Social demands of recycle is becoming strong. In modern production systems, largenumber of one model of product is manufactured at a time and the way ofproduction operations are well specified. In recycling systems, on the contrary, it isusual that operation of disassemble for each works differs. Because of this,achieving high efficiency in recycling systems have been difficult. Quality FunctionDeployment (QFD) was implemented in the project to obtain clear understandingof the problem being dealt with. Being a case study in the recycling of end-of-liferefrigerators means there are several stakeholders which must be satisfied includinggovernment regulations, workforce, and the business organisation. At the same timeproductivity is maximised while cost and time is diminished. Designing withfunction, brainstorming and patent searches were used to generate new ideas.Building morphology was also used to generate ideas as well as document them.The results of the project are different concepts that can be applied individually anda comprehensive concept that will entail exhaustive change in the entire system.The recycling of compressors for material recovery is discussed. / http://www.diva-portal.se/smash/get/diva2:1326957/FULLTEXT02.pdf

A continued increase in government regulations for fuel economy and emissions has driven automakers and suppliers to take a large interest in hybridizing vehicles to help them achieve the new requirements. This increased vehicle electrification has resulted in unconventional vehicle cooling requirements. Electrified vehicle batteries and motors operate under different temperature regimes and cooling loads change drastically with driving styles and conditions. A variable-load cooling system was designed, implemented and tested on the Mississippi State University EcoCAR extended-range electric vehicle (E-REV). This system, utilizing variable flow pumps and variable speed fans, was shown to successfully cool the electronic components under the worst-case design conditions, while providing low energy consumption under normal conditions. When compared to a baseline system utilizing no variable duty cycle components, the variable cooling power system reduced energy consumption during testing both on-road at MSU’s facility and on-road at General Motors proving grounds in Michigan.

The machining of a new alloy often presents a challenge. While useful assumptions can be drawn from materials of similar properties, there will always be unpredictable outcomes. Titanium alloys have been employed in the aerospace industry due to their high mechanical properties and good strength-to-weight ratio. Ti-64 (Ti-6Al-4V) was the standard choice until recently, when Ti-555.3 (Ti-5Al-5V-5Mo-3Cr) began to take its place. Ti-555.3 has improved resistance to fatigue and higher mechanical properties compared to Ti-64 and is able to maintain its strength when exposed to high temperatures, which warrants its acceptance for many applications. However, its chemical reactivity, low thermal conductivity and high mechanical properties are known to cause challenges when cutting this alloy. Making use of both experimental procedures and computational resources, this work presents a comparison between these two aerospace alloys under different process conditions, setting the ground for further academic development and optimization strategies. Determining that these alloys are substantially different from a machinability standpoint (lower tool life, abrasion & chipping as dominant wear mechanisms and nonuniform chip formation for Ti555.3 versus Ti-64). Based on this further investigation should be carried out for optimal tooling selection to improve the machining of Ti555.3. / Thesis / Master of Applied Science (MASc)

This thesis covers the process of automating the design of coolant nozzles used for cylindrical grinding. Coolant nozzles are used to supply coolant, an oil and water mixture used to cool the metal workpiece and lubricate the grinding wheel. In the automotive industry, grinding is used to reduce the surface roughness of the workpiece. However, a large amount of heat is generated, risking the heat treatment of the steel to be compromised, for this, coolant is supplied to minimize the heat caused by friction. A nozzle is used, aiming a jet to the zone that generates heat. Commonly used nozzles are adjustable, leading to variation in cooling performance if misaligned. The design of fixed nozzles is developed in this thesis to reduce variation and automatise the design for multiple applications. The automatically designed nozzles are fused deposition modeled and tested. The design automation tool is tested repeatedly and improved successively in the span of the thesis. This lead to a great extent of implementation of design automation. Which lead to a facilitation in reaching of the work zone and avoid obstacles. Also, the tool managed to create nozzle tubes for a multitude of machines. The tool is able to generate, aim, orient, and individually dimension multi-nozzle tubes. Design of Experiment methodology is implemented to find nozzle designs with improved velocity and flow rate and minimize the air mixture with the coolant. Several nozzle designs are tested and fitted into a surrogate model that is, in turn, optimized. The results of the tests led to a greater understanding of how the nozzle geometry restricts the flow rate when attempts of reaching higher velocities of the coolant jet are made. The surrogate models created, also made it possible to find the range of designs which best suits different applications, whereby a Pareto front was able to be populated with a range of different designs alternating in flow rate, velocity and coherency ratio.

