Dissertations / Theses on the topic 'Pressurized Condition'

Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2017.
This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.
Cataloged from student-submitted PDF version of thesis.
Includes bibliographical references (pages 448-467).
The nuclear industry is no exception when it comes to those affected by fouling deposit problems. Fouling deposits on fuel rods in nuclear reactors, known as crud, can cause a variety of undesirable effects including axial power shifts, accelerated corrosion, increased primary circuit radiation dose, and possible fuel failure. This study revisits the crud problem once again using a newly constructed Internally Heated Testloop For PWRs (IHTFP) and new analytical techniques, and attempt to find a way to prevent or mitigate crud, or at least better understand it. This is the first time that fuelrod coatings are examined as a way of countering crud growth. These coatings are chosen based on their surface chemical properties and robustness at PWR conditions. For the goal of gaining a better understanding of crud, this study is the first to apply fractal analysis to characterize crud. To achieve both of these goals, the IHTFP was built to obtain crud grown under the PWR thermal-hydraulic and chemical conditions. The crud-resistant coatings experiments show significantly reduced crud surface coverage, indicating reduced crud adhesion, for TiC and ZrN coatings. The results roughly agree with London-van der Waals theoretical force predictions, suggesting that London-VDW forces are responsible for the adhesion of crud to fuel cladding. This knowledge can be useful in designing better crud-resistant materials. The fractal analysis can provide a simple, effective way to characterize the macro-scale behavior of crud with its micro-scale properties. The fractal analysis experimental study found R2 values to be very close to one when applying the box-counting method to crud, which is one piece of evidence to support the usage of fractal analysis on crud. Moreover, a strong logarithmic relationship trend between fractal dimension and porosity was found. This relationship applies to both the IHTFP's and Westinghouse loop's crud, even though the two experimental setups used different crud precursors and heat flux. This could indicate that crud's fractal dimension is dependent only on porosity. This relationship could simplify crud modeling and lead to better predictions of crud's behaviors. Better predictions can lower margins, leading to more efficient reactors.
by Ittinop Dumnernchanvanit.
Ph. D.

Für den zielgerichteten Einsatz von präventiven und mitigativen Notfallmaßnahmen sowie zur Beurteilung ihrer Wirksamkeit während auslegungsüberschreitender Unfälle in Druckwasserreaktoren aber auch für Hinweise zum Störfallverlauf und für die Abschätzung der Auswirkungen auf die Anlagenumgebung müssen geeignete Störfallinstrumentierungen vorhanden sein. Insbesondere der Zustand des Reaktordruckbehälterinventars (RDB-Inventar) während der In-Vessel-Phase eines auslegungsüberschreitenden Unfalls lässt sich mit aktuellen Störfallinstrumentierungen nur stark eingeschränkt überwachen, wodurch die o. g. Forderungen nicht erfüllt werden können. Die vorliegende Arbeit beinhaltet detaillierte Untersuchungen für die Entwicklung einer Störfallinstrumentierung, welche eine durchgängige Zustandsüberwachung des RDB-Inventars während der In-Vessel-Phase eines auslegungsüberschreitenden Unfalls ermöglicht. Die Störfallinstrumentierung basiert auf der Messung und Klassifikation von unterschiedlichen Gammaflussverteilungen, welche während der In-Vessel-Phase außerhalb des Reaktordruckbehälters auftreten können. Ausgehend von der Analyse zum Stand von Wissenschaft und Technik wird der modell-basierte Ansatz für Structural Health Monitoring-Systeme genutzt, um eine grundlegende Vorgehensweise für die Entwicklung der Störfallinstrumentierung zu erarbeiten. Anschließend erfolgt eine detaillierte Analyse zu den Vorgängen während der In-Vessel-Phase und eine daraus abgeleitete Definition von Kernzuständen für einen generischen Kernschmelzunfall. Für die definierten Kernzustände werden mittels Simulationen (Monte-Carlo-Simulationen zum Gammastrahlungstransport in einem zu dieser Arbeit parallel laufenden Vorhaben) Gammaflüsse außerhalb des Reaktordruckbehälters berechnet. Die Simulationsergebnisse dienen dem Aufbau von Datenbasen für die Entwicklung und Analyse eines Modells zur Klassifikation von Gammaflussverteilungen. Für die Entwicklung des Klassifikationsmodells kommen drei diversitäre und unabhängig arbeitende Klassifikationsverfahren (Entscheidungsbaum, k-nächste-Nachbarn-Klassifikation, Multilayer Perzeptron) zur Anwendung, um die Identifikationsgenauigkeit und Robustheit der Störfallinstrumentierung zu erhöhen. Die abschließenden Betrachtungen umfassen die Validierung der Störfallinstrumentierung mittels eines Versuchstandes zur Erzeugung unterschiedlicher Gammaflussverteilungen. Im Ergebnis der Untersuchungen konnte die prinzipielle Funktionsweise der entwickelten Störfallinstrumentierung nachgewiesen werden. Unter der Voraussetzung, die Gültigkeit der definierten Kernzustände zu untermauern sowie weitere, nicht in dieser Arbeit betrachtete Kernschmelzszenarien mit in die Entwicklung der Störfallinstrumentierung einzubeziehen, steht somit insbesondere für zukünftige Kernkraftwerke mit Druckwasserreaktoren eine Möglichkeit für die messtechnische Überwachung des RDB-Inventars während auslegungsüberschreitender Unfälle bereit. Die Arbeit leistet einen wesentlichen Beitrag auf dem Gebiet der Reaktorsicherheitsforschung sowie für den sicheren Betrieb von kerntechnischen Anlagen.

