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  • About
  • The Global ETD Search service is a free service for researchers to find electronic theses and dissertations. This service is provided by the Networked Digital Library of Theses and Dissertations.
    Our metadata is collected from universities around the world. If you manage a university/consortium/country archive and want to be added, details can be found on the NDLTD website.
61

Condições de contorno albedo para cálculos globais de reatores nucleares térmicos com o modelo de ordenadas discretas a dois grupos de energia / Albedo boundary conditions for thermal nuclear reactors global calculations with two energy group discrete ordinates formulations

Carlos Eduardo de Araújo Nunes 28 November 2011 (has links)
Fundação Carlos Chagas Filho de Amparo a Pesquisa do Estado do Rio de Janeiro / Como eventos de fissão induzida por nêutrons não ocorrem nas regiões nãomultiplicativas de reatores nucleares, e.g., moderador, refletor, e meios estruturais, essas regiões não geram potência e a eficiência computacional dos cálculos globais de reatores nucleares pode portanto ser aumentada eliminando os cálculos numéricos explícitos no interior das regiões não-multiplicativas em torno do núcleo ativo. É discutida nesta dissertação a eficiência computacional de condições de contorno aproximadas tipo albedo na formulação de ordenadas discretas (SN) para problemas de autovalor a dois grupos de energia em geometria bidimensional cartesiana. Albedo, palavra de origem latina para alvura, foi originalmente definido como a fração da luz incidente que é refletida difusamente por uma superfície. Esta palavra latina permaneceu como o termo científico usual em astronomia e nesta dissertação este conceito é estendido para reflexão de nêutrons. Este albedo SN nãoconvencional substitui aproximadamente a região refletora em torno do núcleo ativo do reator, pois os termos de fuga transversal são desprezados no interior do refletor. Se o problema, em particular, não possui termos de fuga transversal, i.e., trata-se de um problema unidimensional, então as condições de contorno albedo, como propostas nesta dissertação, são exatas. Por eficiência computacional entende-se analisar a precisão dos resultados numéricos em comparação com o tempo de execução computacional de cada simulação de um dado problema-modelo. Resultados numéricos para dois problemas-modelo com de simetria são considerados para ilustrar esta análise de eficiência. / As neutron fission events do not take place in the non-multiplying regions of nuclear reactors, e.g., moderator, reflector, and structural core, these regions do not generate power and the computational efficiency of nuclear reactor global calculations can hence be improved by eliminating the explicit numerical calculations within the non-multiplying regions around the active domain. Discussed here is the computational efficiency of approximate discrete ordinates (SN) albedo boundary conditions for two-energy group eigenvalue problems in X,Y geometry. Albedo, the Latin word for whiteness, was originally defined as the fraction of incident light reflected diffusely by a surface. This Latin word has remained the usual scientific term in astronomy and in this dissertation this concept is extended for the reflection of neutrons. The non-standard SN albedo substitutes approximately the reflector region around the active domain, as we neglect the transverse leakage terms within the nonmultiplying reflector. Should the problem have no transverse leakage terms, i.e., onedimensional slab geometry, then the offered albedo boundary conditions are exact. By computational efficiency we mean analyzing the accuracy of the numerical results versus the CPU execution time of each run for a given model problem. Numerical results to two symmetric test problems are shown to illustrate this efficiency analysis.
62

Análise espectral das equações de transporte de nêutrons na formulação de ordenadas discretas em meios multiplicativos / Spectral analysis of the neutron transport equation in discrete ordinates formulation in multiplying media

Mariah Rissi Leitão 05 June 2014 (has links)
É presentada nesta dissertação uma análise espectral das equações de transporte de nêutrons, independente do tempo, em geometria unidimensional e bidimensional, na formulação de ordenadas discretas (SN), utilizando o modelo de uma velocidade e multigrupo, considerando meios onde ocorrem o fenômeno da fissão nuclear. Esta análise espectral constitui-se na resolução de problemas de autovalores e respectivos autovetores, e reproduz a expressão para a solução geral analítica local das equações SN (para geometria unidimensional) ou das equações nodais integradas transversalmente (geometria retangular bidimensional) dentro de cada região homogeneizada do domínio espacial. Com a solução geral local determinada, métodos numéricos, tais como os métodos de matriz de resposta SN, podem ser derivados. Os resultados numéricos são gerados por programas de computadores implementados em MatLab, versão 2012, a fim de verificar a natureza dos autovalores e autovetores correspondentes no espaço real ou complexo. / Presented in this dissertation is a spectral analysis of the neutron transport equations in the slab and X, Y geometry time-independent discrete ordinates formulation using the one-speed and multigroup model in neutron fission reacting media. This spectral analysis is bared on solving eigenvalue problems and yields the expression for the local general solution of the equations (for slab geometry) or of the transverse integrated nodal equations (for multidimensional rectangular geometry) within each homogenized region of the domain. With the local general solution so determined, a number of coarse-mesh numerical methods, such as the response matrix methods, can be derived. Numerical results are generated by computer program s implemented in MatLab, version 2012, in order to verify the nature of the eigenvalues and corresponding eigenvectors in real or complex space.
63

