Предметом исследования является производство сортового проката высокого качества. Приведен литературный обзор, включающий в себя некоторые особенности производства сортового проката без дополнительных продольных усилий, описание влияния натяжения и/ил подпора на качество получаемого проката. Выполнена постановка задачи по моделированию прокатки полосы одновременно в трех клетях. Адекватность представленной модели показана путем сравнения результатов моделирования и показаний с действующего стана. Погрешность по формоизменению не превысила 0,4%, по моменту прокатки 11%, что является удовлетворительной сходимостью. На основе разработанной модели спланирован и выполнен расчетный эксперимент по влиянию рассогласования скоростей непрерывной прокатки на технологические параметры процесса. Получены уравнения регрессия описывающие закономерности влияния рассогласования скоростей прокатки на технологические параметры процесса. / The subject of the research is the production of high quality long products. A literature review is presented, which includes some features of the production of bars without additional longitudinal forces, a description of the effect of tension and/or back dam on the quality of the rolled products. The formulation of the problem of modeling rolling bar simultaneously in three stands is completed. The adequacy of the presented model is shown by comparing the simulation results and indications from the rolling mill. The error in the spreading did not exceed 0.4%, at the torque of rolling 11%, which is satisfactory convergence. Based on the developed model, a design experiment was planned and performed on the effect of the mismatch of continuous rolling speeds on the process parameters. The regression equations are obtained that describe the patterns of the influence of mismatch of rolling speeds on the technological parameters of the process.

Gas-liquid two-phase flows are encountered in different industrial applications such as, chemical reactors, wastewater treatment, oil and gas exploration and nuclear reactors. In nuclear reactors, boiling two-phase flows occur under both normal and accident conditions. For the design and safety operation of nuclear reactors, Computational Fluid Dynamics (CFD) based on the Euler−Euler framework has become a popular tool. However, accurate CFD prediction for a fuel assembly geometry is still a challenge. The reason is that the accuracy of two-phase flow simulations is highly dependent on adequate modelling of phase interactions including interfacial forces (i.e. drag, lift, wall lubrication, turbulent dispersion and virtual mass), bubble-induced turbulence (BIT) and bubble breakup/coalescence. Through the Euler−Euler framework, modelling of these phase interactions is provided by different approaches. These approaches include closure equations, most of which have been determined empirically. These closures are important for the accurate prediction of mean flow profiles, including void fraction and phase velocity distributions. A variety of closure models has been proposed by different researchers. However, it is difficult to differentiate them and make an appropriate choice for a particular problem without knowing their predictive properties in detail. While an extensive number of models have been developed and have meanwhile been well validated for simple pipe and column geometries, there is yet limited analysis and qualification for more complex three-dimensional flow domains. One reason for this is the lack of suitable experimental validation data. In addition, it is important to mention that most of the available models were generally obtained considering laminar or low turbulence conditions. Therefore, it is necessary to further investigate the modelling capabilities for two-phase flows with flow complexity/high turbulence as they occur in nuclear reactors. For this purpose, additional validations are required in the CFD modelling of two-phase flows. However, studies on the capabilities of two-phase flow models directly for rod bundles are very complicated and time-consuming. Hence, a capability analysis of the models for the three main phenomena, i.e. breakup/coalescence, drag and turbulence, was first carried out for the case of a semi-obstructed pipe under adiabatic flow conditions. The results were validated using the experimental data obtained by Neumann-Kipping (2022) on the void fraction, mean bubble diameter, bubble size distribution, liquid velocity and gas velocity for two different turbulence conditions. Subsequently, experiments were conducted in a 3 x 3 rod bundle with a spacer and vanes using X-ray computed tomography (CT), which provides high quality