In this thesis, the design of a high intensity accumulator ring for the European Spallation Source Neutrino Super Beam (ESSnuSB) is considered. The European Spallation Source (ESS) linear accelerator (Linac), presently being constructed in Lund, Sweden, presents an interesting opportunity to also host an experiment to detect neutrino CP violation. 0.7 ms long H- pulses would be accelerated to 2 GeV and collide with a target, producing pions which then decay into neutrinos. To focus the pions a toroidal magnet (''neutrino horn'') is pulsed with a 350 kA current. The peak current is about 5 μs long, which requires the H- pulses to be shortened to about the same length using an accumulator ring that is located between the linac and the target. The H- would be stripped of their electrons using either a thin carbon foil or a laser beam during injection into the ring. Foil stripping is limited by the lifetime of the foil, which depends on the temperature to which it is heated by the beam. The temperature is simulated in a computer model and the results indicate that it does not rise above the critical temperature (2500 K). The high number of protons (1015) circulating in the ring could cause instabilities due to the collective charge of the particles, known as the space charge effect. The space charge tune shift is calculated for the ESSnuSB and different solutions are discussed. The result of a design accumulator lattice for the ESSnuSB, based on the Spallation Neutron Source, at Oak Ridge National Laboratory, Tennessee, U.S., and made using the computer program Methodical Accelerator Design (MAD), is presented.

Neste trabalho apresentamos um estudo das reações nucleares de alta energia que são fundamentais na definição do termo fonte dos reatores nucleares subcríticos acionados por fonte externa. Estas reações nucleares, também conhecidas como \"spallation\", consistem na interação de hádrons de alta energia com os núcleons do núcleo atômico. A fenomenologia destas reações consiste em duas etapas, sendo que à primeira, o próton interage através de espalhamentos múltiplos, em um processo denominado cascata intra-nuclear seguido da etapa na qual o núcleo excitado oriundo da cascata intranuclear ou evapora partículas de forma a atingir estados energéticos moderados ou fissiona, em um processo conhecido como competição entre evaporação e fissão. Neste trabalho os principais modelos nucleares, os modelos de Bertini e Cugnon, são revistos, pois estes modelos são fundamentais para propósito de projeto devido à falta de dados nucleares avaliados para estas reações. A implementação e validação dos métodos de cálculo para o projeto destas fontes são realizadas. A implementação da metodologia é realizada utilizando o programa MCNPX ( \"Monte Carlo N-Particle eXtended\"), dedicado para cálculos de transporte destas partículas e a validação é realizada mediante uma cooperação internacional junto a um projeto coordenado de pesquisa da Agencia Internacional de Energia Atômica e trabalhos disponíveis. O objetivo é qualificar os cálculos relacionados às reações nucleares e os canais de desexcitação envolvidos. O CRISP, um código nacional para a descrição da fenomenologia das reações envolvidas, também foi estudado e os modelos implementados no código foram revistos e melhorados de forma a dar continuidade ao seu processo de qualificação. Devido às limitações dos principais modelos na descrição de produção de nuclídeos leves, a reação de multi-fragmentação foi estudada. As discrepâncias nos cálculos de produção destes nuclídeos são atribuídas à falta do canal de multi-fragmentação estatística do núcleo. A implementação deste canal foi realizada para a aplicação em reações de altas energias junto ao código CRISP de forma a reproduzir a produção de nuclídeos leves, bem como sua validação mediante a comparação com dados experimentais disponíveis para este fenômeno, obtendo com isso uma melhor reprodução de todo o espectro de produção de nuclídeos do processo. / This work presents a study of high energy nuclear reactions which are fundamental to dene the source term in accelerator driven systems. These nuclear reactions, also known as spallation, consist in the interaction of high energetic hadrons with nucleons in the atomic nucleus. The phenomenology of these reactions consist in two step. In the rst, the proton interacts through multiple scattering in a process called intra-nuclear cascade. It is followed by a step in which the excited nucleus, coming from the intranuclear cascade, could either, evaporates particles to achieve a moderate energy state or ssion. This process is known as competition between evaporation and ssion. In this work the main nuclear models, Bertini and Cugnon are reviewed, since these models are fundamental for design purposes of the source term in