Condições de contorno albedo para cálculos globais de reatores nucleares térmicos com o modelo de ordenadas discretas a dois grupos de energia / Albedo boundary conditions for thermal nuclear reactors global calculations with two energy group discrete ordinates formulations

Carlos Eduardo de Araújo Nunes 28 November 2011 (has links)
Fundação Carlos Chagas Filho de Amparo a Pesquisa do Estado do Rio de Janeiro / Como eventos de fissão induzida por nêutrons não ocorrem nas regiões nãomultiplicativas de reatores nucleares, e.g., moderador, refletor, e meios estruturais, essas regiões não geram potência e a eficiência computacional dos cálculos globais de reatores nucleares pode portanto ser aumentada eliminando os cálculos numéricos explícitos no interior das regiões não-multiplicativas em torno do núcleo ativo. É discutida nesta dissertação a eficiência computacional de condições de contorno aproximadas tipo albedo na formulação de ordenadas discretas (SN) para problemas de autovalor a dois grupos de energia em geometria bidimensional cartesiana. Albedo, palavra de origem latina para alvura, foi originalmente definido como a fração da luz incidente que é refletida difusamente por uma superfície. Esta palavra latina permaneceu como o termo científico usual em astronomia e nesta dissertação este conceito é estendido para reflexão de nêutrons. Este albedo SN nãoconvencional substitui aproximadamente a região refletora em torno do núcleo ativo do reator, pois os termos de fuga transversal são desprezados no interior do refletor. Se o problema, em particular, não possui termos de fuga transversal, i.e., trata-se de um problema unidimensional, então as condições de contorno albedo, como propostas nesta dissertação, são exatas. Por eficiência computacional entende-se analisar a precisão dos resultados numéricos em comparação com o tempo de execução computacional de cada simulação de um dado problema-modelo. Resultados numéricos para dois problemas-modelo com de simetria são considerados para ilustrar esta análise de eficiência. / As neutron fission events do not take place in the non-multiplying regions of nuclear reactors, e.g., moderator, reflector, and structural core, these regions do not generate power and the computational efficiency of nuclear reactor global calculations can hence be improved by eliminating the explicit numerical calculations within the non-multiplying regions around the active domain. Discussed here is the computational efficiency of approximate discrete ordinates (SN) albedo boundary conditions for two-energy group eigenvalue problems in X,Y geometry. Albedo, the Latin word for whiteness, was originally defined as the fraction of incident light reflected diffusely by a surface. This Latin word has remained the usual scientific term in astronomy and in this dissertation this concept is extended for the reflection of neutrons. The non-standard SN albedo substitutes approximately the reflector region around the active domain, as we neglect the transverse leakage terms within the nonmultiplying reflector. Should the problem have no transverse leakage terms, i.e., onedimensional slab geometry, then the offered albedo boundary conditions are exact. By computational efficiency we mean analyzing the accuracy of the numerical results versus the CPU execution time of each run for a given model problem. Numerical results to two symmetric test problems are shown to illustrate this efficiency analysis.
64

Cálculos dos coeficientes de conversão de dose equivalente e dose efetiva em termos da fluência para prótons utilizando simulador antropomórfico híbrido feminino e masculino na postura vertical e sentada e o código MCNPX