void data without disturbing the flow. The effects of different mass and heat fluxes on the void fraction and its distribution downstream of the spacer were analyzed. In addition, the effects of different vane angles on the distribution of the void fraction were discussed. Furthermore, an experimental database was obtained in a rod bundle with a spacer under different flow conditions to validate the numerical modelling. Finally, the improved CFD model obtained from the semi-obstructed pipe geometry was applied to the 3 x 3 rod bundle geometry under two different turbulence conditions. The numerical results were compared with the X-ray CT data on the void fraction. / Gas-Flüssig-Zweiphasenströmungen kommen in verschiedenen industriellen Anwendungen wie Blasensäulen, Rührkesseln und Kernreaktoren vor. In Kernreaktoren treten siedende Zweiphasenströmungen sowohl unter Normal- als auch unter Störfallbedingungen auf. Für die Auslegung und den sicheren Betrieb von Kernreaktoren ist die numerische Strömungsmechanik (engl. Computational Fluid Dynamics, CFD) auf der Grundlage des Euler−Euler-Konzepts zu einem wichtigen Instrument geworden. Eine genaue CFD-Vorhersage für eine Brennelementgeometrie ist jedoch nach wie vor eine Herausforderung. Der Grund dafür ist, dass die Genauigkeit von Zweiphasenströmungssimulationen in hohem Maße von einer genauen Modellierung der Phasenwechselwirkungen abhängt, einschließlich der Grenzflächenkräfte (d. h. Widerstand, Lift, Wand, turbulente Dispersion und virtuelle Masse), der blaseninduzierten Turbulenz (BIT) und des Aufbrechens/Koaleszierens von Blasen. Durch den Euler−Euler-Rahmen wird die Modellierung dieser Phasenwechselwirkungen durch verschiedene Ansätze ermöglicht. Zu diesen Ansätzen gehören Schließungsgleichungen, von denen die meisten empirisch ermittelt wurden. Diese Schließungsgleichungen sind wichtig für die genaue Vorhersage von mittleren Strömungsprofilen, einschließlich Gasgehalt und Phasengeschwindigkeitsverteilungen. Es gibt eine Vielzahl von Schließungsmodellen, die von verschiedenen Forschern innerhalb ihrer experimentellen Bereiche vorgeschlagen wurden. Es ist jedoch schwierig, sie zu unterscheiden und eine geeignete Wahl für ein bestimmtes Problem zu treffen, ohne ihre Vorhersageeigenschaften im Detail zu kennen. Während für einfache Rohr- und Säulengeometrien eine große Anzahl von Modellen entwickelt und inzwischen gut validiert wurde, gibt es für komplexere dreidimensionale Strömungsgebiete noch wenig Analyse und Qualifizierung. Ein Grund dafür ist der Mangel an geeigneten experimentellen Validierungsdaten. Darüber hinaus ist es wichtig zu erwähnen, dass die meisten der verfügbaren Modelle im Allgemeinen unter laminaren oder geringen Turbulenzbedingungen erstellt wurden. Daher ist es notwendig, die Modellierungsmöglichkeiten für Zweiphasenströmungen mit komplexer Strömung/hoher Turbulenz, wie sie in Kernreaktoren auftreten, weiter zu untersuchen. Zu diesem Zweck sind zusätzliche Validierungen bei der CFD-Modellierung von Zweiphasenströmungen erforderlich. Untersuchungen zur Leistungsfähigkeit von Zweiphasenströmungsmodellen direkt für Stabbündel sind jedoch sehr kompliziert und zeitaufwändig. Daher wurde zunächst eine Fähigkeitsanalyse der Modelle für die drei Hauptphänomene, d. h. Aufbrechen/Koaleszenz, Widerstand und Turbulenz, für den Fall eines halbgeschlossenen Rohrs unter adiabatischen Strömungsbedingungen durchgeführt. Die Ergebnisse wurden anhand der von Neumann-Kipping (2022) gewonnenen experimentellen Daten über den Gasgehalt, den mittleren Blasendurchmesser, die Blasengrößenverteilung, die Flüssigkeitsgeschwindigkeit und die Gasgeschwindigkeit für zwei verschiedene Turbulenzbedingungen validiert. Anschließend wurden Experimente in einem 3 x 3-Stabbündel mit einem Abstandshalter und Fahnen unter Verwendung der Röntgen-Computertomographie (CT) durchgeführt, die qualitativ hochwertige Gasgehaltdaten liefert, ohne die Strömung zu stören. Die Auswirkungen unterschiedlicher Massen- und Wärmeströme auf den Gasgehalt und seine Verteilung stromabwärts des Abstandshalters wurden analysiert. Außerdem wurden die Auswirkungen verschiedener Fahnenwinkel auf die Verteilung des Gasgehaltes diskutiert. Darüber hinaus wurde eine experimentelle Datenbasis in einem Stabbündel mit einem Abstandshalter unter verschiedenen Strömungsbedingungen gewonnen, um die numerische Modellierung zu validieren. Schließlich wurde das verbesserte CFD-Modell, das aus der halbgeschlossenen Rohrgeometrie gewonnen wurde, auf die 3 x 3 Stabbündelgeometrie bei zwei verschiedenen Turbulenzbedingungen angewendet. Die numerischen Ergebnisse wurden mit den Röntgen-CT-Daten für den Gasgehalt verglichen.