Made available in DSpace on 2014-10-09T12:27:12Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:56:51Z (GMT). No. of bitstreams: 0 / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

Made available in DSpace on 2014-10-09T12:27:12Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:56:51Z (GMT). No. of bitstreams: 0 / Neste trabalho é aplicada a metodologia da Análise Probabilística de Segurança nível 1 ao reator IEA-R1. Inicialmente são descritos os eventos iniciadores de acidentes identificados no reator para duas categorias: perda de vazão e perda de refrigerante primário. Dentre eles foram escolhidos dois eventos iniciadores para análise mais detalhada do acidente e obtenção da estimativa da freqüência de danos ao núcleo devido a sua ocorrência. Foram selecionados os seguintes eventos iniciadores: bloqueio de canal de refrigeração (maior probabilidade) e perda de refrigerante por grande ruptura da tubulação do circuito primário (maiores consequências). Para modelar a evolução do acidente a partir da ocorrência do evento iniciador e da atuação ou não dos sistemas de segurança utilizou-se Árvore de Eventos. Através de Árvore de Falhas, também foi avaliada a confiabilidade dos seguintes sistemas: sistema de desligamento do reator, isolamento da piscina, sistema de resfriamento de emergência (SRE) e sistema elétrico. Como resultados foram obtidas as estimativas das frequências de danos ao núcleo do reator e as probabilidades de falha dos sistemas analisados. As freqüências de danos ao núcleo mostraram-se dentro das margens esperadas, sendo da mesma ordem de grandeza que os encontrados para reatores similares. As confiabilidades dos sistemas de desligamento do reator, de isolamento da piscina e do SRE foram satisfatórias para as condições em que estes sistemas foram exigidos. Todavia, para o sistema elétrico seria recomendável uma análise para verificar a possibilidade de modernização a fim de aumentar a sua confiabilidade. / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

Thesis Abstract This thesis has been performed under co-tutelle supervision between Charles University in Prague (Czech Republic) and Strasbourg University (France). It also profited from the background and cooperation of Institute of Inorganic Chemistry Academy of Science of the Czech Republic and French Commission for Atomic and Alternative energies (CEA Cadarache, France). Results of the work contribute to the OECD/NEA project Serena 2 (Program on Steam Explosion Resolution for Nuclear Applications). Presented thesis can be classed in the scientific field of nuclear safety and material science. It is aimed on the so-called "molten nuclear Fuel - Coolant Interaction" (FCI) that belongs among the recent issues of the nuclear reactor severe accident R&D. During the nuclear reactor melt down accident the melted reactor load can interact with the coolant (light water). This interaction can be located inside the vessel or outside in the case of vessel break-up. These two scenarios are commonly called in- and ex-vessel FCI and they differ in the conditions such as initial pressure of the system, water sub-cooling etc. The Molten fuel - coolant interaction can progress into thermal detonation called also "steam explosion" that can challenge the reactor or containment integrity. Recent experiments have shown that...

Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Mechanical Engineering, 1981. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND ENGINEERING. / Bibliography: leaves 182-188. / by Juan J. Manzano-Ruiz. / Ph.D.

The phenomena of interest in this work is the thermal stratification which occurs during the early stages of a loss of coolant accident (LOCA) in the OSU APEX Thermal Hydraulic Test Facility, which is a scaled model of the Westinghouse AP600 nuclear power plant. Thermal stratification has been linked to the occurrence of pressurized thermal shock (PTS). Analysis of the OSU APEX facility data has allowed the determination of an onset criteria and support for the postulated mechanisms leading to thermal stratification. CFX 4.1, a computational fluid dynamics code, was used to generate a model of the cold legs and the downcomer and the phenomena occurring within them. The following are the accomplishments of the work contained within this report; Determined the causes of thermal stratification in the cold legs of the Westinghouse Advanced Passive 600 MW (AP600) nuclear power plant. Predicted the onset of thermal stratification in the cold legs of the Westinghouse Advanced Passive 600 MW (AP600) nuclear power plant. Modeled the phenomena associated with thermal stratification in the cold legs of the Westinghouse Advanced Passive 600 MW (AP600) nuclear power plant. / Graduation date: 1998

The purpose of this report is to present the results of the study and analysis of loss-of-coolant and loss-of-flow simulations performed on the Modular Helium Reactor developed by General Atomics using the thermal-hydraulics code RELAP5-3D/ATHENA. The MHR is a high temperature gas cooled reactor. It is a prismatic core concept for New Generation Nuclear Plant (NGNP). Very few reactors of that kind have been designed in the past. Furthermore, the MHR is supposed to be a highly passively safe concept. So there are high needs for numerical simulations in order to confirm the design. The project is dedicated to the assessment of the passive decay heat capabilities of the reactor under abnormal transient conditions. To comply with the requirements of the NGNP, fuel and structural temperatures must be kept under design safety limits under any circumstances. During the project, the MHR has been investigated: first under steady-state conditions and then under transient settings. The project confirms that satisfying passive decay heat removal by means of natural heat transfer mechanisms (convection, conduction and radiation) occurs.