Made available in DSpace on 2014-10-09T12:53:13Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:09:34Z (GMT). No. of bitstreams: 1 11664.pdf: 905420 bytes, checksum: 20644e6d8e90a917c6c5df56691bdf5d (MD5) / Dissertacao (Mestrado) / IEA/D / Instituto de Energia Atomica - IEA

The fission product releases from spherical fuel elements used in modern high temperature gas cooled reactors are one of the first source terms used in describing the safety of planned nuclear plants during normal and accident conditions. The verification and validation of the model and code used to predict the gaseous fission product behaviour and release from spherical fuel elements for the PBMR were documented in this dissertation. The PBMR is the latest design in high temperature gas cooled reactor technology utilizing spherical fuel elements based on the LEU TRISO-coated particle design. Fission products can be divided into relatively short-lived noble gas and halogens, and relatively long-lived metallic fission and activation products. Each group is described by its own models and sets of transport parameters. The noble gases and halogen fission product releases from the fuel elements are direct indications of fuel performance and are modelled by the Booth equation. The fission product release legacy code NOBLEG for noble gases and halogens was developed previously to calculate this diffusion model for high temperature reactors. The model and code are verified and validated for use in PBMR design and analyses under normal operating conditions. The history of irradiation experiments conducted on coated fuel particles and spherical fuel elements was investigated, and the most suitable irradiation tests with their post irradiation investigations were identified for the purpose of validation of the model and code. The model used to determine gaseous fission product behaviour and release from spherical fuel elements is described in detail. The application of this model in the code is verified mathematically with the Booth model, and by inspection of the source code. The thermohydraulic model used by NOBLEG to calculate fuel temperatures is verified with code to code comparisons with the core neutronics code VSOP. The irradiation tests HFR-K5 and -K6 were selected to validate the gaseous fission product code NOBLEG. An investigation was done into the development of NOBLEG to calculate gaseous fission product release under oxidizing conditions caused by water ingress events. New relationships were derived from water vapour injection tests done during the irradiation experiment HFR-K6, that allows NOBLEG to estimate the increase in gaseous fission product release under oxidizing conditions. A new model was proposed to explain peculiarities observed during the water injection tests. / Prof. P.P. Coetzee

Uplift of the Al Hajar Mountains in Oman has been related to either Late Cretaceous ophiolite obduction or the Neogene Zagros collision. To test these hypotheses, the cooling of the central Al Hajar Mountains is constrained by 10 apatite (U-Th)/He (AHe), 15 fission track (AFT), and four zircon (U-Th)/He (ZHe) sample ages. These data show differential cooling between the two major structural culminations of the mountains. In the 3km high Jabal Akhdar culmination AHe single-grain ages range between 392 Ma and 101 Ma (2 sigma errors), AFT ages range from 518 Ma to 324 Ma, and ZHe single-grain ages range from 62 +/- 3Ma to 39 +/- 2 Ma. In the 2 km high Saih Hatat culmination AHe ages range from 26 +/- 4 to 12 +/- 4 Ma, AFT ages from 73 +/- 19Ma to 57 +/- 8 Ma, and ZHe single-grain ages from 81 +/- 4 Ma to 58 +/- 3 Ma. Thermal modeling demonstrates that cooling associated with uplift and erosion initiated at 40 Ma, indicating that uplift occurred 30 Myr after ophiolite obduction and at least 10 Myr before the Zagros collision. Therefore, this uplift cannot be related to either event. We propose that crustal thickening supporting the topography of the Al Hajar Mountains was caused by a slowdown of Makran subduction and that north Oman took up the residual fraction of N-S convergence between Arabia and Eurasia.

