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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.
281

[pt] ADEQUAÇÃO ESTRATÉGICA DE PROJETOS: ESTUDO DE CASO DA ELETRONUCLEAR / [en] PROJECT STRATEGIC FIT: A CASE STUDY OF ELETRONUCLEAR

EDCLER FELIX MAYRINK 03 September 2008 (has links)
[pt] Os princípios de gerenciamento de projetos têm alcançado nos últimos anos um grande interesse por parte das organizações, com objetivos de foco operacional em realizações eficazes dentro do custo, prazo e qualidade planejadas. No entanto, muito pouco se fez para reconhecer a disciplina gerenciamento de projetos como uma das core competencies para a composição do diferencial competitivo na estratégia empresarial selecionada. Esta pesquisa tem como objetivo principal o desenvolvimento de um estudo para averiguar se existe adequação entre os processos da disciplina gerenciamento de projetos e a estratégia da empresa pesquisada. A pesquisa foi desenvolvida por meio de estudo de caso único, para o qual foi selecionada como unidade de análise uma empresa governamental: a Eletrobrás Termonuclear S.A. - Eletronuclear. A coleta de dados foi realizada de acordo com o princípio de triangulação de diferentes métodos (YIN, 2003), e: 1) investigação documental (impressa, telematizada, eletrônica); 2) levantamento de percepções com auxílio de questionário estruturado de pesquisa; 3) levantamento de percepções complementares por meio de entrevistas. As interpretações e análises efetuadas dos dados coletados foram fundamentadas no referencial teórico utilizando-se o modelo genérico-integrativo de Macedo-Soares (2001b). Os resultados evidenciaram algumas inconsistências entre os processos da disciplina gerenciamento de projetos e a estratégia da empresa. Permitiram identificar fatores organizacionais que contribuem e outros que não contribuem para a adequação estratégica de projetos. Na conclusão do trabalho, são compartilhadas lições que a pesquisa focada na Eletronuclear trouxe para outras empresas. / [en] In recent years, organizations have become increasingly interested in the principles of project management in order to enhance the operational effectiveness of their undertakings in terms of planned cost, schedule and quality. However, little has been done in the way of recognizing the discipline of project management as one of the core competencies constituting the competitive differential of the business strategy selected. The main objective of this study is to ascertain whether the processes of the project management discipline fit the strategy of the firm at issue. The study adopted the single case study method, focusing on the government firm Eletrobrás Termonuclear S.A. - Eletronuclear. Data collection was performed in accordance with the method triangulation principle (YIN, 2003), together with 1) documental investigation (printed, telematic, electronic); 2) a perceptions survey using a structured research questionnaire; 3) a complementary perceptions survey through interviews. The data collected was analyzed and interpreted using Macedo-Soares` (2001b) generic integrative model. The results evidenced some inconsistencies between the processes of the project management discipline and the firm´s strategy. They permitted the identification of organizational factors that did or did not contribute to projects´ strategic fit. The study concludes by sharing the lessons for other firms that could be drawn from the Electronuclear case.
282

The Development of a Multi-Objective Optimization and Preference Tool to Improve the Design Process of Nuclear Power Plant Systems