[EN] The neutron diffusion equation is an approximation of the neutron transport equation that describes the neutron population in a nuclear reactor core. In particular, we will consider here VVER-type reactors which use the neutron diffusion equation discretized on hexagonal meshes. Most of the simulation codes of a nuclear power reactor use the multigroup neutron diffusion equation to describe the neutron distribution inside the reactor core.To study the stationary state of a reactor, the reactor criticality is forced in artificial way leading to a generalized differential eigenvalue problem, known as the Lambda modes equation, which is solved to obtain the dominant eigenvalues of the reactor and their corresponding eigenfunctions. To discretize this model a finite element method with h-p adaptivity is used. This method allows to use heterogeneous meshes, and allows different refinements such as the use of h-adaptive meshes, reducing the size of specific cells, and p-refinement, increasing the polynomial degree of the basic functions used in the expansions of the solution in the different cells. Once the solution for the steady state neutron distribution is obtained, it is used as initial condition for the time integration of the neutron diffusion equation. To simulate the behaviour of a nuclear power reactor it is necessary to be able to integrate the time-dependent neutron diffusion equation inside the reactor core. The spatial discretization of this equation is done using a finite element method that permits h-p refinements for different geometries. Transients involving the movement of the control rod banks have the problem known as the rod-cusping effect. Previous studies have usually approached the problem using a fixed mesh scheme defining averaged material properties and many techniques exist for the treatment of the rod cusping problem. The present work proposes the use of a moving mesh scheme that uses spatial meshes that change with the movement of the control rods avoiding the necessity of using equivalent material cross sections for the partially inserted cells. The performance of the moving mesh scheme is tested studying different benchmark problems. For reactor calculations, the accuracy of a diffusion theory solution is limited for for complex fuel assemblies or fine mesh calculations. To improve these results a method that incorporates higher-order approximations for the angular dependence, as the simplified spherical harmonics (SPN ) method must be employed. In this work an h-p Finite Element Method (FEM) is used to obtain the dominant Lambda mode associated with a configuration of a reactor core using the SPN approximation. The performance of the SPN (N= 1, 3, 5) approximations has been tested for different reactor benchmarks. / [ES] La ecuación de la difusión neutrónica es una aproximación de la ecuación del transporte de neutrones que describe la población de neutrones en el núcleo de un reactor nuclear. En particular, consideraremos reactores de tipo VVER y para simular su comportamiento se utilizará la ecuación de la difusión neutrónica para cuya discretización se hace uso de mallas hexagonales. La mayoría de los códigos de simulación de reactores nucleares utilizan aproximación multigrupo de energía de la ecuación de la difusión neutrónica para describir la distribución de neutrones en el interior del núcleo del reactor. Para estudiar el estado estacionario del reactor, es posible forzar la criticidad del reactor de forma artificial modificando las secciones eficaces de forma que se obtiene un problema de valores propios diferencial, conocido como el problema de los Modos Lambda, que se resuelve para obtener los valores propios dominantes del reactor y sus correspondientes funciones propias. Para discretizar este modelo se ha hecho uso de un método de elementos finitos con adaptabilidad h-p. Este método permite el uso de mallas heterogéneas, y de diferentes refinamientos como el uso mallas h-adaptativas, reduciendo el tamaño de los distintos nodos, y el p-refinado, aumentando el grado del polinomio de las funciones básicas utilizado en los desarrollos de la solución en los diferentes nodos. Se ha desarrollado un código basado en un método de elementos finitos de alto orden para resolver el problema de los Modos Lambda en un reactor con geometría hexagonal y se han obtenido los Modos dominantes