its projection on the fission axis), and a much more accurate energy dependence at the 3rd chance threshold (14 MeV) has been obtained. In the spallation domain, above 30 MeV we confirm the high anisotropy revealed in 232Th by the single existing data set. I'll discuss the implications of this finding, related to the low anisotropy exhibited in proton-induced fission. I also explore the critical experiments which is valuable checks of nuclear data. The 237Np neutron-induced fission cross section has recently been measured in a large energy range (from eV to GeV) at the n TOF facility at CERN. When compared to previous measurements, the n TOF fission cross section appears to be higher by 5-7 % beyond the fission threshold. To check the relevance of n TOF data, we simulate a criticality experiment performed at Los Alamos with a 6 kg sphere of 237Np. This sphere was surrounded by enriched uranium 235U so as to approach criticality with fast neutrons. The simulation predicts a multiplication factor keff in better agreement with the experiment (the deviation of 750 pcm is reduced to 250 pcm) when we replace the ENDF/B- VII.0 evaluation of the 237Np fission cross section by the n TOF data. We also explore the hypothesis of deficiencies of the inelastic cross section in 235U which has been invoked by some authors to explain the deviation of 750 pcm. The large distortion that should be applied to the inelastic cross sections in order to reconcile the critical experiment with its simulation is incompatible with existing measurements. Also we show that the nubar of 237Np can hardly be incriminated because of the high accuracy of the existing data. Fission rate ratios or averaged fission cross sections measured in several fast neutron fields seem to give contradictory results on the validation of the 237Np cross section but at least one of the benchmark experiments, where the active deposits have been well calibrated for the number of atoms, favors the n TOF data set. These outcomes support the hypothesis of a higher fission cross section of 237Np.

The predominant nuclear fuel used globally at present is uranium which is a finite resource. Thorium has been identified as an alternative nuclear fuel source that can be utilized in almost all existing uranium–based reactors and can significantly help in conserving limited uranium reserves. Furthermore, the elimination of proliferation risks associated with thorium–based fuel cycles is a key reason for re–evaluating the possible utilization of thorium in high temperature reactors. In addition to the many advantages that thorium–based fuel has over uranium–based fuel, there are vast thorium resources in the earth's crust that up until the present have not been exploited optimally. This study focuses on determining the amount of uranium ore that can be saved using thorium as a nuclear fuel in HTR's. Four identical 200 MWth high temperature reactors are considered which make use of different fuel cycles. These fuel cycles range from the conventional uranium fuel cycle to a thorium–based fuel cycle in which no U–238 is present and have been simulated using the VSOP–A system of computer codes. This study also considers the effect that protactinium, an isotope that occurs in thorium–based fuel cycles, will have on the decay heat production in the case of a depressurized loss of coolant (DLOFC) accident. / Thesis (M.Ing. (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2011.

The predominant nuclear fuel used globally at present is uranium which is a finite resource. Thorium has been identified as an alternative nuclear fuel source that can be utilized in almost all existing uranium–based reactors and can significantly help in conserving limited uranium reserves. Furthermore, the elimination of proliferation risks associated with thorium–based fuel cycles is a key reason for re–evaluating the possible utilization of thorium in high temperature reactors. In addition to the many advantages that thorium–based fuel has over uranium–based fuel, there are vast thorium resources in the earth's crust that up until the present have not been exploited optimally. This study focuses on determining the amount of uranium ore that can be saved using thorium as a nuclear fuel in HTR's. Four identical 200 MWth high temperature reactors are considered which make use of different fuel cycles. These fuel cycles range from the conventional uranium fuel cycle to a thorium–based fuel cycle in which no U–238 is present and have been simulated using the VSOP–A system of computer codes. This study also considers the effect that protactinium, an isotope that occurs in thorium–based fuel cycles, will have on the decay heat production in the case of a depressurized loss of coolant (DLOFC) accident. / Thesis (M.Ing. (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2011.