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Medimos a seção de choque de fotofissão do 238U entre 200 e 1200 MeV, utilizando um feixe de fótons monocromáticos formados a partir da radiação de Bremsstrahlung dos elétrons armazenados no síncrotron Adone, em Frascati (Itália). Verificamos que para este núcleo, nesta faixa de energias, as seções de choque de fotofissâo e de fotoabsorção podem ser consideradas iguais, dentro dos erros experimentais. Comparando a seção de choque de fotoabsorção do urânio com a de outros núcleos, medidas também por nós em Frascati, verificamos que não há indícios do efeito de sombreamento até 1200 MeV. Por outro lado, comparando os nossos resultados com a seção de choque de fotoabsorção do próton na mesma faixa de energia, concluímos que as ressonâncias nucleônicas a energias superiores à da delta, notadamente as ressonâncias D13 e F15, são fortemente amortecidas nos núcleos complexos. Introduzimos um modelo fenomenológico a fim de descrever os nossos dados experimentais, obtendo resultados muito satisfatórios. / We have measured the 238U photofission cross section between 200 and 1200 MeV using a Bremsstrahlung monochromatic photon beam in the Adone facilities, at Frascati (Italy). For this nucleus, we have verified that, at the energy range considered here, the photofission and photoabsorption cross sections can be considered as being identical. From the comparison of the uranium photoabsorption cross section with that one for other nuclei, also measured in Frascati, we verified that there is no evidence of the shadowing effect up to 1200 MeV. On the other hand, by comparing our results with the próton photoabsorption cross section in the same energy range, we concluded that there is an strong damping of the nucleonic resonances in the D13 and F15 region. We introduced a fenomenologic model to describe our experimental data, obtaining very satisfatory results.

Nosso objetivo e estudar os principais mecanismos de foto absorção no ANTPOT.232 TH entre 7 e 60 Mev, ressonâncias gigantes e mecanismo do quase-deuteron, associados ao decaimento por fissão. Para isso, fizemos medidas da seção de choque de eletrofissão no ANTPOT.232 TH, entre as energias de 7 a 60 Mev, no laboratório do acelerador linear do IFUSP. Utilizamos, na analise, o formalismo dos fótons virtuais, que relaciona a seção de choque de fotofissão a seção de choque de eletrofissão. Foi utilizada a seção de choque de fotofissão medida em livermore e calculamos a seção de choque de fotoabsorção e2 (t=0 e t=1), além da seção de choque de fotoabsorção obtida via quase-deuteron. Verificamos que a contribuição predominante para a seção de choque de eletrofissão e a da componente de dipolo elétrico, sendo as demais contribuições (quadrupolo elétrico e modelo modificado do quase-deuteron) uma ordem de grandeza inferior a esta. / Our objective is to study the main photoabsorption mechanisms in 232T]n between 7 and 60 Mev, namely, Giant Resonances and Quasi-Deuteron, associated to fission decay. We performed electrofission measurements at the linear accelerator of IFUSP. In the analysis, the Virtual Photon Formalism, that relates the photofission cross section to the electrofission cross section, was used. In the calculations, the photofission cross section measured at Livermore Laboratory was used. The E2 photoabsorption and quasi-deuteron photoabsorption cross sections were calculated. We concluded that the most important contribution to the electrofission cross section comes from the El- giant resonance component, the other ones (E2 giant resonance component and quasi-deuteron mechanisms) being 1 or 2% of total electrofission cross section.

Primate societies have been classified into discrete categories based on the flexibility of their social organisation. However, due to growing evidence of intra-specific and temporal variation in grouping patterns, it has been suggested that instead, primate societies should be characterised by their relative degree of fission-fusion dynamics, which indicates the extent to which groups vary in spatial cohesion and the temporal variation in the size and composition of parties. While perceived predation risk and food availability are known to be key factors shaping primate societies, it is not clear if fission-fusion dynamics reflect short-term behavioural adaptations to these factors, and if social preferences also influence fission-fusion dynamics. Furthermore, little is known about the impact of fission-fusion dynamics on social relationships. These issues are addressed in this thesis by investigating the grouping patterns and social relationships of two troops (Gamgam and Kwano) of free-ranging olive baboons (Papio& hamadryas & anubis) in Gashaka-Gumti National Park, Nigeria. Grouping patterns were measured through association networks and the temporal variation in party size, party composition, and spatial cohesion, and were related to variations in food availability, predation risk, and habitat use. Variations in patterns of associations and fission-fusion dynamics were found both between troops, and between seasons within troops. As these variations could largely be accounted for by differences in ecology and demography, it seems that fission-fusion dynamics reflect a short-term optimisation of the trade-off between the cost and benefits of group living. The network of associations of the fluid Kwano troop, but not of the cohesive Gamgam troop, was found to be sub-structured in a way that indicates Infanticide avoidance may play an important role in association patterns. Both the frequencies of social behaviours, and the structures of networks based on five types of social interactions, were related to differences in fission-fusion dynamics. The degree of fission-fusion dynamics appears to influence social relationships, as a quantitative difference in social behaviour was linked to variation in fission-fusion dynamics.