para distintos problemas de referencia. Una vez que se ha obtenido la solución para la distribución de neutrones en estado estacionario, ésta se utiliza como condición inicial para la integración de la ecuación de difusión neutrónica dependiente del tiempo. Para simular el comportamiento de un reactor nuclear para un determinado transitorio, es necesario ser capaz de integrar la ecuación de la difusión neutrónica dependiente del tiempo en el interior del núcleo del reactor. La discretización espacial de esta ecuación se hace usando un método de elementos finitos de alto orden que permite refinados de tipo h-p para distintas geometrías. Los transitorios que implican el movimiento de los bancos de las barras de control tienen el problema conocido como el efecto 'rod-cusping'. Estudios anteriores, por lo general, han abordado este problema utilizando una malla fija y definiendo propiedades promedio para los materiales correspondientes a las celdas donde se tiene la barra de control parcialmente insertada. En el presente trabajo se propone el uso de un esquema de malla móvil, de forma que en mallado espacial va cambiando con el movimiento de la barra de control, evitando la necesidad de utilizar secciones eficaces equivalentes para las celdas parcialmente insertadas. El funcionamiento de este esquema de malla móvil propuesto se estudia resolviendo distintos problemas tipo. La precisión obtenida mediante de la teoría de la difusión en los cálculos de reactores es limitada cuando se tienen elementos de combustible complejos o se pretenden realizar cálculos en malla fina. Para mejorar estos resultados, es necesario disponer de un método que incorpore aproximaciones de orden superior de la ecuación del transporte de neutrones. Una posibilidad es hacer uso de las ecuaciones PN simplificadas (SPN ). En este trabajo se utiliza un método de elementos finitos h-p para obtener los modos dominantes asociados con una configuración dada del núcleo de un reactor nuclear con geometría hexagonal usando la aproximación SPN . El funcionamiento de las aproximaciones SPN (N = 1, 3, 5) se ha estudiado para distintos problemas de referencia. / [CA] L'equació de la difusió neutrònica és una aproximació de l'equació del transport de neutrons que descriu la població de neutrons en el nucli de un reactor nuclear. En particular, considerarem reactors de tipus VVER i per a simular el seu comportament s'utilitzarà l'equació de la difusió neutrónica que es discretitza fent ús de malles hexagonals. La majoria dels codis de simulació de reactors nuclears utilitzen l'aproximació multigrup d'energia de l'equació de la difusió neutrónica per a descriure la distribució de neutrons a l'interior del nucli del reactor. Per a estudiar l'estat estacionari del reactor, és possible forçar la seua criticitat de forma artificial modificant les seccions eficaces de manera que s'obté un problema de valors propis diferencial, conegut com el problema dels Modes Lambda, que es resol per a obtenir els valors propis dominants del reactor i les seues corresponents funcions pròpies. Per a discretitzar aquest model s'ha fet ús d'un mètode d'elements finits amb adaptabilitat h-p. Aquest mètode permet l'ús de malles heterogènies, i de diferents refinaments com l'ús malles h-adaptatives, reduint la grandària dels diferents nodes, i el p-refinat, augmentant el grau del polinomi de les funcions bàsiques utilitzat en els desenvolupaments de la solució en els diferents nodes. S'ha desenvolupat un codi basat en un mètode d'elements finits d'alt ordre per a resoldre el problema dels Modes Lambda en un reactor amb geometria hexagonal i s'han obtingut els Modes dominants per a diferents problemes de referència. Una vegada que s'ha obtingut la solució per a la distribució de neutrons en estat estacionari, aquesta s'utilitza com a condició inicial per a la integració de l'equació de difusió neutrònica depenent del temps. Per a simular el comportament d'un reactor nuclear per a un determinat transitori, és necessari ser capaç d'integrar l'equació de la difusió neutrónica depenent del temps a l'interior del nucli del reactor. La discretitzación espacial d'aquesta equació es fa usant un mètode d'elements finits d'alt ordre que permet refinats de tipus h-p per a diferents geometries. Els transitoris que impliquen el moviment dels bancs de les barres de control tenen el problema conegut