Alves, Matheus Carvalho 18 February 2014 (has links)
Ionizing radiation has a harmful potential to humans, so the protection of workers and public individuals is fundamental for the safe use of radiation in different practical purpose. Therefore, is necessary to set exposure limits to radiation using dosimetric quantities such as equivalent dose and effective dose. However equivalent and effective dose are not directly measured, so it is necessary calculate conversion coefficients (CC¡¦s) which relates this quantities with measured quantities such as particles fluence. In the literature exposure scenarios are, in general, built with simulator in the standing posture, but exposure of individuals to radiation can occur in other posture, so the aim of this work is calculate and compare the absorbed dose-to-fluence conversion coefficients (DT/ ¶) and effective dose-to-fluence conversion coefficients (E/ ¶) for the female hybrid simulator (UFHADF) in the standing and sitting posture and for the male hybrid simulator (UFHADM) in the standing posture using the Monte Carlo code MCNPX for monoenergetic protons from 2 MeV to 10 GeV and in the antero posterior (AP), postero anterior (PA), right lateral (RLAT), left lateral (LLAT), rotational (ROT) and isotropic (ISO) exposure scenarios. Comparing the CC¡¦s between standing and sitting posture of UFHADF simulator, it was observed that in the AP and PA irradiation geometry the relative differences in the head, chest and the superior abdomen organs were not relevant. However in the others irradiation geometries, for some organs in the abdomen and chest region differences in CC¡¦s were observed. The organs that presented more differences in CC¡¦s were uterus (538 % in RLAT geometry), bladder (80 % in ROT geometry) and ovaries (2861 % in LLAT geometry) since this organs are located in the lower abdominal region, in which the position of legs and arms are different between standing and sitting posture. Calculate the DT/ ¶ e E/ ¶ nconversion coefficients using simulator in the sitting posture is important to estimate more precisely the dose in individuals exposed to radiation in actual scenarios. / As radiacoes ionizantes tem um potencial danoso aos seres humanos e, por isso, a protecao de trabalhadores e de individuos do publico e essencial para o uso seguro das mesmas nos diversos fins praticos. Desta forma, e necessario estabelecer limites de exposicao com relacao a estes tipos de radiacao e, para tanto, sao utilizadas grandezas dosimetricas como a dose equivalente e a dose efetiva. Como a dose equivalente e a dose efetiva nao sao medidas diretamente faz-se necessario o calculo de coeficientes de conversao (CC¡¦s) em ambito computacional, pois eles relacionam estas grandezas com grandezas mensuraveis, como a fluencia de particulas. Como na literatura os cenarios de exposicao sao, em geral, construidos com simuladores implementados na postura vertical e nem sempre a exposicao de individuos a radiacao ocorre nessa postura, esse trabalho tem como finalidade, utilizar o codigo de transporte de radiacao Monte Carlo MCNPX e o simulador antropomorfico adulto feminino UFHADF nas posturas vertical e sentada e o simulador masculino UFHADM na postura vertical para obter e comparar os coeficientes de conversao para dose absorvida (DT) e dose efetiva (E) em termos da fluencia (£X) (DT/£X e E/£X) para protons monoenergeticos de 2 MeV ate 10 GeV, para os cenarios de irradiacao antero-posterior (AP), postero-anterior (PA), lateral direito (RLAT), lateral esquerdo (LLAT), rotacional (ROT) e isotropico (ISO). Na comparacao dos CC¡¦s entre o simulador UFHADF nas posturas vertical e sentada, foi observado que a diferenca relativa entre os CC¡¦s nos orgaos da regiao da cabeca, do torax e do abdomen superior nao foram relevantes nas geometrias de irradiacao AP e PA. Ja nas demais geometrias de irradiacao, para alguns orgaos da regiao do abdomen e torax diferencas nos CC¡¦s foram observadas. Os orgaos que mais apresentaram diferencas nos CC¡¦s foram o utero (538 % na geometria RLAT), a bexiga (80 % na geometria ROT) e os ovarios (2861 % na geometria LLAT) que se localizam na regiao abdominal inferior, regiao onde ha a diferenca na posicao das pernas e bracos do simulador. Assim, o calculo dos coeficientes de conversao DT/ ¶ e E/ ¶ utilizando simuladores antropomorficos na postura sentada e importante para uma estimativa mais precisa da dose em individuos submetidos a cenarios reais de exposicao a radiacao.
65

Análise espectral das equações de transporte de nêutrons na formulação de ordenadas discretas em meios multiplicativos / Spectral analysis of the neutron transport equation in discrete ordinates formulation in multiplying media