Uncertainties in nuclear model responses must be quantified to define safety limits, minimize costs and define operational conditions in design. Response uncertainties can also be used to provide a feedback on the quality and reliability of parameter evaluations, such as nuclear data. The uncertainties of the predictive model responses sprout from several sources, e.g. nuclear data, model approximations, numerical solvers, influence of random variables. It was proved that the largest quantifiable sources of uncertainty in nuclear models, such as neutronics and burnup calculations, are the nuclear data, which are provided as evaluated best estimates and uncertainties/covariances in data libraries. Nuclear data uncertainties and/or covariances must be propagated to the model responses with dedicated uncertainty propagation tools. However, most of the nuclear codes for neutronics and burnup models do not have these capabilities and produce best-estimate results without uncertainties. In this work, the nuclear data uncertainty propagation was concentrated on the SCK•CEN code burnup ALEPH-2 and the Monte Carlo N-Particle code MCNP.Two sensitivity analysis procedures, i.e. FSAP and ASAP, based on linear perturbation theory were implemented in ALEPH-2. These routines can propagate nuclear data uncertainties in pure decay models. ASAP and ALEPH-2 were tested and validated against the decay heat and uncertainty quantification for several fission pulses and for the MYRRHA subcritical system. The decay uncertainty is necessary to define the reliability of the decay heat removal systems and prevent overheating and mechanical failure of the reactor components. It was proved that the propagation of independent fission yield and decay data uncertainties can be carried out with ASAP also in neutron irradiation models. Because of the ASAP limitations, the Monte Carlo sampling solver NUDUNA was used to propagate cross section covariances. The applicability constraints of ASAP drove our studies towards the development of a tool that could propagate the uncertainty of any nuclear datum. In addition, the uncertainty propagation tool was supposed to operate with multiple nuclear codes and systems, including non-linear models. The Monte Carlo sampling code SANDY was developed. SANDY is independent of the predictive model, as it only interacts with the nuclear data in input. Nuclear data are sampled from multivariate probability density functions and propagated through the model according to the Monte Carlo sampling theory. Not only can SANDY propagate nuclear data uncertainties and covariances to the model responses, but it is also able to identify the impact of each uncertainty contributor by decomposing the response variance. SANDY was extensively tested against integral parameters and was used to quantify the neutron multiplication factor uncertainty of the VENUS-F reactor.Further uncertainty propagation studies were carried out for the burnup models of light water reactor benchmarks. Our studies identified fission yields as the largest source of uncertainty for the nuclide density evolution curves of several fission products. However, the current data libraries provide evaluated fission yields and uncertainties devoid of covariance matrices. The lack of fission yield covariance information does not comply with the conservation equations that apply to a fission model, and generates inconsistency in the nuclear data. In this work, we generated fission yield covariance matrices using a generalised least-square method and a set of physical constraints. The fission yield covariance matrices solve the inconsistency in the nuclear data libraries and reduce the role of the fission yields in the uncertainty quantification of burnup models responses. / Doctorat en Sciences de l'ingénieur et technologie / info:eu-repo/semantics/nonPublished

It is difficult to underestimate the importance of neutron cross section standards in the nuclear data field. Accurate and precise standards are prerequisites for measuring neutron cross sections. Two different projects are presented here with the aim of improving on neutron standards. A simulation study was performed for an experiment intended to measure the cross sections of H(n,n), 235U(n,f), and 238U(n,f) relative to each other. It gave the first estimates of the performance of the experimental setup. Its results have aided the development of the experimental setup by setting limits on the target and detector design. A second neutron-standard project resulted in three measurements of 6Li(n,α)t relative to 235U(n,f). Each subsequent measurement improved upon the previous one and changed the experimental setup accordingly. Although, preliminary cross sections were agreeing well with evaluated data files in some energy intervals, the main goal to measure the cross section up to 3 MeV was not reached. Mass yields and energy spectra are important outcomes of many fission experiments, but in low yield regions the uncertainties are still high even for recurrently studied nuclei. In order to understand the fission dynamics, one also needs correlated fission data. One particular important property is the distribution of excitation energy between the two nascent fission fragments. It is closely connected to the prompt emission of neutrons and γ’s and reveals information about how nucleons and energy are transferred within the fissioning nucleus. By measuring both the pre and post neutron-emission fragment masses, the cumbrance of detecting neutrons directly is overcome. This is done using the fission spectrometer VERDI and the 2E-2v method. In this work I describe how both the spectrometer, the analysis method, and the calibration procedures have been further developed. Preliminary experimental data show the great potential of VERDI, but also areas that call for more attention. A previously overlooked consequence of a central assumption was found and a correction method is proposed that can correct previously obtained data as well. The last part of this thesis concerns the efficiencies of the fission product extraction at the IGISOL facility. The methodology of the fission yield measurements at IGISOL are reliant on assumptions that have not been systematically investigated. The presented work is a first step of such an investigation that can also be used as a tool for optimising the setup for measurements of exotic nuclei. A simulation framework connecting three different simulation codes was developed to investigate the produced yield of fission products in a buffer gas. Several different variants of the setup were simulated and the findings were generally accordant with previous estimates. A reasonable agreement between experimental data and the simulation results is demonstrated.