Axial offset anomaly (AOA) in pressurized water reactors (PWR) refers to deviation of the measured neutron flux in the top half of the core from the predicted values. Among other difficulties, AOA reduces the shutdown margin, and may force the plant to reduce power output. AOA is believed to be caused by three related phenomena occurring in the core while operating at full power: sub-cooled nucleate boiling concentrated mainly in the upper half of the core, corrosion product deposition on the cladding surface (crud), and the deposition of boron within the porous crud layer in regions of vigorous sub-cooled boiling. This study replicates the conditions within the PWR primary coolant; specifically, the temperature, pressure, peak surface heat flux, coolant velocity and water chemistry are simulated in order to produce prototypical crud on an electrically heated Zircaloy-4 test element. At the conclusion of each test run, the heated Zircaloy-4 test element is rapidly isolated from the coolant in order to trap any soluble boron species that may be present in the crud layer. The results of this investigation indicate that prototypical crud with significant boron deposition can be produced. The deposited boron compound has been determined to be lithium tetraborate (Li2B4O7). Comparative experiments have been run to determine the effect of coolant pH, concentration and type of additives, and duration of exposure on the thickness of the crud deposit. The data obtained in this investigation can be used to validate mechanistic models for crud deposition and AOA in pressurized water reactors.

Single-phase CFD calculations are already widely applied in nuclear industry for the thermal-hydraulic design optimization of fuel assemblies (FA). In contrast, two-phase CFD-applications are still in the state of development. The work presented in this thesis shows contributions towards the detailed two-phase modeling of boiling flows under swirl conditions in sub-channel geometries of pressurized water reactors (PWR) FAs, including a realistic description of the critical heat flux (CHF)-phenomena and identification of two-phase indicators characterizing CHF-phenomena. The numerical simulations were conducted with a 3-D CFD code (STAR CD) for various types of swirl generating components in FA. New insights regarding local void distribution in sub-channels under swirl conditions were obtained, which are relevant for CHF (“bubble pockets”). Furthermore, an enhanced wall partitioning model provides a more realistic description of the steep increase of the rod temperature due to CHF. Presented validation studies showed good agreement with the available experiments under PWR conditions for the radial void distributions at non-CHF conditions as well as for the CHF prediction. The results performed in this thesis show the incentives and chances of two-phase CFD applications for the development of thermal-hydraulically optimized PWR spacer grids with regard to heat transfer and improvement to the CHF behaviour
Einphasige CFD Analysen stellen für typische thermohydraulische Fragestellungen aus dem Kernkraftwerksbereich bereits jetzt ein wichtiges Werkzeug für die Brennelement (BE)¬Auslegung dar. Die zweiphasige CFD-Modellierung befindet sich dagegen in der Entwicklungsphase. Die in dieser Dissertation präsentierten Arbeiten zeigen Fortschritte für die detaillierte zweiphasige Modellierung drallbehafteter Strömungen im Unterkanal eines BEs des Druckwasserreaktors (DWR) einschließlich der realistischen Beschreibung des kritischen Wärmestroms (CHF) sowie die Bestimmung zweiphasiger Indikatoren, welche das Auftreten von CHF-Phänomen beschreiben. Verschiedene drallerzeugende Komponenten im BE wurden mit dem 3-D CFD-Code STAR-CD modelliert. Es wurden neue Erkenntnisse zur lokalen Blasenverteilung in Unterkanälen unter Drallbedingungen gewonnen, die für CHF relevant sind (“bubble pockets”). Durch eine Modifikation des Wärmeübergangsmodells (heat partitioning model) wird der starke Anstieg der Stabtemperatur infolge CHF realistischer beschrieben. Die durchgeführten Validierungen zeigen eine gute Übereinstimmung mit verfügbaren Experimenten unter DWR-Bedingungen für die radialen Blasenverteilungen und für die Bestimmung von CHF. Die vorliegenden Ergebnisse dieser Dissertation verdeutlichen den Nutzen und die Möglichkeiten von zweiphasigen CFD-Anwendungen für die Entwicklung und die thermohydraulische Optimierung von DWR-Abstandshaltern bezüglich des Wärmeübergangs und der Verbesserung des CHF-Verhaltens
Модели однофазовой среды в вычислительной гидродинамике (англ. CFD) являются уже сейчас важным инструментом для решения типичных термогидравлических задач в ядерной энергетике, например, при конструировании тепловыделяющих сборок (ТВС). Двухфазовое моделирование, в сравнении с однофазовым, находится на сегодняшний момент в стадии развития. Данная диссертация связана с совершенствованием двухфазовой модели в направлении улучшения детализации вихревого течения внутри ячейки ТВС в условиях работы двухконтурного ядерного реактора (тип PWR). Также в работе показана возможность более реалистичного описания феномена кризиса теплоотдачи и определения двухфазовых индикаторов, характеризующих критический тепловой поток (англ. CHF). Комплекс расчетов выполнен для различных интенсификаторов теплоотдачи, размещенных на дистанционирующих решетках TBC. Расчеты производились с помощью программного обеспечения STAR-CD, позволяющего моделировать трехмерные гидродинамические системы. Полученные новые данные о локальном распределении пузырьков в ячейках с вихревым течением дали важную информацию для идентификации критического теплового потока. Усовершенствование модели теплоотдачи на поверхности тепловыделяющего элемента (ТВЭЛ) позволило более реалистично описать резкое повышение температуры на поверхности ТВЭЛа при достижении критических условий. Полученные результаты численного моделирования для радиальных распределений пузырьков при нормальных условиях работы PWR и также для определения критического теплового потока показали хорошее совпадение с известными экспериментальными данными. Представленные в диссертации результаты показывают возможности применения двухфазовых CFD-расчётов для разработки и термогидравлической оптимизации дистанционирующих решеток с целью улучшения теплообмена и характеристик критического теплового потока в двухконтурном ядерном реакторе типа PWR