Mariah Rissi Leitão 05 June 2014 (has links)
É presentada nesta dissertação uma análise espectral das equações de transporte de nêutrons, independente do tempo, em geometria unidimensional e bidimensional, na formulação de ordenadas discretas (SN), utilizando o modelo de uma velocidade e multigrupo, considerando meios onde ocorrem o fenômeno da fissão nuclear. Esta análise espectral constitui-se na resolução de problemas de autovalores e respectivos autovetores, e reproduz a expressão para a solução geral analítica local das equações SN (para geometria unidimensional) ou das equações nodais integradas transversalmente (geometria retangular bidimensional) dentro de cada região homogeneizada do domínio espacial. Com a solução geral local determinada, métodos numéricos, tais como os métodos de matriz de resposta SN, podem ser derivados. Os resultados numéricos são gerados por programas de computadores implementados em MatLab, versão 2012, a fim de verificar a natureza dos autovalores e autovetores correspondentes no espaço real ou complexo. / Presented in this dissertation is a spectral analysis of the neutron transport equations in the slab and X, Y geometry time-independent discrete ordinates formulation using the one-speed and multigroup model in neutron fission reacting media. This spectral analysis is bared on solving eigenvalue problems and yields the expression for the local general solution of the equations (for slab geometry) or of the transverse integrated nodal equations (for multidimensional rectangular geometry) within each homogenized region of the domain. With the local general solution so determined, a number of coarse-mesh numerical methods, such as the response matrix methods, can be derived. Numerical results are generated by computer program s implemented in MatLab, version 2012, in order to verify the nature of the eigenvalues and corresponding eigenvectors in real or complex space.
66

Modélisation et méthodes numériques pour l'étude du transport de particules dans un plasma chaud / Modelling and numerical methods for the study of particle transport in a hot plasma

Guisset, Sébastien 23 September 2016 (has links)
Les modèles aux moments angulaires constituent des descriptions intermédiaires entre les modèles cinétiques et les modèles fluides. Dans ce manuscrit, les modèles aux moments angulaires basés sur un principe de minimisation d'entropie sont étudiés pour des applications en physique des plasmas. Ce mémoire se découpe en trois parties. La première est une contribution à la modélisation en physique des plasmas à travers le formalisme des modèles aux moments angulaires. Dans celle-ci, le domaine de validité de ces modèles est étudié en régimes non-collisionels. Il est également montré que les opérateurs de collisions proposés pour le modèle M1 permettent de retrouver des coefficients de transport plasma précis. La deuxième partie de ce document concerne la dérivation de méthodes numériques pour l'étude du transport de particules en temps long. Dans ce cadre, des schémas numériques appropriés pour le modèle M1, préservant l'asymptotique, sont construits et validés numériquement. La troisième partie représente un premier pas significatif vers la modélisation multi-espèces. Ici, le modèle aux moments angulaire M1, construit dans un référentiel mobile, est appliqué à la dynamique des gaz raréfiés. Les propriétés de ce modèle sont détaillées, un schéma numérique est proposé et une validation numérique est menée. / Angular moments models represent alternative descriptions situated in between the kinetic and the fluid models. In this work, angular moments models based on an entropy minimisation principle are considered for plasma physics applications. This manuscript is organised in three parts. The first one is a contribution to plasma physics modelling within the formalism of angular moments models. The validity domain of angular moments models in collisionless regimes is studied. It is also shown that the collisional operators proposed for the M1 angular moments model enable to recover accurate plasma transport coefficients. The second part of this document deals with the derivation of numerical methods for the long timescales particle transport. Appropriate asymptotic-preserving numerical schemes are designed for the M1 angular moments model and numerical validations are performed. The third part represents a first important step toward multi-species modelling. The M1 angular moments model in a moving frame is introduced and applied to rarefied gas dynamics. The model properties are highlighted, a numerical scheme is proposed and a numerical validation is carried out.
67

Cálculos dos coeficientes de conversão de dose equivalente e dose efetiva em termos da fluência para prótons utilizando simulador antropomórfico híbrido feminino e masculino na postura vertical e sentada e o código MCNPX

