Made available in DSpace on 2014-10-09T12:55:30Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:07:16Z (GMT). No. of bitstreams: 0 / Foi desenvolvida uma técnica de medida de nível em vasos de pressão usando sondas térmicas resfriadas internamente por um fluido e análise dos dados experimentais com Redes Neurais Artificiais (RNA´s). Esse novo conceito de sondas térmicas foi testado em uma Bancada Experimental para Testes de Sondas de Nível (BETSNI) com duas seções de testes, ST1 e ST2. Dois projetos distintos de sondas foram construídos: Sonda de Tubos Concêntricos e Sonda de Tubo U. Um Sistema de Aquisição de Dados (SAD) foi montado para registrar os dados experimentais. Testes foram realizados tanto para condições de nível nas seções de testes em estado estacionário quanto para transientes. Os dados experimentais de temperatura e de nível obtidos foram usados para compor tabelas de treinamento e de verificação usadas para implementar RNA´s no programa RETRO-05, que simula um Perceptron de Múltiplas Camadas com Retropropagação. As análises mostraram que a técnica pode ser aplicada para medir o nível em vasos de pressão. As análises mostraram ainda que a técnica é aplicável para um número menor de entradas de temperatura que o inicialmente previsto no projeto das sondas e é robusta, aplicando-se mesmo quando ocorre a perda de alguma informação de temperatura. Dados experimentais disponíveis na literatura referentes a uma sonda térmica aquecida eletricamente também foram usados nas análises com RNA´s, produzindo bons resultados. Os resultados das análises indicaram que a técnica é eficaz e robusta, podendo ser aprimorada e aplicada para medidas de nível em vasos de pressão. / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

Thesis. 1979. Ph.D. cn--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / Ph.D.cn

To decrease the ecological footprint, humans either have to adjust their lifestyles, or the large scale industries must take corporate social responsibility. This study is based on the well-developed field of energy efficiency in industries by applying technology and organizational-focused proposals. The proposals are based on three different aspects, the economic, the environmental, and the social. These three aspects combined are called the triple bottom line perspective. An original case of the study objects energy balance was determined to develop the conclusions, with the simulation program IDA ICE. The study object was GKN ePowertrain, located in Köping. Energy efficiency cases were simulated in IDA ICE to observe the change in the energy balance. The cases and interviews of the employees were the foundation of the discussion where the improvements were critically reviewed from the triple bottom line perspective. The result shown that the temperature was too high for working conditions, the ventilation system consumes a large quantity of energy, and the internal flow of information is insufficient. In conclusion, GKN ePowertrain would increase their overall value by investing in a cooling system and more efficient heat exchangers for their ventilation system. These investments would notably increase their short term value of environmental sustainability and the social aspect. Furthermore, their economic value would increase in the long term. The cooling system would improve the working environment, and a new ventilation system would increase the heat recovery and decrease the energy consumed, even more than the consumption of the cooling system. Finally, GKN should also be more distinct in their information to the employees in the building regarding energy aims and their working environment, to have a positive gain of value in all the fields.