Wilding, Paul Richard 01 June 2019 (has links)
The complete design process for a new nuclear power plant concept is costly, long, complicated, and the work is generally split between several specialized groups. These design groups separately do their best to design the portion of the reactor that falls in their expertise according to the design criteria before passing the design to the subsequent design group. Ultimately, the work of each design group is combined, with significant iteration between groups striving to facilitate the integration of each of the heavily interdependent systems. Such complex interaction between experts leads to three significant problems: (1) the issues associated with knowledge management, (2) the lack of design optimization, and (3) the failure to discover the hidden interdependencies between different design parameters that may exist. Some prior work has been accomplished in both developing common frame of reference (CFR) support systems to aid in the design process and applying optimization to nuclear system design.The purpose of this work is to use multi-objective optimization to address the second and third problems above on a small subset of reactor design scenarios. Multi-objective optimization generates several design optima in the form of a Pareto front, which portrays the optimal trade-off between design objectives. As a major part of this work, a system design optimization tool is created, namely the Optimization and Preference Tool for the Improvement of Nuclear Systems (OPTIONS). The OPTIONS tool is initially applied to several individual nuclear systems: the power conversion system (PCS) of the Integral, Inherently Safe Light Water Reactor (I²S-LWR), the Kalina cycle being proposed as the PCS for a LWR, the PERCS (or Passive Endothermic Reaction Cooling System), and the core loop of the Zion plant. Initial sensitivity analysis work and the application of the Non-dominated Sorting Particle Swarm Optimization (NSPSO) method provides a Pareto front of design optima for the PCS of the I²S-LWR, while bringing to light some hidden pressure interdependencies for generating steam using a flash drum. A desire to try many new PCS configurations leads to the development of an original multi-objective optimization method, namely the Mixed-Integer Non-dominated Sorting Genetic Algorithm (MI-NSGA). With this method, the OPTIONS tool provides a novel and improved Pareto front with additional optimal PCS configurations. Then, the simpler NSGA method is used to optimize the Kalina cycle, the PERCS, and the Zion core loop, providing each problem with improved designs and important objective trade-off information. Finally, the OPTIONS tool uses the MI-NSGA method to optimize the integration of three systems (Zion core loop, PERCS, and Rankine cycle PCS) while increasing efficiency, decreasing costs, and improving performance. In addition, the tool is outfitted to receive user preference input to improve the convergence of the optimization to a Pareto front.
283

Thresholds to XE-135 Induced Flux Oscillations in the Pickering and Bruce Nuclear Power Reactors (Part A) / Arc Trimming of Nichrome Thin Film Microcircuits (Part B)

Simmons, J. V. B. January 1970 (has links)
This thesis contains both Parts A and B. / <p> Xenon induced flux oscillations are possible in large thermal reactors operating at high powers because of the inter-play between the xenon concentration, reactivity, and thermal flux, and the fact that xenon is produced mainly by radioactive decay of I-135, which has a half-life of 6.7 hours. Due to these nuclear characteristics along with size and operating conditions of the Pickering and Bruce cores, these oscillations in flux are inherently unstable with respect to xenon. That is, a local perturbation in reactivity will result in a divergent and cyclic time and space variation in the thermal flux distribution in the core.</p> <p> One group diffusion theory and a simple perturbation analysis yield for a bare thermal reactor, a threshold in the average flux level ∅ which satisfies (1) M^2λij^2 / αxe - αT/αxe ∅ = 1/1+λxe/σxe∅ - μxe / 1+(λxe + λ1)/σxe∅ for oscillations in ijth mode of the flux distribution (see Figure 1) M^2 is the migration area in cm^2, αxe is the reactivity load of Xe-135 at high flux levels; αT is the fuel temperature coefficient expressed in terms of reactivity change per unit flux. The function f(∅) depends only upon the decay constants λxe of Xe-135 and λ1 of I-135; μxe is the fraction of Xe-135 produced directly from the fission of the fuel rather than through iodine decay (which fraction is denoted by μ1). The dimensionless parameter λij^2 depends only upon the shape of the flux distribution and is equal to the difference between the bulking of the ijth mode and the fundamental model.</p> <p> The Bruce and Pickering reactors are used as models in this study to determine the threshold power level at which xenon instability is possible and in which mode this instability occurs.</p> <p> Bruce is found to be unstable in the fundamental and first azimuthal mode for fresh and equilibrium fuel conditions, and stable for the radial, axial and higher azimuthal modes.</p> <p> Pickering, on the other hand, is unstable for the equilibrium fuel condition in the fundamental and first azimuthal modes only and is stable in every mode except the fundamental in the fresh fuel condition.</p> (Part A of Thesis)-------------------------------------------------------------------------------------------------------(Part B of Thesis) </p> Trimming of thin-film resistor components by an electrical arc is investigated in this report as an inexpensive and simple alternative to the laser trim and mechanical scribe methods. A multitude of tests were effected on Garrett Manufacturing Limited production circuits containing nichrome thin film resistors. These tests included Temperature Coefficient of Resistivity, resistance stability, substrate damage, noise performance, dynamic trim with active devices operating, width of cut as compared to mechanical scribe and laser trim techniques, and optimum parameters for trimming. In all cases the trimmed circuits were within the design specifications of the resistor properties under test. It is the conclusion of the author that the obvious attributes of the arc-trim method as well as its outstanding performance in the above tests, warrants its serious consideration as a viable alternative to the laser trim and mechanical scribe methods of altering resistance levels.</p> / Thesis / Master of Engineering (MEngr)
284

