Le dioxyde d'uranium UO2 est le combustible nucléaire standard des réacteurs à eau pressurisée. Durant le fonctionnement du réacteur, la fission de l'uranium produit une grande variété de produits de fission (PF) dont le ralentissement dans la matrice crée un nombre important de défauts ponctuels. Les défauts ponctuels et les PF gouvernent en retour l'évolution des propriétés physiques du combustible sous irradiation. Dans cette étude,nous utilisons les calculs de structure électronique afin de mieux comprendre le comportement sous irradiation du combustible UO2. Nous nous intéressons en particulier au comportement des défauts ponctuels ainsi qu'à la stabilité de trois PF volatils : iode, krypton et xénon. Afin de rendre compte des fortes corrélations électroniques des électrons 5f de l'uranium dans UO2, nous utilisons l'approximation DFT+U, basée sur la théorie de la fonctionnelle de la densité. Cependant, cette approximation crée un nombre important d'états métastables dans lesquels les systèmes peuvent rester piégés et qui sont à l'origine des dispersions observées dans la littérature.Pour résoudre ces problèmes, nous utilisons une méthode basée sur le contrôle des occupations électroniques des orbitales corrélées afin de systématiquement approcher le plus possible l'état fondamental des systèmes étudiés.Nous montrons que l'approximation DFT+U, utilisée en contrôlant les occupations électroniques, permet d'une part de décrire précisément le comportement des défauts ponctuels et des PF dans UO2, d'autre part de fournir des informations quantitatives quant aux propriétés de transport des défauts ponctuels dans le combustible oxyde. / Uranium dioxide UO2 is the standard nuclear fuel used in pressurized water reactors. During in-reactoroperation, the fission of uranium atoms yields a wide variery of fission products (FP) which create numerouspoint defects while slowing down in the material. Point defects and FP govern in turn the evolution of the fuelphysical properties under irradiation. In this study, we use electronic structure calculations in order to betterunderstand the fuel behavior under irradiation. In particular, we investigate point defect behavior, as well as thestability of three volatile FP: iodine, krypton and xenon. In order to take into account the strong correlations ofuranium 5f electrons in UO2, we use the DFT+U approximation, based on the density functional theory. Thisapproximation, however, creates numerous metastable states which trap the system and induce discrepanciesin the results reported in the literature. To solve this issue and to ensure the ground state is systematicallyapproached as much as possible, we use a method based on electronic occupancy control of the correlated orbitals.We show that the DFT+U approximation, when used with electronic occupancy control, can describe accuratelypoint defect and fission product behavior in UO2 and provide quantitative information regarding point defecttransport properties in the oxide fuel.

The interval between meiotic nuclear divisions can be regarded as a modified mitotic cell cycle where DNA replication is blocked. Mechanisms regulating this critical aspect of meiosis that allows haploid cells to be generated from a diploid progenitor were investigated in this project. Licensing is restricted after meiosis I due to down-regulation of Cdc18 and Cdt1. Late meiotic expression of Cdc18 and Cdt1, which load the MCM helicase onto replication origins, can lead to partial DNA replication after meiosis I. This implies that block to initiation via licensing forms an important component of this regulation. As detecting any minor DNA re-replication after meiosis I requires a technique more sensitive than flow cytometry for detection of total cell DNA contents, I also investigated a procedure to allow incorporation and detection of 5-ethynyl-2'-deoxyuridine (EdU) in fission yeast. Additional inactivation of Spd1 or stabilization of Dfp1 after MI when Cdc18 and Cdt1 are also expressed does not enhance re-replication, but cyclin-dependent kinase Cdc2 plays a role in preventing re-replication during the MI-MII interval. Unexpectedly, when the licensing block is subverted, replication forks only move a short distance in the interval between meiosis I and II, implying that the elongation step of DNA replication is also inefficient. In addition, I show that the regulation of entry into meiosis II is not delayed by a partial round of DNA replication or DNA damage, indicating that replication and DNA damage checkpoints do not operate in late meiosis.