Flow boiling heat transfer allows for the dissipation of large amounts of heat. In this work, the effect of heat flux and pressure on flow boiling of liquid refrigerant R-134a is studied in a vertical thin channel. The experimental setup mimics a refrigeration cycle and specifically looks at the effect of pressure and wall heat flux on the departure size and bubble generation rate. The experimental setup consists of a closed loop which includes a vertical narrow rectangular channel and two synchronized high speed cameras for optical measurements at either sides of the channel. The setup is built to employ an accurate measurement technique to define wall temperatures of the representative flow boiling process. Instead of using thermocouples on the surface channel, the thermochromic liquid crystallography (TLC) technique is used to determine non-invasively the heater surface temperature at high temporal and spatial resolution. The TLC interval range is 30-50??C. The TLC is attached to a Fecralloy heating section. The high speed Prosilica cameras simultaneously capture, colored TLC images as well as bubble nucleation and departure at very high frame rates. Experiments on subcooled flow boiling heat transfer have been conducted with refrigerant R-134a under a mass flux range of 484.838 kg/m??s to 1212.1 kg/m??s. With the low mass flux, the wall heat flux ranged from 167.2 to 672.1 kW/m??, the inlet subcooling ranged from 0.35??C to 16.55??C, the system pressure ranged from 621 kPa to 1034 kPa. At high mass flux, the wall heat flux ranged from 329.8 kW/m?? to 744 kW/m??, the inlet subcooling from 0.16??C to 17.21??C, and the system pressure from 621 kPa to 1034 kPa. A parametric study was done by maintaining various input parameters constant. From the high speed images, bubble parameters such as size and frequency are calculated. Temperature contours are utilized to determine the surface wall temperature at specific points.; Sequential wall temperatures are traced over a short period of time to understand the cooling effects. The bubble propagation and coalescence are also visualized. Results show that bubble size and frequency increased with heat flux at any particular pressure. At higher pressure, the trend would be for the bubble size to decrease; however, the inlet subcooling and heat flux also affect bubble size. The bubble frequency is also seen to be affected by the inlet subcooling and the heat flux. Even though the inlet subcooling is maintained approximately constant, any slight decrease in subcooling increased bubble growth rate. Another trend that is observed is that at higher the heat flux, the bubble generation frequency is faster; however no specific trend is observed for wall superheat. With an increase in heat flux, the wall superheats are expected to increase; however, the localized nature of the nucleation activity sites is seen to affect the results. The variables are non-dimensionalized to note trends in parameters. In summary, the data analysis demonstrates that both heat flux and pressure significantly influence the bubble generation rate, size, propagation and coalescence.
ID: 030646273; System requirements: World Wide Web browser and PDF reader.; Mode of access: World Wide Web.; Thesis (M.S.A.E.)--University of Central Florida, 2011.; Includes bibliographical references (p. 107-115).
M.S.A.E.
Masters
Mechanical and Aerospace Engineering
Engineering and Computer Science
Aerospace Engineering; Thermofluid Aerodynamics Systems Track