com l'efecte 'rod-cusping'. Estudis anteriors, en general, han abordat aquest problema utilitzant una malla fixa i definint propietats equivalents per als materials corresponents a les cel·les on es té la barra de control parcialment inserida. En el present treball es proposa l'ús d'un esquema de malla mòbil, de manera que en mallat espacial va canviant amb el moviment de la barra de control, evitant la necessitat d'utilitzar seccions eficaces equivalents per a les cel·les parcialment inserides. El funcionament de aquest esquema de malla mòbil s'estudia resolent diferents problemes tipus. La precisió obtinguda mitjançant de la teoria de la difusió en els càlculs de reactors és limitada quan es tenen elements de combustible complexos o es pretenen realitzar càlculs en malla fina. Per a millorar aquests resultats, és necessari disposar d'un mètode que incorpore aproximacions d'ordre superior de l'equació del transport de neutrons. Una possibilitat és fer ús de les equacions PN simplificades (SPN ). En aquest treball s'utilitza un mètode d'elements finits h- p per a obtenir els modes dominants associats amb una configuració donada del nucli de un reactor amb geometria hexagonal usant l'aproximació SPN . El funcionament de les aproximacions SPN (N = 1, 3, 5) s'ha estudiat per a diferents problemes de referència. / Fayez Moustafa Moawad, R. (2016). Approximation of The Neutron Diffusion Equation on Hexagonal Geometries Using a h-p finite element method [Tesis doctoral]. Universitat Politècnica de València. https://doi.org/10.4995/Thesis/10251/65353

1 Michal Vázal: The Confucian Ideal of Harmonious Community according to the Norms of the Wu Lineage from Mingzhou Abstract Abstract: This paper aims to characterize the structure and values produced by rituals in a kinship community, and how these characteristics subsequently helped to shape a harmoniously working community and its ideological relationship with the state in terms of local governance. The rituals in question are partially confined in time and place, as they are observed on one particular community, and are examined only in the extent of the primary source named "The Norms and Rituals of the Wu Lineage of Mingzhou" (Mingzhou Wu Shi Jiadian) - a ritual manual authored mainly by Wu Di (died 1736) from the village of Mingzhou, which belonged to the Huizhou prefecture (the south of the present day Anhui province). On the other hand, this text is largely based on Zhu Xi's "Family Rituals" (Jiali) which were viewed across the country as the ritual standard. The most essential rituals used to govern the lineage were coming of age ritual, wedding rituals, funeral rituals and sacrifices to ancestors. A unifying principle behind the structure and values these rituals created was seniority. The lineage structure was created mainly by the system in which the branches of firstborn sons were superiors to...

<p>The primary objective of this research was to identify and<br />analyse the challenges faced by ethnic minority students<br />while studying and building an academic career in the higher<br />education system of Serbia. The secondary objective was to<br />analyse the unconscious and conscious gender biases towards<br />ethnic minority women, when building their academic careers<br />and in reaching decision-making position in academia. The<br />tertiary objective of was to raise awareness about the<br />increased demand for human resources in the technical fields<br />and that therefore more women should be steered towards the<br />studying engineering.<br />The research was conducted based on 2192 filled in<br />questionnaires and 45 semi-structured interviews. The<br />research results showed that language, intersecting with<br />gender, ethnicity and class result in a new inequality concept.<br />It was shown that women are under-represented in technical<br />fields, which has its roots in gender stereotypes. Finally, it<br />was shown that women are less motivated to reach higher<br />positions in the Serbian higher education system than men.<br />The author proposes a set of policy recommendations for<br />solving/mitigating the identified challenges, e.g. deconstruction<br />of gender stereotypes via improved teaching<br />aids in elementary and high schools, optimised Serbian<br />language teaching to eliminate the language difficulty faced<br />at the start of their higher education; as well as the founding<br />of an ethnic minority research centre, which would research<br />the challenges faced by ethnic minority communities.