La chromatine est le support de l'information génétique tout le long du cycle cellulaire. Elle est soumise à des modifications diverses et rigoureusement coordonnées par les complexes CDK-Cyclines, sous le contrôle de mécanismes de surveillance. En mitose, la kinase Aurora est un acteur clé qui contrôle la ségrégation correcte des chromosomes. Aurora participe à la bi-orientation des centromères, à la condensation des chromosomes et à la cytocinèse. Le dysfonctionnement de cette kinase conduit alors à une instabilité chromosomique et à l'aneuploïdie, un phénotype observé dans la majorité des cancers solides. Les travaux réalisés au cours de cette thèse démontrent un nouveau rôle pour cette kinase dans la dispersion et la disjonction des télomères en mitose chez la levure S. Pombe. La dispersion des télomères s'accompagne en métaphase de la dissociation aux télomères des protéines Swi6/HP1 et cohésine Rad21. Tandis que la disjonction a lieu en anaphase après la phosphorylation de la sous-unité de condensine Cnd2. L'inhibition d'Aurora induit la formation de ponts chromosomiques anaphasiques qui révèle des défauts de séparation des télomères. La délétion d'une protéine spécifique aux télomères, Ccq1, protège la cellule de la formation de ces ponts chromosomiques en favorisant le chargement de la condensine en anaphase malgré l'inhibition d'Aurora. / Chromatin is the support of the genetic information throughout the cell cycle. It is subject to various modifications that occur with precise coordination. This coordination is led by CDK-cyclins under the control of cell cycle checkpoints. In mitosis, correct chromosome segregation is ensured by Aurora kinases. Aurora participates to centromere bi-orientation, chromosome condensation and cytokinesis. A dysfunction in the activity of this kinase leads to chromosomal instability and aneuploidy, phenotypes frequently observed in cancer. The results obtained during this thesis reveal a new function for fission yeast Aurora kinase during mitosis in telomere dispersion and disjunction. Telomere dispersion is triggered in metaphase by the dissociation of Swi6/HP1 and cohesion Rad21 from telomeres. Then, during anaphase, the phosphorylation of the condensin subunit Cnd2 is required for telomere disjunction. Aurora inhibition leads to anaphase chromosome bridges with unseparated telomeres. Deletion of a specific telomeric protein, Ccq1, prevents the formation of anaphase chromosome bridges by favoring condensin loading despite Aurora inhibition.

Consistent leadership of group travel by specific individuals has been documented in many animals. Most species exhibiting this type of leadership have relatively stable group membership. Animals using fission-fusion grouping are not expected to use specific leaders because associations would not be frequent. Certain conditions, however, may allow this type of control over group travel to occur. First, a population would need to be small enough to allow regular associations between individuals. Second, leadership may be useful if the environment where the population in question lives is complex and requires learning to access the resources efficiently. To determine whether fission-fusion species existing under these conditions utilize specific individual leadership, I examined a small residential population of bottlenose dolphins (Tursiops truncatus) in the Lower Florida Keys (LFK) where the benthic habitat is highly complex. My goals were to 1) determine whether specific individuals in this population led group travel more often than expected; 2) determine whether certain factors predicted which animals would lead most often and 3) investigate the benefits of leading to leaders and to followers in a fission-fusion society. Multiple types of data were collected to answer questions posed including dolphin behavior (for leadership analyses), fish sampling (to examine dolphin habitat use under leadership), and dolphin biopsy sampling (for genetic analyses). Results of analyses provided strong evidence for consistent leadership in this population. Leaders were female, most were mothers and on average they had larger measures of centrality within the LFK population. Leaders benefited by leading individuals who were more closely related than expected. Followers benefited from efficient access to profitable habitat. Results build on previous leadership research by expanding our knowledge about the type of species in which specific individuals lead and predictors for what types of individuals may lead. Additionally, results provide the first detailed information about benefits group members obtain by both leading and following.

The integration of low-temperature thermochronometers, including apatite and zircon (U-Th)/He (AHe, ZHe) and apatite fission-track (AFT) methods, allows for a quantification of the thermal history experienced by rocks as they heat and cool through upper crustal temperature regimes (<200°C). Whereas these methods are practical in geologic terranes that have undergone rapid cooling, application to strata with protracted cooling histories is complicated by the enhanced role of grain-specific parameters (volume, chemistry, radiation damage) on the kinetics of helium diffusion and fission track annealing. The effects of these variables are most prevalent in sedimentary samples, where natural variance in detrital accessory mineral populations results in a broad range of diffusion kinetics and great dispersion in corresponding cooling dates. This thesis integrates contemporary thermochronometer diffusion and annealing kinetics to investigate the burial and exhumation history of two natural laboratories. In the Mackenzie Mountains and Plain of the Northwest Territories, long-term radiation damage accumulation in zircon from Neoproterozoic siliciclastic units produces ZHe dates that track Albian to Paleocene burial and exhumation in front of the foreland-propagating fold-thrust belt. For the Phanerozoic stratigraphic section, AFT annealing kinetics are calculated from Devonian and Cretaceous samples, and are incorporated into multi-kinetic AFT modeling. These kinetics also constrain AHe date-radiation damage trends, and when combined allow for an estimation on the magnitude of eroded sediment across regional pre-Albian and post-Paleocene unconformities. Finally, conodont (U-Th)/He data from Anticosti Island, Québec in the Gulf of the St. Lawrence are compared with ZHe, AHe and AFT data to test their utility as a thermochronometer for carbonate basin analysis. These data evince a Mesozoic thermal history previously unattributed to the region. Ultimately, this thesis provides a novel assessment on the ways in which thermochronometer date dispersion can be quantified to assess the thermal evolution of sedimentary basins from burial through to inversion.