Single-phase CFD calculations are already widely applied in nuclear industry for the thermal-hydraulic design optimization of fuel assemblies (FA). In contrast, two-phase CFD-applications are still in the state of development. The work presented in this thesis shows contributions towards the detailed two-phase modeling of boiling flows under swirl conditions in sub-channel geometries of pressurized water reactors (PWR) FAs, including a realistic description of the critical heat flux (CHF)-phenomena and identification of two-phase indicators characterizing CHF-phenomena. The numerical simulations were conducted with a 3-D CFD code (STAR CD) for various types of swirl generating components in FA. New insights regarding local void distribution in sub-channels under swirl conditions were obtained, which are relevant for CHF (“bubble pockets”). Furthermore, an enhanced wall partitioning model provides a more realistic description of the steep increase of the rod temperature due to CHF. Presented validation studies showed good agreement with the available experiments under PWR conditions for the radial void distributions at non-CHF conditions as well as for the CHF prediction. The results performed in this thesis show the incentives and chances of two-phase CFD applications for the development of thermal-hydraulically optimized PWR spacer grids with regard to heat transfer and improvement to the CHF behaviour.
Einphasige CFD Analysen stellen für typische thermohydraulische Fragestellungen aus dem Kernkraftwerksbereich bereits jetzt ein wichtiges Werkzeug für die Brennelement (BE)¬Auslegung dar. Die zweiphasige CFD-Modellierung befindet sich dagegen in der Entwicklungsphase. Die in dieser Dissertation präsentierten Arbeiten zeigen Fortschritte für die detaillierte zweiphasige Modellierung drallbehafteter Strömungen im Unterkanal eines BEs des Druckwasserreaktors (DWR) einschließlich der realistischen Beschreibung des kritischen Wärmestroms (CHF) sowie die Bestimmung zweiphasiger Indikatoren, welche das Auftreten von CHF-Phänomen beschreiben. Verschiedene drallerzeugende Komponenten im BE wurden mit dem 3-D CFD-Code STAR-CD modelliert. Es wurden neue Erkenntnisse zur lokalen Blasenverteilung in Unterkanälen unter Drallbedingungen gewonnen, die für CHF relevant sind (“bubble pockets”). Durch eine Modifikation des Wärmeübergangsmodells (heat partitioning model) wird der starke Anstieg der Stabtemperatur infolge CHF realistischer beschrieben. Die durchgeführten Validierungen zeigen eine gute Übereinstimmung mit verfügbaren Experimenten unter DWR-Bedingungen für die radialen Blasenverteilungen und für die Bestimmung von CHF. Die vorliegenden Ergebnisse dieser Dissertation verdeutlichen den Nutzen und die Möglichkeiten von zweiphasigen CFD-Anwendungen für die Entwicklung und die thermohydraulische Optimierung von DWR-Abstandshaltern bezüglich des Wärmeübergangs und der Verbesserung des CHF-Verhaltens.
Модели однофазовой среды в вычислительной гидродинамике (англ. CFD) являются уже сейчас важным инструментом для решения типичных термогидравлических задач в ядерной энергетике, например, при конструировании тепловыделяющих сборок (ТВС). Двухфазовое моделирование, в сравнении с однофазовым, находится на сегодняшний момент в стадии развития. Данная диссертация связана с совершенствованием двухфазовой модели в направлении улучшения детализации вихревого течения внутри ячейки ТВС в условиях работы двухконтурного ядерного реактора (тип PWR). Также в работе показана возможность более реалистичного описания феномена кризиса теплоотдачи и определения двухфазовых индикаторов, характеризующих критический тепловой поток (англ. CHF). Комплекс расчетов выполнен для различных интенсификаторов теплоотдачи, размещенных на дистанционирующих решетках TBC. Расчеты производились с помощью программного обеспечения STAR-CD, позволяющего моделировать трехмерные гидродинамические системы. Полученные новые данные о локальном распределении пузырьков в ячейках с вихревым течением дали важную информацию для идентификации критического теплового потока. Усовершенствование модели теплоотдачи на поверхности тепловыделяющего элемента (ТВЭЛ) позволило более реалистично описать резкое повышение температуры на поверхности ТВЭЛа при достижении критических условий. Полученные результаты численного моделирования для радиальных распределений пузырьков при нормальных условиях работы PWR и также для определения критического теплового потока показали хорошее совпадение с известными экспериментальными данными. Представленные в диссертации результаты показывают возможности применения двухфазовых CFD-расчётов для разработки и термогидравлической оптимизации дистанционирующих решеток с целью улучшения теплообмена и характеристик критического теплового потока в двухконтурном ядерном реакторе типа PWR.

D. Tech. (Department of Civil Engineering and Building, Faculty of Engineering and Technology), Vaal University of Technology
Growing demand for water due to increasing populations, industrialisation and water consuming lifestyles puts stress on existing water supply systems. To cater for the rising demand, water distribution networks are expanded beyond their design capacities and this creates transient “low-pressure-open-channel flow” (LPOCF) conditions. Current water supply models use “demand driven approach” (DDA) methodology which is not able to simulate transient LPOCF conditions, that poses an impediment to management/analysis of pressure-deficient networks. With a case study of the water supply network of Kampala City, LPOCF conditions were studied in this research. A “pressure/head driven approach” (PDA/HDA) was used in order to determine what demand is enabled by particular nodal pressures. Conversion of free surface to pressurised flow was analysed and modelled, with a view to clearly understanding occurrence of this phenomenon. The research demonstrated that if adequate pressures and flows are to be maintained, effectiveness of the water distribution network should be given as much attention as water production capacity. The research also indicated that when network pressures are low, the head-driven approach to water distribution modelling gives more accurate results than the traditional demand-driven methodology. Coexistence of free-surface and pressurised flow in networks prone to LPOCF conditions was confirmed and modelled. Results obtained highlighted the advantages of developing fully dynamic and transient models in the solution of transient LPOCF conditions in water distribution networks. Models developed allow application of PDA/HDA and DDA methodologies in systems that may exhibit LPOCF conditions thus enabling identification, understanding and analysis of the status of all sections of the network. These culminated in the development of a DSS to guide operational decisions that can be made to optimise network performance.