This thesis investigates the patterning of the Algonquian “central agreement”, i.e. the primary person-number agreement marking, from a diachronic and comparative perspective. The central agreement patterns differ in the two orders: in the conjunct it is fusional and often portmanteau while in the independent it is discontinuous and non-portmanteau. In addition to these differences, there are also some commonalities, such as a pattern in which 1p consistently outranks 2p in both orders. This thesis shows that the differences between the two orders can be taken to reflect variation in the features of the syntactic probe and different morphological spell-out rules, while the shared properties follow from the underlying structure of φ-features. In particular, it is proposed that an additional person feature under the [plural] node causes first person plural to be privileged over second person plural in the competition among vocabulary items in post-syntactic spellout. / October 2016

Les réacteurs actuels produisent deux types de déchets dont la gestion et le devenir soulèvent des problèmes. Il s’agit d’abord de certains produits de fission et de noyaux lourds (isotopes de l’Américium et du Curium) au-delà de l’uranium appelés actinides mineurs. Deux options sont envisagées : le stockage en site géologique profond et/ou l’incinération de ces déchets dans un flux de neutrons rapides, c’est-à-dire, la transmutation par fission. Ces études font appel à de nombreuses données neutroniques. Malheureusement, les bases de données présentent encore de nombreuses insuffisances pour parvenir à des résultats fiables. L’objectif de ce travail est ici d’actualiser des données nucléaires et de les compléter. Nous avons ainsi mesuré la section efficace de fission de l’243Am (7370 ans) en référence à la diffusion élastique (n,p) afin de fournir des données indépendantes des mesures existantes dans la gamme des neutrons rapides (1 - 8 MeV). La réaction 243Am(n,f) a été analysée en utilisant un modèle statistique décrivant les voies de désexcitation du noyau composé d’244Am. Ainsi les sections efficaces de capture radiative (n,?) et de diffusion inélastique (n,n’) ont pu être évaluées. La mesure directe des sections efficaces neutroniques d’actinides mineurs constitue très souvent un véritable défi compte tenu de la forte activité des actinides mineurs. Pour cela, une méthode indirecte a été développée utilisant les réactions de transfert dans le but d’étudier certains isotopes du curium. Les réactions 243Am(3He,d)244Cm, 243Am(3He,t)243Cm et 243Am(3He,alpha)242Am nous ont permis de mesurer les probabilités de fission des noyaux de 243,244Cm et de l’242Am. Les sections efficaces de fission des curiums 242,243Cm(162,9 j, 28,5 ans) et de l’américium 241Am sont obtenues en multipliant ces probabilités par les sections efficaces calculées de formation des noyaux composés. Pour chaque mesure, une évaluation précise des erreurs a été réalisée à travers une étude des variances-covariances des résultats présentés. Pour les mesures de la réaction 243Am(n,f), une analyse des corrélations d’erreurs a permis d’interpréter la portée de ces mesures au sein des mesures existantes. / The existing reactors produce two kinds of nuclear waste : the fission products and heavy nuclei beyond uranium called minor actinides (Americium and Curium isotopes). Two options are considered: storage in deep geological site and/or transmutation by fast neutron induced fission. These studies involve many neutron data. Unfortunately, these data bases have still many shortcomings to achieve reliable results. The aim of these measurements is to update nuclear data and complement them. We have measured the fission cross section of 243Am (7370y) in reference to the (n,p) elastic scattering to provide new data in a range of fast neutrons (1 - 8 MeV). A statistical model has been developed to describe the reaction 243Am(n,f). Moreover, the cross sections from the following reactions have been be extracted from these calculations: inelastic scattering 243Am(n,n’) and radiative capture 243Am(n,?) cross sections. The direct measurements of neutron cross sections are often a challenge considering the short half-lives of minor actinides. To overcome this problem, a surrogate method using transfer reactions has been used to study few isotopes of curium. The reactions 243Am(3He, d)244cm, 243Am(3He, t)243cm and 243Am(3He, alpha)242Am allowed to measure the fission probabilities of 243,244Cm and 242Am. The fission cross sections of 242,243Cm(162,9d, 28,5y) and 241Am(431y) have been obtained by multiplying these fission probabilities by the calculated compound nuclear neutron cross section relative to each channel. For each measurement, an accurate assessment of the errors was realized through variance-covariance studies. For measurements of the reaction 243Am(n,f), the analysis of error correlations allowed to interpret the scope of these measures within the existing measurements.