Alves, Matheus Carvalho 18 February 2014 (has links)
Ionizing radiation has a harmful potential to humans, so the protection of workers and public individuals is fundamental for the safe use of radiation in different practical purpose. Therefore, is necessary to set exposure limits to radiation using dosimetric quantities such as equivalent dose and effective dose. However equivalent and effective dose are not directly measured, so it is necessary calculate conversion coefficients (CCs) which relates this quantities with measured quantities such as particles fluence. In the literature exposure scenarios are, in general, built with simulator in the standing posture, but exposure of individuals to radiation can occur in other posture, so the aim of this work is calculate and compare the absorbed dose-to-fluence conversion coefficients (DT/ ) and effective dose-to-fluence conversion coefficients (E/ ) for the female hybrid simulator (UFHADF) in the standing and sitting posture and for the male hybrid simulator (UFHADM) in the standing posture using the Monte Carlo code MCNPX for monoenergetic protons from 2 MeV to 10 GeV and in the antero posterior (AP), postero anterior (PA), right lateral (RLAT), left lateral (LLAT), rotational (ROT) and isotropic (ISO) exposure scenarios. Comparing the CCs between standing and sitting posture of UFHADF simulator, it was observed that in the AP and PA irradiation geometry the relative differences in the head, chest and the superior abdomen organs were not relevant. However in the others irradiation geometries, for some organs in the abdomen and chest region differences in CCs were observed. The organs that presented more differences in CCs were uterus (538 % in RLAT geometry), bladder (80 % in ROT geometry) and ovaries (2861 % in LLAT geometry) since this organs are located in the lower abdominal region, in which the position of legs and arms are different between standing and sitting posture. Calculate the DT/ e E/ nconversion coefficients using simulator in the sitting posture is important to estimate more precisely the dose in individuals exposed to radiation in actual scenarios. / As radiacoes ionizantes tem um potencial danoso aos seres humanos e, por isso, a protecao de trabalhadores e de individuos do publico e essencial para o uso seguro das mesmas nos diversos fins praticos. Desta forma, e necessario estabelecer limites de exposicao com relacao a estes tipos de radiacao e, para tanto, sao utilizadas grandezas dosimetricas como a dose equivalente e a dose efetiva. Como a dose equivalente e a dose efetiva nao sao medidas diretamente faz-se necessario o calculo de coeficientes de conversao (CCs) em ambito computacional, pois eles relacionam estas grandezas com grandezas mensuraveis, como a fluencia de particulas. Como na literatura os cenarios de exposicao sao, em geral, construidos com simuladores implementados na postura vertical e nem sempre a exposicao de individuos a radiacao ocorre nessa postura, esse trabalho tem como finalidade, utilizar o codigo de transporte de radiacao Monte Carlo MCNPX e o simulador antropomorfico adulto feminino UFHADF nas posturas vertical e sentada e o simulador masculino UFHADM na postura vertical para obter e comparar os coeficientes de conversao para dose absorvida (DT) e dose efetiva (E) em termos da fluencia (X) (DT/X e E/X) para protons monoenergeticos de 2 MeV ate 10 GeV, para os cenarios de irradiacao antero-posterior (AP), postero-anterior (PA), lateral direito (RLAT), lateral esquerdo (LLAT), rotacional (ROT) e isotropico (ISO). Na comparacao dos CCs entre o simulador UFHADF nas posturas vertical e sentada, foi observado que a diferenca relativa entre os CCs nos orgaos da regiao da cabeca, do torax e do abdomen superior nao foram relevantes nas geometrias de irradiacao AP e PA. Ja nas demais geometrias de irradiacao, para alguns orgaos da regiao do abdomen e torax diferencas nos CCs foram observadas. Os orgaos que mais apresentaram diferencas nos CCs foram o utero (538 % na geometria RLAT), a bexiga (80 % na geometria ROT) e os ovarios (2861 % na geometria LLAT) que se localizam na regiao abdominal inferior, regiao onde ha a diferenca na posicao das pernas e bracos do simulador. Assim, o calculo dos coeficientes de conversao DT/ e E/ utilizando simuladores antropomorficos na postura sentada e importante para uma estimativa mais precisa da dose em individuos submetidos a cenarios reais de exposicao a radiacao.
68

Numerical simulation of wind erosion : application to dune migration / Simulation numérique de l’érosion éolienne : application sur la migration des dunes