Cette thèse est dédiée à l'étude du comportement des aciers inoxydables sous irradiation exposés en condition primaire des réacteurs à eau pressurisée (REP). Le potentiel électrochimique de l'acier inoxydable austénitique 316L et les paramètres environnementaux comme la teneur en hydrogène, ont été mesurés de façon continue à haute température (HT) et haute pression (HT) grâce à un dispositif expérimental unique, la cellule HTHP. Deux sources d'irradiation ont été utilisées: les protons et les électrons. Le comportement électrochimique du 316L s'est avéré similaire dans les deux cas: (i) une augmentation du potentiel sous irradiation de l'ordre de la dizaine de millivolts ("réponse oxydative"); (ii) l'augmentation de la teneur en hydrogène diminue cette augmentation du potentiel sous irradiation; (iii) une synergie est observée entre le vieillissement à 300 C et la fluence qui conduit également à limiter la réponse oxydative sous irradiation. Les observations du film passif d'oxydes mettent en évidence la présence de nickel métallique dans l'ensemble des oxydes (interne et externe) en présence d'hydrogène, sans irradiation. Après les irradiations les plus fortes, des cavités (piqûres) sont observées en surface du 316L. Ces défauts sont attribués à l'effet de la radiolyse de l'eau et de l'irradiation de la couche passive. La radiolyse influence également l'évolution de la chimie du milieu primaire qui devient plus acide et plus oxydante. Il en résulte une augmentation du relâchement des cations métalliques et la présence d'hématite ( a-Fe2O3) sur le film d'oxyde externe de l'acier inoxydable lorsque les cavités (piqûres) sont formées
The dissertation focuses on the behaviour of stainless steel under irradiation and exposed to primary PWR conditions. The electrochemical potential of austenitic 316L stainless steel and the environmental parameters (hydrogen pressure, temperature, etc. ,) have been measured continuously at high temperature (HT) and high pressure (HP) under irradiation, using a unique experimental HTHP working cell. Two sources of irradiation, proton and electron beams, have been employed in the study. A high similarity of electrochemical behaviour under both types of irradiations has been observed: (i) an oxidative potential response under irradiation (few tens of millivolts); (ii) an increase in the hydrogen pressure reduces the oxidative potential response; (iii) a synergetic effect of thermal ageing and fluence leading to a decrease of the oxidative response under irradiation. The observations of the oxide film showed that without irradiation, metallic nickel in the inner and outer oxide films has been observed under a high hydrogen pressure. Under irradiation, um scale cavities (pits) have been observed in the strongly electron irradiated oxide film formed on 316L stainless steel. These defects are induced by the effect of irradiation of the passive film and water radiolysis. It is also shown that water radiolysis influences the PWR water chemistry by making it become a stronger oxidant at the oxide/solution interface. As a result, the release of metallic cations is increased and a-Fe2O3 hematite has been observed on the irradiated outer oxide film where cavities were formed

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This paper proposes biodiesel production by non-catalytic process using ethanol in pressurized conditions in continuous mode of Macaúba oil (Acrocomia aculeata), evaluating the effect of process variables (temperature, pressure, mass ratio oil: alcohol and addition of cosolvent) on the conversion of the reaction in terms of fatty acid esters to determine the best experimental conditions. As well as envisioned, a study of changes in driving the reaction in pressurized conditions, seeking to decrease the reaction conditions of temperature and pressure. The results show this study that regarding obtaining better rates of mass transfer, the use of fillings of glass spheres presented performed better. Through planning Plackett Burman 12, it was found that the variables that showed greater significance in the process were the weight ratio (alcohol: oil) and the addition of cosolvent, besides that, it was observed that the results for the decomposition were satisfactory (<5.0%). With this we was performed a kinetic study, based on these two variables, where it was found that the use of a larger amount of alcohol in the process did not prove to be beneficial, already the addition of cosolvent played a positive role enabling reduction in the time and reaction temperature, since the condition of 275 º C was achieved a yield of 89.62%.
O presente trabalho propõe a produção de biodiesel pelo processo não catalítico utilizando etanol em condições pressurizadas em modo contínuo do óleo de Macaúba (Acrocomia aculeata), avaliando o efeito das variáveis de processo (temperatura, pressão, razão mássica óleo:álcool e adição de cossolvente) sobre a conversão da reação em termos de ésteres de ácidos graxos visando determinar as melhores condições experimentais. Vislumbrou-se também um estudo de modificações na condução da reação em condições pressurizadas, buscando diminuir as condições reacionais de temperatura e pressão. Os resultados obtidos demonstram que, no estudo referente a obtenção de melhores taxas de transferência de massa, a utilização de recheios de esferas de vidro apresentaram melhor desempenho. Através do planejamento Plackett Burman 12, verificou-se que as variáveis que apresentaram maior significância no processo foram a razão mássica (álcool:óleo) e a adição de cossolvente, além de que, observou-se que os resultados referentes a taxa de decomposição apresentaram-se satisfatórios (<5,0%). Com isso realizou-se um estudo cinético baseado nestas duas variáveis, onde verificou-se que a utilização de uma maior quantidade de álcool no processo não apresentou-se benéfico, já a adição de cossolvente desempenhou um papel positivo ao possibilitar a diminuição do tempo e temperatura de reação, uma vez que na condição de 275ºC houve um rendimento de 89,62%.

碩士
國立成功大學
水利及海洋工程學系
87
Bridge become partially or totally submerged during large floods are subjectto pressure-flow scour. Under this flow condition, the velocity and bed scour at the bridge deck are much larger than that under non-pressure situations. In order to understanding the contraction scour at the bridge deck under pressurized flow condition, the first course is to analyze velocity and discharge flowing through the bridge deck. The experiments were conducted to study the flow field, discharge, and water level at the bridge deck under the pressurized flow condition. A model bridge deck was tested under a variety of controlled pressurized flow conditions, and the experimental data were all recorded. The experimental data were substituted into energy equation and continuity equation to calculate energy loss, energy loss coefficient. An equation to evaluated flow discharge related the energy loss was derived. The deviation from actual discharge and calculated discharge were within 10％. The velocity data were compared with the log-law velocity distribution to predict the fore influence region (FIR) and behind influence region (BIR). The result showed that when the upstream Fround No. was smaller than 0.1 and the contraction ratio was smaller than 0.267, the maximum FIR would be within one quarter width of the bridge deck and the BIR would be within 4.7 width of the bridge deck.

碩士
大葉大學
機械工程研究所碩士在職專班
97
Pressure tubes are used in various industries to transport high temperature steam, gas, liquid, and other fluids. Some components are usually required in pressurized tubing systems to relieve the high stress due to thermal expansion. Among them, U-tube is a kind which plays an important role. It is mainly serves as reinforcement and connection usage. In this study, the structural behavior of a non-isothermal U-tube under its simulated operating condition is investigated based on finite element analysis in conjunction with heat transfer and fluid mechanics theories. The investigation includes the structural stress analysis, temperature distribution analysis, the modal analysis, as well as the design optimization. A program based on the use of ANSYS is then provided for the users to select the optimal thickness of a U-tube under a safe operating condition.

