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.

At the Los Alamos Neutron Science Center accelerator complex, protons are accelerated to 800 MeV and directed to two tungsten targets, Target 4 at the Weapons Neutron Research facility and the 1L target at the Lujan Center. The Department of Energy requires hazard classification analyses to be performed on these targets and places limits on certain radionuclide inventories in the targets to avoid characterizing the facilities as nuclear facilities. Gadolinium-148 is a radionuclide created from the spallation of tungsten. Allowed isotopic inventories are particularly low for this isotope because it is an alpha-particle emitter with a 75-year half-life. The activity level of Gadolinium-148 is low, but it encompasses almost two-thirds of the total dose burden for the two tungsten targets based on present yield estimates. From a hazard classification standpoint, this severely limits the lifetime of these tungsten targets. The cross section is not well-established experimentally and this is the motivation for measuring the Gadolinium-148 production cross section from tungsten. In a series of experiments at the Weapons Neutron Research facility, Gadolinium-148 production was measured for 600- and 800-MeV protons on tungsten, tantalum, and gold. These experiments used 3 m thin tungsten, tantalum, and gold foils and 10 m thin aluminum activation foils. In addition, spallation yields were determined for many short-lived and long-lived spallation products with these foils using gamma and alpha spectroscopy and compared with predictions of the Los Alamos National Laboratory codes CEM2k+GEM2 and MCNPX. The cumulative Gadolinium-148 production cross section measured from tantalum, tungsten, and gold for incident 600-MeV protons were 15.24.0, 8.310.92, and 0.5910.155, respectively. The average production cross sections measured at 800 MeV were 28.63.5, 19.41.8, and 3.690.50 for tantalum, tungsten, and gold, respectively. These cumulative measurements compared best with Bertini and were within a factor of two to three of CEM2k+GEM2.

Thesis (Master's)--University of California, Berkeley. / Includes bibliographical references (p. 33-35). 54

La fracturation des roches concerne plusieurs applications industrielles, telles que les tunnels, l’excavation, l’extraction de blocs de roches et l'industrie minière. Les techniques classiques pour fracturer la roche sont associées à des inconvénients ceux qui restreignent leur utilisation dans certaines circonstances. Par conséquent, la fracturation par spallation thermique a été suggérée comme une solution alternative. Cela produit des contraintes de compression dans la roche grâce à un flux de chaleur intense. Une fois que ces contraintes dépasseraient la résistance à compression de la roche, la rupture aurait lieu en éjectant des petits éclats. Cette mode de fracturation thermique nécessite une source d’énergie puissante ainsi qu’elle influence négativement les conditions du travail sur le site. Profitant d'une faible résistance à la traction du matériau de roche, le présent travail propose une méthode basée sur un chauffage rapide de la matière rocheuse par un rayonnement micro-ondes, suivi par un refroidissement rapide par de l'eau pour fracturer la roche. Au cours de ce processus, une dilatation thermique est produite à l'intérieur de la zone traitée, qui est ensuite suivie d'une contraction thermique. Cette contraction produit des contraintes de traction, ce qui pourrait conduire à la rupture de la matière de roche. Le processus d'échauffement/refroidissement sera analysés grâce à un modèle numérique ce qui décrit les événements physiques et l'influence de différents paramètres. Expérimentalement, le processus sera examiné du point de vue thermique.‎ / The issue of rock fracturing concerns several industrial applications, such as tunneling or excavation ‎in rock material, extraction of rock blocks and the mining industry. The conventional techniques to ‎fracture the rock material are associated with disadvantages restrict their use in certain circumstances. ‎Consequently, the fracture by thermal spallation was suggested as an alternative solution. This ‎solution basically depends on exceeding the compressive strength of the rock material by compressive ‎stresses induced by heating effects. This necessitates high temperature at the rock surface, which ‎requires high power supply and it degrades the work conditions. Profiting from low tensile strength ‎of the rock material, the present work proposes a method based on a rapid heating of the rock ‎material by microwaves radiation followed by a rapid cooling by water to fracture the rock material. ‎During this process, a thermal dilatation is produced within the treated zone, which is then followed ‎by a thermal shrinkage. This shrinkage produces tensile stresses, which could lead to fracturing the ‎rock material. The heating/cooling process will be analyzed through numerical model describes the ‎physical events and the influence of different parameters. Experimentally, the process will be ‎examined from thermal point of view.‎