ADS, due to lack of evaluated nuclear data for these reactions. The implementation and validation of the calculation methods for the design v of the source is carried out to implement the methodology of source design using the program MCNPX (Monte Carlo N-Particle eXtended), devoted to calculation of transport of these particles and the validation performed by an international cooperation together with a Coordinated Research Project (CRP) of the International Atomic Energy Agency and available jobs, in order to qualify the calculations on nuclear reactions and the de-excitation channels involved, providing a state of the art of design and methodology for calculating external sources of spallation for source driven systems. The CRISP, is a brazilian code for the phenomenological description of the reactions involved and the models implemented in the code were reviewed and improved to continue the qualication process. Due to failure of the main models in describing the production of light nuclides, the multifragmentation reaction model was studied. Because the discrepancies in the calculations of production of these nuclides are attributes to the lack of reaction channel and the implementation of this channel was carried out for applications in high energy reactions with the CRISP code to reproduce the production of light nuclides, as well, as its validation by comparison with experimental data available for this phenomenon. Thus, obtaining a better reproduction of the whole spectrum of production of nuclides in the process.

Neste trabalho apresentamos um estudo das reações nucleares de alta energia que são fundamentais na definição do termo fonte dos reatores nucleares subcríticos acionados por fonte externa. Estas reações nucleares, também conhecidas como \"spallation\", consistem na interação de hádrons de alta energia com os núcleons do núcleo atômico. A fenomenologia destas reações consiste em duas etapas, sendo que à primeira, o próton interage através de espalhamentos múltiplos, em um processo denominado cascata intra-nuclear seguido da etapa na qual o núcleo excitado oriundo da cascata intranuclear ou evapora partículas de forma a atingir estados energéticos moderados ou fissiona, em um processo conhecido como competição entre evaporação e fissão. Neste trabalho os principais modelos nucleares, os modelos de Bertini e Cugnon, são revistos, pois estes modelos são fundamentais para propósito de projeto devido à falta de dados nucleares avaliados para estas reações. A implementação e validação dos métodos de cálculo para o projeto destas fontes são realizadas. A implementação da metodologia é realizada utilizando o programa MCNPX ( \"Monte Carlo N-Particle eXtended\"), dedicado para cálculos de transporte destas partículas e a validação é realizada mediante uma cooperação internacional junto a um projeto coordenado de pesquisa da Agencia Internacional de Energia Atômica e trabalhos disponíveis. O objetivo é qualificar os cálculos relacionados às reações nucleares e os canais de desexcitação envolvidos. O CRISP, um código nacional para a descrição da fenomenologia das reações envolvidas, também foi estudado e os modelos implementados no código foram revistos e melhorados de forma a dar continuidade ao seu processo de qualificação. Devido às limitações dos principais modelos na descrição de produção de nuclídeos leves, a reação de multi-fragmentação foi estudada. As discrepâncias nos cálculos de produção destes nuclídeos são atribuídas à falta do canal de multi-fragmentação estatística do núcleo. A implementação deste canal foi realizada para a aplicação em reações de altas energias junto ao código CRISP de forma a reproduzir a produção de nuclídeos leves, bem como sua validação mediante a comparação com dados experimentais disponíveis para este fenômeno, obtendo com isso uma melhor reprodução de todo o espectro de produção de nuclídeos do processo. / This work presents a study of high energy nuclear reactions which are fundamental to dene the source term in accelerator driven systems. These nuclear reactions, also known as spallation, consist in the interaction of high energetic hadrons with nucleons in the atomic nucleus. The phenomenology of these reactions consist in two step. In the rst, the proton interacts through multiple scattering in a process called intra-nuclear cascade. It is followed by a step in which the excited nucleus, coming from the intranuclear cascade, could either, evaporates particles to achieve a moderate energy state or ssion. This process is known as competition between evaporation and ssion. In this work the main nuclear models, Bertini and Cugnon are reviewed, since these models are fundamental for design purposes of the source term in ADS, due to lack of evaluated nuclear data for these reactions. The implementation and validation