Nowadays, the management of pressurized irrigation networks requires plenty of information to provide an efficient and reliable service to farmers. An approach called MASSPRES is being developed as a collaboration between FAO and CIHEAM-Bari with the goal of developing a reliable modernization strategy and improving the performance of pressurized irrigation systems. Mapping the perturbation, which is represented by the unsteady state flow analysis, is one of the most significant steps of this approach. The perturbation in irrigation networks is often created when sudden changes in flow rates occur in the pipes. This is essentially due to the manipulation of hydrants (service outlets) according the operational scenarios called configurations. During the perturbation occurrence, pressure waves propagate through the networks pipes that may lead to a signification pressure variation. This variation could expose the irrigation system’s components to a substantial danger that could cause significant damage. To model such a phenomenon, several computational algorithms have been developed. The majority of these models aimed to simulate the unsteady state conditions induced by the farmer’s behavior. The most recent ones are efficient enough to provide a good image of the perturbation occurrence through different indicators, however, one of the main draw backs of such model is the significantly high time and computational costs. In the present work, two different generations of models were developed. The first is a directly programmed model that was devaloped based on the method of characteristics and two indicators have been introduced: i) The hydrant risk indicator (HRI), which is defined as the ratio between the participation probability of hydrant no. x in the riskiest configurations and its total number of participations; and ii) the relative pressure exceedance (RPE), which provides the variation of the unsteady state pressure with respect to the nominal pressure. The two indicators could help managers better understand the network behavior with respect to the perturbation by defining the riskiest hydrants and the potentially affected pipes. Although, knowing the riskiest hydrants in the network is an important piece of information, managing ramified networks in real time will remain a difficult task to handle in real time. Thus, the need of developing a real time Decision Support System (RTDSS) that could process such information and guide the manager in real time is crucial. For this aim, two thousand configurations (operational scenarios) were simulated using the directly programmed model from the first step and fed to train a new model based on deep learning with the objective of forecasting the maximum pressure occurred due to the perturbation at each section. The occurred pressure is represented as classes according to the case sensitivity and the required precision. Steps of 1, 2 and 3 bars were simulated. The model proved to be significantly time saving compared to previous approaches as the results are produced instantaneously with a forecasting accuracy of 85 %. Furthermore, using the confusion matrix, the error committed by the model is of one class lower or higher that may be considered tolerable according to the system sensitivity. This approach was applied on a pressurized on-demand irrigation system located in south of Italy that consists of 19 hydrants and covers 57 hectares. Nonetheless, the deep learning-based model needs to be trained on each section. Thus, as a main step of the method of characteristics, the network was discretized into 1017 sections of 3 meter each. Training the deep learning model for such number of sections is not practical and time consuming. For this reason, a code was developed using autoencoding combined with t-distributed stochastic neighbor embedding (t-SNE) algorithm for features extraction and their visualization respectively. It is principally to cluster the sections according to their behavior to the perturbation, thus, reduce the number of trainings of the previously mentioned model. Nine zones of similar behavior were determined by the present developed code and the deep learning model will be trained only on these zones representing all the sections. The two last developed codes could be integrated for a decision support system (DSS) for modelling the perturbation in the on-demand pressurized irrigation networks that would add a significant contribution to provide practical recommendations for real-time decision-making processes. which was not possible using directly programmed software.

碩士
中原大學
機械工程學系
85
Ever since the occurrence of the Three Mile Island Accident in 1979, it became increasingly important for an in-depth understanding of the thermal-hydraulic (T-H) phenomena associated with the uncovering of the fuel rods during an accident. In the meantime, evaluation of the core behavior resulting from the loss-of-coolant accidents (LOCAs) has long become one the key issues needed to be addressed for the design basis accidents (DBAs) related to the design of a nuclear power plant. In the Final Safety Analysis Report (FSAR) of the Third Nuclear Power Station owned by the Taiwan Power Company (TPC), it was indicated that after the initiation of a DBA LOCA, the peak cladding temperature (PCT) of the fuel rods reached 2199.9℉, which is almost the same as the upper temperature limit of 2200℉ set by the nuclear regulatory authority. In addition, it is commonly believed that, after more than ten years of operation of a nuclear plant, such as the Third Nuclear Power Station of TPC, the percentage of tube blockage for the steam-generator (S-G) assembly or the actual flow rates associated with the emergency core cooling systems (ECCSs) may be quite different from what have been used for the FSAR analyses. Thus it is necessary to perform the LOCA analyses based on the current realistic conditions of the plant. 　　This study used RELAP5YA T-H code, developed by the Yankee Atomic Company, for the LOCA analyses of the Third Nuclear Power Station of TPC. Even though this code lacks the capability for the modeling of the omission of the water inventory in the region below the reactor core during the reactor vessel blow-down, this deficiency was made-up by raising the temperature of the injecting water for the ECCS flow. For the LOCA analyses done for this study, the percentage of blockage of the S-G tubes was raised from a typical value of 1％ to 5％. Also, a number of sensitivity studies were carried out using various values of the discharge coefficients for the breaks. The results obtained in this study indicated that the PCT of the fuel rods for all cases studied was 1548.5℉, which is much below the upper temperature limit of 2200℉ set by the nuclear regulatory authority.