Doctor of Philosophy / Department of Mechanical and Nuclear Engineering / Douglas S. McGregor / A Micro-Pocket Fission Detector (MPFD) is a miniaturized type of fission chamber developed for use inside a nuclear reactor. Their unique design allows them to be located between or even inside fuel pins while being built from materials which give them an operational lifetime comparable to or exceeding the life of the fuel. While other types of neutron detectors have been made for use inside a nuclear reactor, the MPFD is the first neutron detector which can survive sustained use inside a nuclear reactor while providing a real-time measurement of the neutron flux. This dissertation covers the deployment of MPFDs as a large three-dimensional array inside the Kansas State University TRIGA Mark-II Nuclear Reactor for real-time neutron flux measurements. This entails advancements in the design, construction, and packaging of the Micro-Pocket Fission Detector Triads with incorporated Thermocouple, or MPFD[superscript]3-T. Specialized electronics and software also had to be designed and built in order to make a functional system capable of collecting real-time data from up to 60 MPFD[superscript]3-Ts, or 180 individual MPFDs and 60 thermocouples. Design of the electronics required the development of detailed simulations and analysis for determining the theoretical response of the detectors and determination of their size. The results of this research shows that MPFDs can operate for extended times inside a nuclear reactor and can be utilized toward the use as distributed neutron detector arrays for advanced reactor control systems and power mapping. These functions are critical for continued gains in efficiency of nuclear power reactors while also improving safety through relatively inexpensive redundancy.

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.

Thesis advisor: Charles S. Hoffman / In this thesis, I describe the development of a screening platform for detecting PDE8A inhibitors using the cAMP-dependent glucose sensing pathway of the fission yeast Schizosaccharomyces pombe, which led us to discover several PDE8A selective inhibitors. In this system, the only PDE of the fission yeast is replaced with mammalian PDE8A1 in strains that have been engineered such that PDE inhibition is required to allow cell growth. Using this system, I screened 56 compounds obtained from PDE4 and PDE7 high throughput screens (HTSs) and identified a PDE4-PDE8 dual specificity inhibitor. Using this as a positive control, I developed a robust high-throughput screen (HTS) for PDE8A inhibitors and screened 240,267 compounds at the Harvard Medical School ICCB Screening Facility. Approximately 0.2 % of the screened compounds were potential PDE8A inhibitors with 0.03% displaying significant potency. Secondary assays of 367 of the most effective compounds against strains expressing PDE8A (both full length and catalytic domain), PDE4A and PDE7A or PDE7B led to the selection of structurally diverse compounds for further testing. To profile the selectivity of twenty-eight of these compounds, dose response assays were conducted using 16 yeast strains that express different PDE isoforms (representing all PDE families with the exception of the PDE6 family). These assays identified compounds with different patterns of inhibition, including structurally-distinct PDE8A-specific inhibitors. By evaluating the effects of these compounds for steroid production in mouse Leydig cells, biologically active compounds that can elevate steroid production were identified. / Thesis (PhD) — Boston College, 2011. / Submitted to: Boston College. Graduate School of Arts and Sciences. / Discipline: Biology.