</p> / <p>Primarni cilj istraživanja je identifikacija i i analiza prepreka<br />u sistemu visokog obrazovanja tokom studiranja i izgradnje<br />karijere u akademskoj zajednici žena iz nacionalnih zajednica<br />sa posebnim osvrtom na žene iz mađarske nacionalne<br />zajednice. Sekundarni cilj je analiza nesvesne i svesne rodne<br />pristrasnosti prema ženama etničkih manjina u toku izgradnje<br />akademske karijere i pri dosezanju visokih pozicija unutar<br />akademije. Tercijarni cilj istraživanja je podizanje svesti o<br />tome, kako je potražnja za ljudskim resursima na trži&scaron;tu rada<br />u oblasti tehničkih nauka značajna i da je stoga potrebno<br />usmeriti veći broj žena ka tim oblastima. Istraživanje je<br />sprovedeno pomoću 2192 popunjena upitnika i 45 polustrukturirana<br />intervjua. Istraživanjem je utvrđeno da jezik,<br />koji je u intersekciji sa rodom, nacionalno&scaron;ću i klasom,<br />rezultira novim konceptom nejednakosti. Takođe je dokazano<br />da su žene nedovoljno zastupljene u tehničkim oblastima, &scaron;to<br />je najvećim delom moguće pripisati rodnim stereotipima.<br />Konačno, utvrđeno je da su žene manje motivisane da<br />dosegnu visoke pozicije od mu&scaron;karaca u sistemu visokog<br />&scaron;kolstva. Autorka predlaže skup mera za re&scaron;avanje i/ili<br />ublažavanje identifikovanih izazova, npr. dekonstrukcija<br />rodnih stereotipa pomoću unapređenih nastavnih materijala u<br />osnovnim i srednjim &scaron;kolama, prilađen program učenja<br />srpskog jezika za učenike iz etničkih manjina sa ciljem<br />izbegavanja jezičke barijere na početku studija; odnosno<br />osnivanje centra za istraživanje statusa i izazova zajednica<br />etničkih manjina.</p>

Este trabalho tem como objetivo estudar a influência da geometria de suspensão do veículo nas atitudes da massa suspensa. Apresenta um confronto entre obras e autores e está segmentada em três partes; onde na primeira parte são definidos os conceitos básicos como dive, squat, lift, anti-dive, anti-squat, anti-lift e equivalente trailing-arm; na segunda parte são apresentadas as limitações e os novos conceitos definidos por R. S. Sharp e na terceira parte é apresentado o modelo dinâmico bidimensional introduzido por Fu-Cheng Wang. Apresenta um modelo virtual em sistema de multi-corpos desenvolvido no programa ADAMS, com todos os subsistemas que compõe um veículo completo. Inova ao trazer como objeto de estudo um veículo de competição (fórmula SAE) que possui como particularidade o sistema de suspensão push-rod. Surpreende com os resultados obtidos, pois, contrariam os conceitos básicos encontrados na maioria dos livros / This work has objective study the influence of suspension geometry on the sprung mass attitudes. It presents a confrontation among works and authors and this segmented in three parts; where in the first part the basic concepts are defined, dive, squat, lift, anti-dive, anti-squat, anti-lift and equivalent trailing-arm; in the second part the limitations are presented and the new concepts are defined for R. S. Sharp and in the third part are presented the bidimensional dynamic model introduced by Fu-Cheng Wang. It presents a virtual model in system of multi-bodies developed in the program ADAMS, with all the subsystems that composes a complete vehicle. It innovates when bringing such object to study one vehicle of competition (formula SAE) that it has a particularity suspension system push-rod. It surprises with results because it’s opposite of the basic concepts which is present in the majority of books

My Eyes Due See is a multidimensional examination of the “black experience” in America. The installation is composed of a single-channel video, a music composition that utilizes music samples and live instrumentation, and sculptures made up of car parts and broomsedge grass. Each of these elements arranged in space share a nuanced and complicated view of blackness through the lens of a black man decoding personal history and American history simultaneously. Autonomy is the overarching theme throughout the work as it pertains to race, identity, urban and rural environments, and the relationship between generational trauma and nostalgia.