Wu, Jianzhao 29 May 2019 (has links)
L’érosion éolienne est un phénomène complexe avec des interactions entre la couche limite atmosphérique, le transport des particules et la déformation des dunes. Dans cette thèse des simulations numériques de transport de particules solides sur des dunes fixes ou déformables sont effectuées. L’écoulement turbulent est calculé par des simulations des grandes échelles (LES) couplée avec une méthode de frontières immergées. Les particules solides sont tractées par une approche Lagrangienne. L’entraînement des particules, leur interaction avec la surface et leur dépôt sont pris en compte par des modèles physiques complets d’érosion. D’un point de vue numérique, une méthode de frontières immergées a été introduite pour simuler les écoulements turbulents sur des frontières mouvantes. Le nouveau solveur a été validé en effectuant des comparaison avec les résultats expérimentaux de Simoens et al. (2015) dans le cas d’une colline Gaussienne. D’un point de vue physique, des modèles complets ont été développés pour l’érosion éolienne en se basant sur les forces agissant sur les particules. Des modèles instantanés pour l’envol, le roulement et le glissement des particules sont développés pour initier le mouvement des particules. Leur rebond et le splash sont également pris en compte. Des équations Lagrangiennes sont utilisées pour simuler la trajectoire des particules solides dans l’air. Une équation de transport d’un lit de particules a également été développée pour les cas de glissement et de roulement des particules sur la surface. La déformation de la dune est effectuée en faisant le bilan des particules qui s’envolent et se déposent. Ces modèles ont été validés en comparant les résultats de simulation avec les résultats expérimentaux de Simoens et al. (2015) sur les profils de concentration autour d’une colline Gaussienne. Enfin, des simulations numériques d’une dune sinusoïdale déformable sont effectuées. La forme de la dune simulée est comparée avec les résultats expérimentaux de Ferreira and Fino (2012). Un bon agrément est obtenu a t = 2.0 min, par contre la hauteur de la dune est sous-estimée entre 4.0 min et 6.0 min. Les résultats numériques montrent que la zone de recirculation diminue progressivement quand la dune se déforme. L’érosion, due à l’envol et au splash, est important a l’avant de la dune tandis que les particules se déposent a l’arrière de la dune. Le modèle de splash a été modifié pour prendre en compte l’effet de la pente, ce qui a permis une meilleure estimation de la hauteur de la dune a t = 4.0 min. / Wind erosion is a complex dynamic process consisting in an atmospheric boundary layer, aeolian particle transport, sand dune deformation and their intricate interactions. This thesis undertakes this problems by conducting three-dimensional numerical simulations of solid particle transport over a fixed or deformable sand dune. Turbulent flow is calculated by a developed numerical solver (Large-eddy simulation (LES) coupled with immersed boundary method (IBM)). Solid particle trajectories are tracked by a Lagrangian approach. Particle entrainment, particle-surface interactions and particle deposition are taken into account by physical comprehensive wind erosion models. Firstly, a new numerical solver has been developed to simulate turbulent flows over moving boundaries by introducing the IBM into LES. Two canonical simulation cases of a turbulent boundary layer flow over a Gaussian dune and over a sinusoidal dune are performed to examine the accuracy of the developed solver. Recirculation region characteristics, mean streamwise velocity profiles, Reynolds stress profiles as well as the friction velocity over the dune are presented. In the Gaussian case, a good agreement between experimental data and simulated results demonstrates the numerical ability of the improved solver. In the sinusoidal case, the developed solver with wall modeling over the immersed boundary shows a better performance than the pure one, when a relatively coarse grid is used. Secondly, physical comprehensive modeling of wind erosion is described in detail, based on the forces acting an individual particle. An instantaneous entrainment model for both lifting and rolling-sliding modes is proposed to initialize particle incipient motions. Lagrangian governing equations of aeolian particle motion are presented and used to simulate the trajectories of solid particles. Particularly, Lagrangian governing equations of bed-load particle motion are originally deduced and applied to model the particle rolling-sliding movement on the bed surface. In addition, particle-surface interactions are taken into account by probabilistic rebound/splash models. Thirdly, numerical simulations of particle transport over a fixed Gaussian dune and over a deformable sinusoidal dune are carried out. In the fixed Gaussian case, an overall good agreement on the particle concentration profiles over the dune between the simulated results and the experimental data of Simoens et al. (2015) preliminarily validates the ability and accuracy of the developed numerical solver coupled with physical comprehensive wind erosion models. In the deformable sinusoidal case, the simulated dune shapes are compared with the experimental ones of Ferreira and Fino (2012). A good agreement between them is observed at t = 2.0 min and an obvious underestimate of the dune shape is shown at t = 4.0 min and t = 6.0 min. By analyzing the simulated results, it is shown that the recirculation zone behind the dune is gradually reduced as the dune deforms and that windward erosion and lee side deposition is observed. It is also shown after testing that the splash entrainment is important for the lee side erosion. Moreover, a preliminary attempt is presented to apply an improved splash model with accounting for the bed slope effect to the simulation of sand dune deformation. A better performance on the simulated dune shape is achieved at t = 4.0 min in comparison with the experimental one.
69

Étude de la macro-dispersion de particules inertes dans des milieux poreux 3D fortement hétérogènes / Study of the macro-dispersion of inert particles in highly heterogeneous 3D porous media