abstract: Shock loading produces a compressive stress pulse with steep gradients in density, temperature, and pressure that are also often modeled as discontinuities. When a material is subject to these dynamic (shock) loading conditions, fracture and deformation patterns due to spall damage can arise. Spallation is a dynamic material failure that is caused by the nucleation, growth, and coalescence of voids, with possible ejection of the surface of the material. Intrinsic defects, such as grain boundaries are the preferred initiation sites of spall damage in high purity materials. The focus of this research is to study the phenomena that cause void nucleation and growth at a particular grain boundary (GB), chosen to maximize spall damage localization. Bicrystal samples were shock loaded using flyer-plates via light gas gun and direct laser ablation. Stress, pulse duration, and crystal orientation along the shock direction were varied for a fixed boundary misorientation to determine thresholds for void nucleation and coalescence as functions of these parameters. Pressures for gas gun experiments ranged from 2 to 5 GPa, while pressures for laser ablation experiments varied from 17 to 25 GPa. Samples were soft recovered to perform damage characterization using electron backscattering diffraction (EBSD) and Scanning Electron Microscopy (SEM). Results showed a 14% difference in the thresholds for void nucleation and coalescence between samples with different orientations along the shock direction, which were affected by pulse duration and stress level. Fractography on boundaries with strong damage localization showed many small voids, indicating they experience rapid nucleation, causing early coalescence. Composition analysis was also performed to determine the effect of impurities on damage evolution. Results showed that higher levels of impurities led to more damage. ABAQUS/Explicit models were developed to simulate flyer-plate impact and void growth with the same crystal orientations and experimental conditions. Results are able to match the damage seen in each grain of the target experimentally. The Taylor Factor mismatch at the boundary can also be observed in the model with the higher Taylor Factor grain exhibiting more damage. / Dissertation/Thesis / Doctoral Dissertation Mechanical Engineering 2020

No description available.

The research conducted was a feasibility study using Lithium Fluoride-Beryllium Fluoride (LiF-BeF2) or FLiBe as a coolant with a natural uranium neutron spallation source applied to an accelerator driven sub-critical molten salt reactor. The study utilized two different software tools, MCNPX 2.6 and FLUENT 12.1. MCNPX was used to determine the neutronics and heat deposited in the spallation target structure while FLUENT was used to determine the feasibility of cooling the target structure with FLiBe. Several target structures were analyzed using a variety of plates and large cylinders of natural uranium with a proton beam incident on a Hastelloy-N window. The supporting structures were created from Hastelloy-N due to their anti-corrosive properties of molten salts such as FLiBe and their resistance to neutron damage. The final design chosen was a "Sandwich" design utilizing a section of thick plates followed by several smaller plates then finally a section of thick plates to stop any protons from irradiating the bottom of the target support structure or the containment vessel of the reactor. Utilizing a proton beam with 0.81 MW of proton beam power at 1.35 mA with proton kinetic energies of 600 MeV, the total heat generated in the spallation target was about 0.9 MW due to fissions in the natural uranium. Additionally, the neutrons produced from the final design of the spallation target were approximately 1.25x1018 neutrons per second which were mainly fast neutrons. The use of a natural uranium target proved to be very promising. However, cooling the target using FLiBe would require further optimization or investigation into alternate coolants. Specifically, the final design developed using FLiBe as a coolant was not practically feasible due to the hydraulic forces resulting from the high flow rates necessary to keep the natural uranium target structures cooled. The primary reason for the lack of a feasible solution was the FLiBe as a coolant; FLiBe is unable to pull enough heat generated in the target out of the target structure. Due to the high energy density of a natural uranium spallation target structure, a more effective method of cooling will be required to avoid high hydraulic forces, such as a liquid metal coolant like lead-bismuth eutectic. / Master of Science

The phenomenon of spallation, a process by which pieces of char "pop off" a heat shield, has been investigated as it occurs in carbon-reinforced phenolic ablators. Spallation is shown to be the result of a pressure buildup within the char. This pressure increase results from occlusion of the char and the consequent blockage of now. By selective fiber orientation, the spallation process can be alleviated. / Master of Science

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.