Doctor of Philosophy / Department of Mechanical and Nuclear Engineering / Douglas S. McGregor / Advancements in nuclear reactor core modeling and computational capability have encouraged further development of in-core neutron sensors. Measurement of the neutron-flux distribution within the reactor core provides a more complete understanding of the operating conditions in the reactor than typical ex-core sensors. Micro-Pocket Fission Detectors (MPFDs) have been developed and tested previously but have been limited to single-node operation and have utilized highly specialized designs. The development of a widely deployable, multi-node MPFD assembly will enhance nuclear research capabilities. In-core neutron flux measurements include many challenges because of the harsh environment within the reactor core. Common methods of in-core neutron measurement are also limited by geometry and other physical constraints. MPFDs are designed to be small and robust while offering a real-time, spatial measurement of neutron flux. Improvements to the MPFD design were developed based on shortcomings of prior research in which many of the theoretical considerations for MPFDs were examined. Fabrication techniques were developed for the preparation of MPFD components and electrodeposition of fissile material. Numerous arrays of MPFDs were constructed for test deployments at the Kansas State University TRIGA Mk. II research nuclear reactor, University of Wisconsin Nuclear Reactor, Transient REActor Test facility at the Idaho National Laboratory (INL), and Advanced Test Reactor at INL. Preliminary testing of a single MPFD sensor at KSU yielded a linear response to reactor power between 10 kWth and 750 kWth and followed both positive and negative reactivity insertions in real-time. A $1.50 reactor pulse was monitored from the Intra-Reflector Irradiation System, located in reflector region of the KSU TRIGA Mk. II core with 1-ms time resolution. Improved multi-node MPFD arrays were then designed, fabricated, and deployed in flux ports between fuel rods and within an iron-wire flux port which was inserted into the central thimble of the KSU TRIGA Mk. II research nuclear reactor. Work continues to develop MPFDs for deployment at research reactors at INL and elsewhere. Results from the MPFD measurements will be useful for future validation of computational modeling and as part of advanced nuclear fuel development efforts.

No description available.

Foi desenvolvido, implementado e testado um formalismo que permite descrever propriedades nucleares em regimes de deformação fora do equilíbrio, utilizando o método Macroscópico-Microscópico em associação com o Método Semimicroscópico Combinado. Esse formalismo foi utilizado para a interpretação e elucidação de alguns problemas abertos como as estruturas na seção de choque de fotofissão do 237.ANTPOT Np, distribuições angulares de fotofissão do 239.ANTPOT. Pu, e a concentração de transições M1 no 237.ANTPOT Np e 239.ANTPOT. Pu em baixas energias. Também, foram interpretadas informações experimentais referentes aos estados isoméricos do 237.ANTPOT Pu e 239.ANTPOT. Pu. Com relação ao potencial preditivo do formalismo, foram identificados os possíveis candidatos (spin e paridade) a estados isoméricos no 241.ANTPOT Np, bem como foi calculada também pela primeira vez a distribuição de momentos de nêutrons para o 239.ANTPOT Np fora da deformação de equilíbrio. / It was developed, implemented and tested a formalism suitable to the description of nuclear properties at non equilibrium deformations regime, by using the Macroscopic-Microscopic method in association with the Combined Semimicroscopic Method. This formalism was used for the interpretation and elucidation of some open problems, as the structures in the 237Np photofission cross section, photofission angular distributions of 239Pu, and the concentrations of low-energy Ml transitions in 237Np and 239Pu. Also, experimental information on 237Pu and 239Pu isomeric states was interpreted. Concerning the prediction potentialities of the formalism, were identified possible candidates (spin and parity) for the 241Pu isomeric states, as well as the 239Pu neutron momentum distributions, at non equilibrium deformation, was also calculated for the first time.

Metal foils were implemented in a measurement of neutron-induced fission at the IGISOL facility in 2016. These foils were activated by a neutron flux during the experiment and measured after the beam was turned off. The radioactive products from the neutron activation were identified in an analysis of γ-ray spectroscopy data. The results were then used to benchmark the neutron flux simulated by MCNPX, which is used for a simulation model of an ion guide that was implemented in the experiment in 2016. The predicted number of neutron activation products were calculated using the simulated neutron flux and compared to results from the experiment. This comparison benchmarked the neutron flux and showed a consistency with the results from a previous study. This is a step in the process to validate the predictive power of the simulation model which is developed for the study of neutron-induced fission.