Master of Science / Department of Geology / Mary Hubbard / The southern Sawatch Range of the Southern Rocky Mountains of south-central Colorado is composed of Precambrian crystalline igneous and metamorphic rocks that have undergone at least three major mountain building events during the Phanerozoic, the Ancestral Rockies Orogeny, the Laramide Orogeny, and Rio Grande rifting. In order to determine how the ancient basement structures might have influenced later episodes of deformation, a small area of basement terrain was mapped along the western margin of the Poncha Pass transfer zone between the San Luis and Upper Arkansas basins in the northern Rio Grande rift. The two dominant rock types in the map area, (hornblendic) amphibolite gneiss and (felsic) quartzofeldspathic gneiss, may represent interlayered metabasalt/metadiorite and metarhyolite/metagranite, with lenses of exotic lithologies throughout. Metamorphic foliations were found to be oriented predominantly N35ºW 47ºNE and to have had an influence on younger brittle structures related to the rifting episode. Lineations and fractures in the gneissic fabric also are parallel to brittle deformation structures. Apatite Fission-Track (AFT) analysis provided a means of determining when this crust was exhumed and cooled by the removal of overburden in response to erosion and/or tectonics. The resultant AFT age distribution revealed that exhumation occurred at the higher elevations during the Laramide orogeny (~299-46 Ma), and at lower elevations during Rio Grande rifting (~29-19 Ma). Although it is commonly thought that these mountains were exhumed during the rifting episode, the results of this study indicate that older events played a significant role in the exhumation.

Master of Science / Department of Mechanical and Nuclear Engineering / Douglas S. McGregor / Fission chambers are ideal neutron flux surveillance instruments to ensure nuclear reactor control and safety. They can provide online, in-core, real-time measurements covering the dynamic range of neutron flux including pulse, Campbell, and current mode over decades of reactor operation cycles. The first patented fission chamber was developed by Baer et al. in 1957. It was a cylindrical assembly thermal fission counter having sensitivity of 0.7 count/neutron cm⁻² for a background measurement of 5 counts/second with ability to operate at a temperature range of 20-80 ºC [3]. Since then, fission chamber technology was developed to come up with miniature and sub-miniature dimensions withstanding high irradiation and high temperature environment making them suitable for in-core online diagnosis. Since the introduction of high temperature fission chamber technology starting in the 1970’s, the need of the advancement in modeling of the fission chambers to improve their performance has become important. The development of modeling depends upon the understanding and consideration of underlying physics of these detectors. The validation of modeling of fission chambers will need the quantification of uncertainty introduced at every stage from neutron-deposit interaction to signal shaping. Based on this objective, a detailed review was performed on fission chamber modeling and simulation covering neutron flux self-shielding, fissile deposit evolution, fission product emission, auto-absorption, electron-ion pair creation, charge recombination and avalanche, space charge effect, charge transport, propagation of electronic pulse and pulse shaping. The analytical methods, algorithmic treatments, simulation, and computation codes used so far in case of modeling different aspects of fission chambers were reviewed. Along with the numerical methods and computer codes for simulating electron drift and charge transport for the usual gas chamber detectors, the use of several fissile material evolution techniques and computation codes were observed in case of fission chamber modeling. The use higher order statistics to handle fluctuation mode and to treat noisy data were observed. In recent years, fission chamber modeling made reasonable improvement in detail physics modeling. Several analytical methods like advanced statistics for Campbellng mode and electric field distortion due to space charge effect need to be incorporated in computation codes. More progress in the areas of evolution of gas behavior, consideration of Penning, recombination, and avalanche effect still needed.