of the calculation methods for the design v of the source is carried out to implement the methodology of source design using the program MCNPX (Monte Carlo N-Particle eXtended), devoted to calculation of transport of these particles and the validation performed by an international cooperation together with a Coordinated Research Project (CRP) of the International Atomic Energy Agency and available jobs, in order to qualify the calculations on nuclear reactions and the de-excitation channels involved, providing a state of the art of design and methodology for calculating external sources of spallation for source driven systems. The CRISP, is a brazilian code for the phenomenological description of the reactions involved and the models implemented in the code were reviewed and improved to continue the qualication process. Due to failure of the main models in describing the production of light nuclides, the multifragmentation reaction model was studied. Because the discrepancies in the calculations of production of these nuclides are attributes to the lack of reaction channel and the implementation of this channel was carried out for applications in high energy reactions with the CRISP code to reproduce the production of light nuclides, as well, as its validation by comparison with experimental data available for this phenomenon. Thus, obtaining a better reproduction of the whole spectrum of production of nuclides in the process.

Welding of duplex stainless steel pipeline material for the oil and gas industry is now common practice. To date, research has been conducted primarily on the parent material and heat affected zones in terms of its susceptibility to various forms of corrosion. However, there has been little research conducted on the degree of sensitisation of the various successive weld layers, namely the root, fill and cap layers. The focus of this research study was to: (i) provide an in-depth microstructural analysis of the various weld passes, (ii) study the mechanical properties of the weld regions; (iii) determine degree of sensitisation of the various weld passes; and (iv) investigate the residual stress levels within the various regions/ phases of the welds. Four test conditions were prepared using manual Gas Tungsten Arc Welding with 'V' and 'U' bevel configuration. Structural analysis consisted of (i) optical microscopy, scanning electron microscopy and magnetic force microscopy; (ii) ferrite determination using Magna-Gauge, Fischer Ferrite-scope and Point Count method. Mechanical testing consisted of Vickers hardness measurements, Charpy impact studies and transverse tensile testing. The degree of sensitisation was determined by three test methods: a modified ASTM A262, ASTM A923 and a modified Double Loop Electrochemical Potentiodynamic Reactivation (DL-EPR) test. Residual stress levels were determined using two neutron diffraction techniques: a reactor source and a time of flight spallation source. Microstructure observed by optical microscopy and magnetic force microscopy shows the formation of both fine and coarse structures within the weld metal. There was no evidence of secondary austenite, being present in any of the weld metal conditions examined. In addition, no detrimental intermetallic phases or carbides were present. The DL-EPR test results revealed that the fill layer regions for all four conditions and the base material showed the highest values for Ir/Ia and Qr/Qa. All four test conditions passed the ASTM A262 and A923 qualitative type tests, even under restricted and modified conditions. Residual stress measurements by neutron diffraction conducted at Lucas Heights Hi-Flux Reactor revealed that the ferrite phase stress was tensile in the heat affected zones and weld, and appeared to be balanced by a local compressive austenite phase stresses in the normal and transverse directions. Residual stress measurements by neutron diffraction conducted at Los Alamos Nuclear Science Centre revealed that in the hoop direction, ferrite (211) and austenite (311) exhibit tensile strains in the weld. In the axial and radial direction, the strains for both phases were more compressive. Correlations between the degree of sensitization and microstructural changes / ferrite content were observed. Higher degrees of sensitization (Ir/Ia and Qr/Qa) were associated with reduced ferrite (increased austenite) content. Correlations between the stresses generated, the evolved microstructures and degree of sensitization were evident. Stresses within the cap region were generally shown to be of a tensile nature in the transverse and longitudinal direction. In summary, the study has shown that correlations exist between the weld microstructure, susceptibility to sensitisation and levels / distribution of internal stresses within the weld regions.