Dartois, Arthur 14 December 2016 (has links)
Les milieux poreux font partie des formations géologiques assez répandue dans la nature et son sujet d'études intensives. L'engouement de ce sujet vient des multiples secteurs d'applications de ces recherches et leur importance dans notre société. Que ce soit de la part des sociétés pétrolières qui souhaitent optimiser leurs moyens de productions, les agences de contrôles environnementaux qui veulent prévenir la contamination de nappe phréatique et la fuite de déchets nucléaires ou encore des industriels avec des problèmes de drainages et de réhabilitation de mines, tous ces acteurs dépendent des recherches faites dans ce domaine. Cependant, un des principaux problèmes de ce sujet est l'inaccessibilité des milieux que nous voulons étudier. Pour palier à cela de nombreuses équipes se sont tournées vers la simulation numérique. Cette thèse s'inscrit dans ce cadre et utilise le module PARADIS du logiciel d'hydrogéologie H2olab pour modéliser le transport de particules dans des milieux poreux fortement hétérogènes. Grâce aux données obtenues et à des comparaisons avec la littérature nous montrerons l'effet du passage au 3D sur la topologie de l'écoulement et les répercussions sur le transport de particules ainsi que l'effet de la diffusion moléculaire sur les coefficients de macro-dispersion. Enfin nous proposerons deux lois de transport reliant macrodispersion, variance du champ de perméabilité et diffusion moléculaire. / Heterogeneous porous media have been intensively studied these last fifty years. The popularity of this subject come from the multiple areas where these researches can be applied and their importance to our society. Whether from the oil companies that want to optimize their methods of production, environmental control agencies who want to prevent contamination of ground water and leakage of nuclear waste or industrial with drainage issues and mine rehabilitation, all these actors depend on research done in this area. However, one of the main problems of this subject is the accessibility of these porous media which are often several hundred meters underground. To overcome this, many teams have turned to computer simulation. This thesis is among them and uses the PARADIS module from the hydrogeology software H2olab to model particle transport in highly heterogeneous porous media. Thanks to the data obtained and comparisons with the literature, we show the impact of switching from a 2D to a 3D porous media on the ow topology and the repercussions on the particle transport. Furthermore, we also investigated the effect of molecular diffusion coefficients on macro-dispersion. Finally, we will propose two empirical functions linking macro-dispersion variance of the permeability field and molecular diffusion.
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Untersuchungen zum Vorkommen und Transportverhalten von Partikeln in Grundwässern und Abschätzung ihrer Relevanz für den Schadstofftransport