Este trabalho é dedicado ao estudo de reações de fissão de núcleos pesados induzidas por fótons e prótons a energias intermediárias e altas, fazendo uso, para tanto, do código de Monte Carlo CRISP, sendo um trabalho inteiramente computacional. Estudou-se um novo conjunto de parâmetros para a fórmula de massa semi-empírica proposta por Pearson em seu trabalho de 2001, a partir da qual se passou à simulação de reações de fissão induzidas por fótons dos núcleos 208Pb, 232Th, 237Np e 238U, e fissão induzida por prótons nos núcleos 197Au, 208Pb, 237Np e 241Am. Os modelos de Bohr e Wheeler para fissão, de 1939, e o modelo de Weisskopf para emissão de partículas de 1937 foram empregados na simulação. Para os parâmetros de densidade de níveis, um conjunto de parâmetros foi obtido para as fórmulas empíricas de Dostrovsky de 1958 e para a razão de fissão. Foram calculadas seções de choque de fotofissão para os núcleos 208Pb, 232Th, 237Np e 238U, produtos de reações de spallation induzidas por prótons nos núcleos 208Pb e 197Au, e distribuições de massa dos fragmentos de fissão em reações de Bremsstrahlung com o 238U e em reações induzidas por prótons com os núcleos 197Au, 208Pb, 237Np e 241Am. São apresentadas comparações a dados experimentais de todos os cálculos realizados. Também se obteve um modelo para aproximar os valores de barreira de fissão obtidos pelo método ETFSI (Extended Thomas-Fermi plus Strutinsky Integral). / This work is dedicated to the study of heavy nuclei fission induced by intermediate- and high-energy photons and protons, by using to this end the Monte Carlo code CRISP, therefore being an entirely computacional work. A new set of parameters for the 2001 semi-empirical mass formula proposed by Pearson is studied. Then we simulate fission reactions induced by photons and protons on 208Pb, 232Th, 237Np and 238U, and fission induced by protons on 197Au, 208Pb, 237Np e 241Am. The Bohr-Wheeler model for describing the fission process and the Weisskopf model for the emission probability of particles were used to perform the calculation. Regarding the level density parameters, a set of parameters is presented for the empirical formulas of Dostrovsky and for the fission ratio. This work also presents calculated fotofission cross section for induced reactions on 208Pb, 232Th, 237Np and 238U nuclei, spallation products of proton induced reactions on 208Pb and 197Au, and fragment mass distributions of Bremsstrahlung reactions with 238U and of proton induced reactions on 197Au, 208Pb, 237Np and 241Am. Comparisons to experimental data are shown for all calculations. A model to aproximate the fission barrier values obtaind by the ETFSI - Extended Thomas-Fermi plus Strutinsky Integral method is also presented.

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.

In this project, we have successfully joined MA956 Oxide Dispersion-Strengthened (ODS) steel plates using Friction Stir Welding (FSW). ODS steels are prime candidate materials for the fuel cladding in Generation IV nuclear fission reactors and as first wall components in nuclear fusion reactors. This is due to their exhibiting excellent high temperature strength and creep behaviour, together with enhanced resistance to radiationinduced void swelling. ODS steels are heavily reliant on a fine dispersion of (Y-Al-O) nanooxide particles to provide the aforementioned properties. This, however, makes ODS steels particularly problematic to join. Most joining techniques melt the material along the joint line, but this would severely alter or deplete the nano-oxide dispersion and hence be highly detrimental to the material’s performance in a nuclear environment. FSW is a solid-state joining technique, and therefore can join ODS steel without melting the material. Although FSW can potentially alter the microstructure of the base material and affect the distribution of nano-oxide particles, if a sufficient number of nano-sized particles and a sufficiently homogeneous dispersion remain after the welding process, then a major roadblock for the implementation of ODS steels will have been removed. The research of this thesis focused on the impact of FSW on: i) the microstructure, ii) the mechanical properties, iii) the residual stresses, and iv) the abnormal grain growth behaviour of ODS steels; utilizing a wide array of techniques to assess the micro-to-nano scale structure and the properties of the base material and welds, including optical, scanning and transmission and electron microscopy, X-ray and neutron diffraction, small-angle neutron scattering, tensile testing and micro-hardness measurements. We also produced welds with systematic changes to the tool traverse speed and rotation speed to investigate the impact of changing the welding parameters on the weld microstructure, and therefore optimise the process parameters for enhanced radiation and mechanical performance of the ODS steel welds.