Research Doctorate - Doctor of Philosophy (PhD)
Drives to reduce carbon dioxide emissions and improve efficiency make pressurised gasification an attractive option in future coal utilisation technologies. Process conditions in pressurised gasification differ from conventional entrained flow combustion in pressure, atmosphere, peak temperature and heating rate, yet there is sparse literature concerning coal behaviour under pressurised conditions. Previous work suggests that bituminous coals can show enhanced plasticity at high pressures and this phenomenon may not be predicted by standard tests of coking properties. Previous modelling of char reactivity and burnout in combustion and gasification has failed to take account of the petrographic variability of coals. Current work to improve the predictive capacity of these models requires evaluation of the effects of different macerals and of char preparation pressure on char behaviour. Prior studies of whole coals subjected to high pressure and high temperature conditions have shown that daughter char morphology is influenced by particle heating rate, the size distribution of the feed coal, furnace pressure, feed rate, coal rank and the parent coal petrography. Chars were produced by pyrolysis at 1100 or 1300 °C and 1, 5, 8, 10 and 15 atm furnace pressure, and by combustion at 1100 °C and 1 atm furnace pressure, from a suite of East Australian bituminous coals. The characteristics of the chars and their parent feed coals were quantified using semi-automated image analysis, as well as petrographic, particle size and chemical analyses. Relationships between the morphology of the chars and properties of the parent coal and furnace pressure were established. Daughter char morphology and volatile yield was found to be related to the petrographic composition of the parent feed coals, their full reflectance profiles and the char preparation pressure. Chars derived from vitrinite-rich lithotypes and those prepared under high pressure conditions show larger mean diameters, porosities, sphericities and proportions of porous char types. Volatile yield is related to the vitrinite content of the lithotype. A parameter derived from full coal reflectograms proves to be effective for prediction of char morphology and trends in volatile yield. The Carbon Burnout Kinetic model is improved in its predictive value by including parent coal vitrinite content as an input parameter and could be further improved by utilising the full coal reflectogram parameter.