Analysis and Simulation of Nuclear Thermal Energy Storage Systems for Increasing Grid Stability

Wallace, Jaron 07 December 2023 (has links) (PDF)
With the growing capacity of renewable energy production sources, nuclear energy, once a mainstay of power generation, faces challenges due to its limited adaptability to fluctuating energy demands. This inherent rigidity makes it less desirable than the more flexible renewable sources. However, integrating thermal energy storage (TES) systems offers a promising avenue, enabling nuclear power plants (NPPs) to enhance their operational flexibility and remain competitive in an evolving renewable market. A comprehensive ranking methodology has been introduced, delineating the criteria and processes to determine the most synergistic TES/NPP design couplings. This methodology considers the unique characteristics of both current and prospective reactor fleets, ensuring broad applicability across various nuclear technologies. Economic analysis further supports the case for TES integration. Findings indicate that when equipped with TES systems, NPPs can remain price competitive, even with carbon-neutral alternatives like solar power generation. A lab-scale TES system was meticulously designed and constructed to validate these theoretical propositions. For its control, the Python GEKKO model predictive control (MPC) was employed, a decision influenced by the proven efficacy of GEKKO in managing complex systems. Tests conclusively demonstrated the feasibility and efficiency of using GEKKO for MPC of TES systems. A novel methodology for the MPC of a RELAP5-3D input deck has been proposed and elaborated upon. This methodology was rigorously tested at two distinct scales. The initial focus was on a thermal-hydraulic model of the lab-scale TES system. Subsequent efforts scaled up to control a more intricate thermal-hydraulic model, representing a small modular reactor (SMR) paired with an oil-based TES system. In both scenarios, GEKKO exhibited exemplary performance, controlling the RELAP5-3D models with precision and ensuring they met the stipulated demand parameters. The research underscores the potential of RELAP5-3D MPC in streamlining the licensing process for TES systems intended for NPP coupling. This approach could eliminate the need for expensive and time-consuming experiments, paving the way for more efficient and cost-effective nuclear energy solutions.
285

An Experimental Approach to Assessing Material Corrosion Rates in a Reactor Containment Sump Following a Loss of Coolant Accident

Lahti, Erik Anders 17 September 2013 (has links)
No description available.
286

A Comparison of Dynamic and Classical Event Tree Analysis for Nuclear Power Plant Probabilistic Safety/Risk Assessment

Metzroth, Kyle G. 22 July 2011 (has links)
No description available.
287

Summarizing the theoretical foundation for hospital communication research: A scoping review of interdisciplinary literature.

Keeppanasseril, Arun 10 1900 (has links)
<p>Hospitals are complex socio-technical systems where health professionals from varied backgrounds interact with each other and technology for the wellbeing of patients. Effective communication among the members of the care team is vital for optimal care; poor communication can result in suboptimal care and in many cases, lead to adverse events (AEs) and even death. More than a decade after the US Institute of Medicine report which catalyzed patient safety improvement measures, patient safety remains a major concern. Two-thirds of AEs in hospitals are still linked to communication errors. Hospitals are trying to improve communication by introducing new communication devices like smart phones and tablet computers for professional use. However, they are being deployed without adequate study of the mechanics of communication in hospitals or their use affects inter-professional communication. High risk organizations such as nuclear power plants, aviation and the military have achieved better safety records than healthcare. This is likely because they have studied their communication challenges and based their assessments on a firm theoretical foundation before implementing customized solutions. This approach in healthcare is lacking. Therefore a scoping review was conducted to collect communication theories, models, frameworks, and methods applicable to new information and communication technology used in hospitals. Literature from basic and applied science domains such as cognitive psychology, human factors engineering, organizational behavior, sociology, communication sciences and from high risk organizations like aviation, nuclear power generation and defense was reviewed. 14 theories, 12 models and 12 communication analysis methods were identified. One of the selected methods was employed to conduct a case study of a case of faulty communication reported in the AHRQ web M&M. It is not known how well those theories, models and analysis methods can be adapted to medicine. Future research may be able to address the issue and adopt theories and models to hospital communication research, modifying existing theories and models to suit the unique requirements of hospitals or by developing a strategy to design them de-novo.</p> / Master of Science (MSc)
288