Marre, Dirk 18 September 2003 (has links)
Im Grundwasser mobile Feststoff-Partikel stehen im Verdacht, den Transport schwerlöslicher Schadstoffe zu begünstigen. Die Partikel-Konzentration im Wasser lässt sich aber nur mittels einer aufwändigen Probenahme bestimmen. Vor diesem Hintergrund wurden im Rahmen dieser Arbeit Feld- und Laborversuche durchgeführt. In Feldversuchen zur Probenahme wurde festgestellt, dass für eine Stabilisierung der Partikel-Anzahl-Konzentration (CN in Partikel>Nachweisgrenze/L) die Dauer der Probenahme ausschlaggebend ist, nicht das insgesamt geförderte Volumen. Eine hohe Förderrate hat dabei nicht automatisch eine stärkere Mobilisierung von Partikeln aus dem Partikel-Depot im Umfeld der Messstelle zur Folge, wie es häufig postuliert wird. Die Gewinnung einer repräsentativen Partikelprobe macht eine Probenahme-Dauer von mindestens 5, häufig sogar über 10 oder 12 Stunden erforderlich. Empfehlungen zur Probenahme wurden erarbeitet. Es wurde aber festgestellt, dass sich stabilisierte Werte für CN als Funktion der Förderdauer (t in min) nach CN = a ? t^(-½) ungefähr abschätzen lassen, wenn der Parameter a über CN nach ca. 60 Minuten ermittelt wird. Bei Wässern mit Sauerstoff-Konzentrationen über ca. 1 mg/L kann überdies auch die Verteilung der Partikel auf einzelne Größenklassen bereits nach dieser Zeit ermittelt werden; bei sauerstoffärmeren Wässern verändert sie sich später noch. Angesichts einer starken Variation von CN einer Messstelle ist es generell aber nur möglich, eine Größenordnung für die Hintergrundkonzentration anzugeben. Von Messstelle zu Messstelle sind große Unterschiede bei CN festzustellen. Die Konzentration ist dabei nicht eindeutig abhängig von der Lithologie des Grundwasserleiters oder der Zusammensetzung des Grundwassers. Allerdings konnte eine schwache Korrelation mit dem Redox-Potential (Eh in mV) des Wassers gefunden werden (CN = 1,8?10^6?e^( 0,0087?Eh) [Partikel>2,58µm/L]; r² ≈ 0,46). Hierüber besteht die Möglichkeit, CN eines Grundwassers auch ohne Partikelmessung abzuschätzen. Insgesamt bewegen sich die Partikel-Massen-Konzentrationen (C in mg/L) der beprobten Wässer meist im Bereich von <1 mg/L, öfters sogar <0,1 mg/L, wenn die im Verlaufe von Probenahme und Messung ausgefällten Fe- und Mn-Oxide nicht berücksichtigt werden. Solche Konzentrationen sind vermutlich kaum in der Lage, relevante Mengen selbst sehr hydrophober Schadstoffen aufzunehmen und zu transportieren. Versuche mit Phenanthren ergaben zudem, dass es anscheinend weniger an bereits in Suspension befindliche Partikel sorbiert, sondern vielmehr in sorbiertem oder kristallinen Zustand aus dem Depot erodiert wird. In Laborversuchen wurde weiter gezeigt, dass in natürlichen Sedimenten ein großes Depot mobilisierbarer Partikel vorhanden ist, das Partikel über einen sehr langen Zeitraum kontinuierlich abgeben kann. Durchbruchsversuche ergaben außerdem, dass ein Großteil zugegebener Partikel bei der Passage durch eine Sedimentprobe zurückgehalten und nur sehr allmählich wieder abgegeben wird. Allerdings war auch ein schneller (präferentieller) Durchbruch zu verzeichnen. In Modellrechnungen konnte gezeigt werden, dass sich ein solcher Partikeltransport weder über eine Filterfunktion noch über die Transportgleichung zufrieden stellend berechnen lässt. Daher ist es nötig, einerseits einen bevorzugten Transport und andererseits eine starke Retardation zu berücksichtigen. Letzteres kann am besten über verschiedene Retardationsfaktoren oder ein dynamisches Partikel-Depot mit Anlagerungs- und Ablösungskonstanten geschehen. / Solid particles that are mobile in groundwater are suspected to enhance the transport of hardly soluble contaminants. But particle concentrations in water can only be measured using time-consuming sampling-procedures. On this background field- and laboratory-experiments were conducted in this work. In field experiments on sampling it turned out, that sampling time is crucial for stabilizing particle number-concentration (CN in particles>detection limit/L), not the volume sampled. A high sampling rate does not -as often argued- automatically result into higher mobilization of particles from the particle-depot in the vicinity of the sampling-well. Obtaining a representative particle sample requires a sampling-time of at least 5, often even more than 10 or 12 hours. In this work recommendations on sampling are given. It was noticed that stabilized values of CN can be estimated as function of sampling time (t in min) by CN = A ? t^(-½), if parameter A is calculated using CN after about 60 minutes. In waters having oxygen-concentrations above approximately 1 mg/L even distribution of the particles into size classes can be estimated after this time; in oxygen-poor waters size-distributions stabilized much later. Because of strong variations of CN in a single measuring well it is generally only possible to give the magnitude of the background-particle-concentration. But among several measuring wells CN may differ by several magnitudes. The concentrations do neither definitely depend upon the lithology of the aquifer nor on the groundwater-composition. But a weak correlation to the redox-potential (Eh in mV) can be found (CN = 1.8 ? 10^6 ? e^( 0.0087 ? Eh) [particles>2.58µm/L]; r² ≈ 0,46). Using this connection it is possible to estimate a magnitude of CN of a groundwater without even measuring particles. Over all particle mass-concentrations (C in mg/L) of all sampled groundwaters were almost always <1 mg/L, often even <0.1 mg/L, at least if iron- and manganese-oxides that precipitated during measurements were ignored. Such particle concentrations are probably hardly capable of adsorbing and carrying relevant amounts of contaminants, even very hydrophobic ones. Experiments using phenanthrene in contaminated sand additionally showed that it is probably hardly adsorbed onto already suspended particles, but mostly eroded from the particle depot in adsorbed or crystalline state. In laboratory experiments it was further shown that there is a huge depot of mobilizable particles in natural sediments that can continually release particles over a very long period of time. Break-through-experiments showed in addition that a large part of particles fed into the system are retained during the passage through a sediment sample and that they are re-released only very slowly. However, there also was a fast (preferential) break-through. In model calculations it could be shown that such a particle transport can neither be sufficiently described by the filter-function nor by the transport equation. Because of that it is necessary to take into consideration a preferential transport on the one hand and a strong retardation on the other. The last one can at the best be described by several retardation-factors or a dynamic particle-depot having constant attachment- and detachment rates.

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