Für den zielgerichteten Einsatz von präventiven und mitigativen Notfallmaßnahmen sowie zur Beurteilung ihrer Wirksamkeit während auslegungsüberschreitender Unfälle in Druckwasserreaktoren aber auch für Hinweise zum Störfallverlauf und für die Abschätzung der Auswirkungen auf die Anlagenumgebung müssen geeignete Störfallinstrumentierungen vorhanden sein. Insbesondere der Zustand des Reaktordruckbehälterinventars (RDB-Inventar) während der In-Vessel-Phase eines auslegungsüberschreitenden Unfalls lässt sich mit aktuellen Störfallinstrumentierungen nur stark eingeschränkt überwachen, wodurch die o. g. Forderungen nicht erfüllt werden können. Die vorliegende Arbeit beinhaltet detaillierte Untersuchungen für die Entwicklung einer Störfallinstrumentierung, welche eine durchgängige Zustandsüberwachung des RDB-Inventars während der In-Vessel-Phase eines auslegungsüberschreitenden Unfalls ermöglicht. Die Störfallinstrumentierung basiert auf der Messung und Klassifikation von unterschiedlichen Gammaflussverteilungen, welche während der In-Vessel-Phase außerhalb des Reaktordruckbehälters auftreten können. Ausgehend von der Analyse zum Stand von Wissenschaft und Technik wird der modell-basierte Ansatz für Structural Health Monitoring-Systeme genutzt, um eine grundlegende Vorgehensweise für die Entwicklung der Störfallinstrumentierung zu erarbeiten. Anschließend erfolgt eine detaillierte Analyse zu den Vorgängen während der In-Vessel-Phase und eine daraus abgeleitete Definition von Kernzuständen für einen generischen Kernschmelzunfall. Für die definierten Kernzustände werden mittels Simulationen (Monte-Carlo-Simulationen zum Gammastrahlungstransport in einem zu dieser Arbeit parallel laufenden Vorhaben) Gammaflüsse außerhalb des Reaktordruckbehälters berechnet. Die Simulationsergebnisse dienen dem Aufbau von Datenbasen für die Entwicklung und Analyse eines Modells zur Klassifikation von Gammaflussverteilungen. Für die Entwicklung des Klassifikationsmodells kommen drei diversitäre und unabhängig arbeitende Klassifikationsverfahren (Entscheidungsbaum, k-nächste-Nachbarn-Klassifikation, Multilayer Perzeptron) zur Anwendung, um die Identifikationsgenauigkeit und Robustheit der Störfallinstrumentierung zu erhöhen. Die abschließenden Betrachtungen umfassen die Validierung der Störfallinstrumentierung mittels eines Versuchstandes zur Erzeugung unterschiedlicher Gammaflussverteilungen. Im Ergebnis der Untersuchungen konnte die prinzipielle Funktionsweise der entwickelten Störfallinstrumentierung nachgewiesen werden. Unter der Voraussetzung, die Gültigkeit der definierten Kernzustände zu untermauern sowie weitere, nicht in dieser Arbeit betrachtete Kernschmelzszenarien mit in die Entwicklung der Störfallinstrumentierung einzubeziehen, steht somit insbesondere für zukünftige Kernkraftwerke mit Druckwasserreaktoren eine Möglichkeit für die messtechnische Überwachung des RDB-Inventars während auslegungsüberschreitender Unfälle bereit. Die Arbeit leistet einen wesentlichen Beitrag auf dem Gebiet der Reaktorsicherheitsforschung sowie für den sicheren Betrieb von kerntechnischen Anlagen.:1 Einleitung 2 Analyse zum Stand von Wissenschaft und Technik 2.1 Sicherheit in deutschen Kernkraftwerken mit Druckwasserreaktor 2.1.1 Mehrstufenkonzept 2.1.2 Störfallinstrumentierungen 2.2 Auslegungsüberschreitende Unfälle mit Kernschmelze in DWR 2.2.1 Auslösende Ereignisse 2.2.2 Grundlegender Ablauf eines auslegungsüberschreitenden Unfall mit Kernschmelze 2.3 Strahlungstechnik, Strahlungsmesstechnik 2.3.1 Grundlagen der Strahlungstechnik 2.3.2 Wechselwirkungen von Gammastrahlung mit Materie 2.3.3 Messung ionisierender Strahlung 2.4 Verfahren und Methoden der Zustandsüberwachung 2.4.1 Zustandsüberwachung 2.4.2 Structural Health Monitoring 2.4.3 Mustererkennung 2.4.4 Entscheidungsbäume 2.4.5 k-nächste-Nachbarn-Klassifikation 2.4.6 Künstliche neuronale Netze 2.5 Schlussfolgerungen aus der Analyse zum Stand von Wissenschaft und Technik 2.5.1 Zusammenfassung zum Kapitel 2 2.5.2 Zielstellung, Aufbau und Abgrenzung der Arbeit 3 Analyse der In-Vessel-Phase und Definition von Kernzuständen 3.1 Detaillierte Analyse der In-Vessel-Phase 3.1.1 Auftretende Temperaturbereiche 3.1.2 Vorgänge während der frühen In-Vessel-Phase 3.1.3 Vorgänge während der späten In-Vessel-Phase 3.1.4 Spaltproduktfreisetzung 3.2 Definition von Kernzuständen für einen generischen Kernschmelzunfall 3.3 Zusammenfassung zum Kapitel 3 4 Datenbasen zur Entwicklung und Analyse des Klassifikationsmodells 4.1 Beschreibung der Monte-Carlo-Simulationsmodell 4.2 Beschreibung der Simulationsergebnisse und Merkmalsextraktion 4.3 Datenbasis zur Entwicklung 4.4 Datenbasen zur Analyse 4.5 Zusammenfassung zum Kapitel 4 5 Entwicklung und Analyse des Klassifikationsmodells 5.1 Beschreibung des Klassifikationsmodells 5.2 Teilmodell 1 - Entscheidungsbaum 5.2.1 Entwicklung 5.2.2 Analyse der Identifikationsgenauigkeit 5.3 Teilmodell 3 - k-nächste-Nachbarn-Klassifikation 5.3.1 Entwicklung 5.3.2 Analyse der Identifikationsgenauigkeit 5.4 Teilmodell 3 - Multilayer Perzeptron 5.4.1 Trainings- und Testdatenbasis 5.4.2 Entwicklung 5.4.3 Analyse der Identifikationsgenauigkeit 5.5 Teilmodell 4 - Vergleichsalgorithmus 5.5.1 Entwicklung 5.5.2 Analyse der Identifikationsgenauigkeit 5.6 Analysen zur Robustheit des Klassifikationsmodells 5.6.1 Ausfall einzelner Gammastrahlungsdetektoren 5.6.2 Gleichzeitiger Ausfall mehrerer Gammastrahlungsdetektoren 5.7 Zusammenfassung und Schlussfolgerungen für das Kapitel 5 6 Validierung der Kernzustandsüberwachungsverfahren 6.1 Zielstellung und Vorgehensweise 6.2 Versuchstand zur Validierung 6.2.1 Aufbau 6.2.2 Funktionsweise 6.3 Anpassung der Kernzustandsüberwachungsverfahren an den Versuchsstand 6.4 Validierungsexperimente 6.4.1 Experiment 1 - Füllstandsänderungen 6.4.2 Experiment 2 - Quellenbewegungen 6.4.3 Experiment 3 - Füllstandsänderungen, Quellenbewegungen und Änderung von Profilkonturen 6.5 Zusammenfassung und Schlussfolgerungen für das Kapitel 6 7 Zusammenfassung und Ausblick

碩士
國立成功大學
航空太空工程學系碩博士班
100
In the present study, a numerical model has been developed for a pressurized, pulverized-coal, entrained-bed gasifier by the commercial CFD software, ANSYS-FLUENT. The accuracy for the predicted composition of the outlet syngas is investigated for different combustion models. The influence of the operating conditions on the composition of the outlet syngas is also examined. Three different combustion models including non-premixed equilibrium, non-premixed flamelet, and finite-rate/eddy dissipation model, are investigated. The results obtained from the present computations show that the predicted syngas composition by the non-premixed flamelet model is in the best agreement with the experimental data. The non-premixed equilibrium model, however, leads to a composition of the outlet syngas more due to combustion. The concentrations of CO, H2, and CO2 are over-estimated by the finite-rate/eddy-dissipation model. The present study also indicates that the reaction parameters of water-gas shift reaction significantly affect the outlet syngas composition. The effects of the oxygen/carbon ratio and the operating pressure on the gasification performance are studied in the present parametric study. The results show that a lower oxygen/carbon ratio leads to higher fractions of gasification species such as CO and H2, and a lower fraction of combustion species such as CO2. A lower operating pressure results in a lower char conversion rate, and the gasification zone is not conspicuous. With a higher operating pressure, the char conversion rate increases. The mole fractions of CO and H2 at outlet increase, while that of CO2 decreases.