Este trabalho tem como objetivo estudar a influência da geometria de suspensão do veículo nas atitudes da massa suspensa. Apresenta um confronto entre obras e autores e está segmentada em três partes; onde na primeira parte são definidos os conceitos básicos como dive, squat, lift, anti-dive, anti-squat, anti-lift e equivalente trailing-arm; na segunda parte são apresentadas as limitações e os novos conceitos definidos por R. S. Sharp e na terceira parte é apresentado o modelo dinâmico bidimensional introduzido por Fu-Cheng Wang. Apresenta um modelo virtual em sistema de multi-corpos desenvolvido no programa ADAMS, com todos os subsistemas que compõe um veículo completo. Inova ao trazer como objeto de estudo um veículo de competição (fórmula SAE) que possui como particularidade o sistema de suspensão push-rod. Surpreende com os resultados obtidos, pois, contrariam os conceitos básicos encontrados na maioria dos livros / This work has objective study the influence of suspension geometry on the sprung mass attitudes. It presents a confrontation among works and authors and this segmented in three parts; where in the first part the basic concepts are defined, dive, squat, lift, anti-dive, anti-squat, anti-lift and equivalent trailing-arm; in the second part the limitations are presented and the new concepts are defined for R. S. Sharp and in the third part are presented the bidimensional dynamic model introduced by Fu-Cheng Wang. It presents a virtual model in system of multi-bodies developed in the program ADAMS, with all the subsystems that composes a complete vehicle. It innovates when bringing such object to study one vehicle of competition (formula SAE) that it has a particularity suspension system push-rod. It surprises with results because it’s opposite of the basic concepts which is present in the majority of books

Tato diplomová práce byla psána při studentské zahraniční stáži, pod záštitou Evropské Unie – program „ERASMUS Student Mobility for Placement“. Stáž byla absolvována mezi prosincem 2010 a květnem 2011 ve společnosti a.d.Tramontana, mající sídlo v Palau de Santa Eulália, Španělsko. Pro kompletní návrh podvozku a odpružení jakéhokoli vozidla je nezbytná znalost mnoha technických disciplín. Tato diplomová práce se zabývá dvěma z nich – odpružení a řízení. Nejprve je rozebrána teorie, na kterou se může navázat v praktické části práce. Velká pozornost byla věnována srozumitelnosti textu a názornosti obrázků, bez zbytečných detailů, avšak bez vynechání důležitého. Tuto práci je tedy možné užít jako prvního kroku před návrhem podvozku. V další části je popsáno, jak byla probraná teorie využita při návrhu řízení u skutečného vozu, přičemž největší pozornost je věnována Ackermannově teorii řízení a geometrii zabraňující samořízení při propružení. V závěrečných částech je pozornost věnována ukázce některých z každodenních činností v malosériové výrobě automobilů – jde o zjištění maximálně možného pohybu kola při propružení a proces výroby příčných trojúhelníkových ramen včetně návrhu jejich připevnění k šasi.

Diese Dissertation widmet sich der Erfassung, Identifikation und Beschreibung von Entladungsprozessen, die an Überschlägen bei Blitzspannung auftreten. Es wird ein Messsystem entwickelt, welches die elektrischen und optischen Parameter der Entladungsprozesse an der Spitze-Spitze-Elektrodenanordnung bei standardisierter und oszillierender Blitzspannung mit hoher Empfindlichkeit und Synchronisationsgenauigkeit aufzeichnet. Mithilfe der Strommessungen und der fotografischen Aufzeichnungen von Entladungen können drei Phasen des Durchschlagprozesses identifiziert werden: In der Reihenfolge ihres Auftretens handelt es sich um die Streamerphase, die Kanalübergangsphase und die Kanalbildungsphase. Diese Phasen werden für die standardisierte und oszillierende Blitzspannung aufgezeigt, wobei Gemeinsamkeiten und Unterschiede herausgestellt werden. Anhand von statistischen Beschreibungen des Durchschlagverhaltens und des Entladungsverhaltens werden daraufhin Abhängigkeiten in den Entladungsprozessen abgeleitet. / This thesis is dedicated to the acquisition, identification and description of discharge processes, which occur under lightning impulse voltage. A measuring system has been developed that records the electrical and optical parameters of the discharge processes with a high sensitivity and synchronization accuracy on a rod-rod electrode arrangement under standardised and oscillated lightning impulse voltage. With the current measurements and the photographic records of discharges, three phases of the breakdown process can be identified. In order of their occurrence these are the streamer phase, the channel transition phase and the channel formation phase. These phases are shown for the standardised and oscillated lightning impulse voltage, whereby similarities and differences are presented in detail. Using statistical descriptions of the breakdown and the discharge behaviour, dependencies in the discharge process will be derived.