A method of generation scheduling in electric utility systems with nuclear units

Rahman, Saifur 07 April 2010 (has links)
The problem of unit commitment in an electric utility system is analyzed. The types of generating units considered include nuclear-steam, fossil-steam, thermalpeaking, conventional and pumped-storage hydro. The large problem of generating unit commitment, due to the inclusion of the nuclear unit, is decomposed into two stages. In the first stage, the relatively stable nuclear generation is optimized with respect to the generation from the large fossil-steam unit. Hourly generation levels for all the units in the system are determined in the second stage. AS a result of considering the startup-shutdown cost, the objective function has a fixed charge component in addition to first and second degree polynomials. Representation of the minimum turndown level and minimum Shutdown duration of the generator necessitates the use of O-1 variables along with continuous variables. The solution methodology presented here, applying an extension of the Lambda-Separable Programming, can handle these requirements efficiently. Application of the algorithm results in a minimum-cost generation schedule for all units in the system. Optimum generation levels of energy limited units are determined without using a preselected unit commitment order. The effect of startup-shutdown costs on the number of hours a Plant should operate is established. The cost and benefit of spent nuclear fuel reprocessing is analyzed and the effect of uranium prices on it (reprocessing) is shown. The model is tested using a sample system of six generating units. Hourly generation schedules, includig purchase and sale, are determined for two one-week periods while the nuclear generation is optimized for an entire year. / Ph. D.
289

Mechanisms for automated toolhead changing in nuclear steam generator robotics

Melnyk, Glenn J. 30 June 2009 (has links)
The design of toolhead changing manipulator is highly dependent on the specific application. The geometry, mobility of the existing system, the toolhead robot interface and the toolhead size and shape all are major factors in the development of an effective solution. The addition of other functional requirements increase the complexity of the design. The platform maintenance functions required in the BWNS problem increased the complexity to a 5 DOF feeding manipulator. This solution, while complex, is an effective and efficient solution to this specific application. The result should be a significant reduction in human radiation exposure and reduced steam generator service time. / Master of Science
290

Design of a robust acoustic positioning system for an underwater nuclear reactor vessel inspection robot

Maples, Allen B. 23 June 2009 (has links)
The objective of this thesis is the algorithmic enhancement and initial evaluation of an underwater acoustic positioning system which is designed to determine the position and orientation of a mobile nuclear reactor vessel inspection robot. Although a great deal of research has been done in the area of underwater acoustic positioning, this work differs from previous work in three significant ways. First, most applied acoustic positioning systems have been designed for the offshore oil drilling industry, and thus their requirements and restrictions are dictated by an oceanic environment. Second, most previous work has focused only upon acquiring the position of a point from the acoustic system. The inspection robot operation requires accurate positioning and orientation. Finally, the accuracy of acoustic positioning systems is generally dependent upon an evaluation of the speed of sound. However, this parameter is highly dependent upon water temperature. As will be discussed, the reactor vessel water temperature may not be uniform or constant, which makes the design of a precise positioning system difficult. Original methods to overcome this obstacle are discussed and evaluated. Also examined are configurations and constraints of the acoustic transceivers, the numerical solution procedures utilized, and the resulting errors associated with the developed methods. / Master of Science

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