This master's thesis is an investigation and evaluation of MELCOR (a software tool for severe accident analyses regarding nuclear power plants), or more correctly of the (ASEA-Atom BWR 75) reactor model developed for version 1.8.6 of MELCOR. The main objective was to determine if MELCOR, with the reactor model in question, is able to produce satisfactory results in severe accident analyses compared to results made by MAAP, which is currently the only official software tool for this application in Sweden. The thesis work is related to the RASTEP project. This project has been carried out in several stages on behalf of SSM since 2009, with a number of specific issues explored within an NKS funded R&D project carried out 2011-2013. This investigation is related to the NKS part of the project. The purpose with the RASTEP project is to develop a method for rapid source term prediction that could aid the authorities in decision making during a severe accident in a nuclear power plant. A software tool, which also gave the project its name, i.e. RASTEP (RApid Source TErm Prediction), is therefore currently under development at Lloyd's Register Consulting. A software tool for severe accident analyses is needed to calculate the source terms which are the end result from the predictions made by RASTEP. A set of issues have been outlined in an earlier comparison between MAAP and MELCOR. The first objective was therefore to resolve these pre-discovered issues, but also to address new issues, should they occur. The existing MELCOR reactor model also had to be further developed through the inclusion of various safety systems, since these systems are required for certain types of scenarios. Subsequently, a set of scenarios was simulated to draw conclusions from the additions made to the reactor model. Most of the issues (pre-discovered as well as new ones) could be resolved. However the work also rendered a set of issues which are in need of further attention and investigation. The overall conclusion is that MELCOR is indeed a promising alternative for severe accident analyses in the Swedish work with nuclear safety. Several potential benefits from making use of MELCOR besides MAAP have been identified. In conclusion, they would be valuable assets to each other, e.g. since deviations in the results (between the two codes) would highlight possible weaknesses of the simulations. Finally it is recommended that the work on improving the MELCOR reactor model should continue. / RASTEP

Submitted by Marco Antonio Oliveira da Silva (maosilva@ipen.br) on 2016-08-26T12:15:03Z No. of bitstreams: 0 / Made available in DSpace on 2016-08-26T12:15:03Z (GMT). No. of bitstreams: 0 / O escoamento bifásico de gás-líquido é encontrado em muitos circuitos fechados que utilizam circulação natural para fins de resfriamento. O fenômeno da circulação natural é importante nos recentes projetos de centrais nucleares para a remoção de calor. O circuito de circulação natural (Circuito de Circulação Natural - CCN), instalado no Instituto de Pesquisas Energéticas e Nucleares, IPEN / CNEN, é um circuito experimento concebido para fornecer dados termo-hidráulicos relacionados com escoamento monofásico ou bifásico em condições de circulação natural. A estimativa de transferência de calor tem sido melhorada com base em modelos que requerem uma previsão precisa de transições de padrão de escoamento. Este trabalho apresenta testes experimentais desenvolvidos no CCN para a visualização dos fenômenos de instabilidade em ciclos de circulação natural básica e classificar os padrões de escoamento bifásico associados aos transientes e instabilidades estáticas de escoamento. As imagens são comparadas e agrupadas utilizando mapas auto-organizáveis de Kohonen (SOM), aplicados em diferentes características da imagem digital. Coeficientes da Transformada Discreta de Cossenos de Quadro Completo (FFDCT) foram utilizados como entrada para a tarefa de classificação, levando a bons resultados. Os protótipos de FFDCT obtidos podem ser associados a cada padrão de escoamento possibilitando uma melhor compreensão da instabilidade observada. Uma metodologia sistemática foi utilizada para verificar a robustez do método. / Dissertação (Mestrado em Tecnologia Nuclear) / IPEN/D / Instituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SP

This thesis aims to increase photovoltaic (PV) panel power efficiency by employing a cooling system based on water circulation, which represents an improved version of water flow based active cooling systems. Theoretical calculations involved finding the heat produced by the PV panel and the circulation water flow required to remove this heat. A data logger and a cooling system for a test panel of 20W was designed and employed to study the relationship between the PV panel surface temperature and its output power. This logging and cooling system includes an Arduino microcontroller extended with a data logging shield, temperature sensing probes, current sensors, and a DC water pump. Real-time measurements were logged every minute for one or two day periods under various irradiance and air temperature conditions. For these experiments, a load resistance was chosen to operate the test panel at its maximum power point. Results indicate that the cooling system can yield an improvement of 10% in power production. Based on the observations from the test panel experiments, a cooling system was devised for a PV panel array of 640 W equipped with a commercial charge controller. The test data logger was repurposed for this larger system. An identical PV array was left uncooled and monitored simultaneously to compare the effect of cooling, demonstrating that the cooled array provided up to an extra 132W or 20% of maximum power for sunny weather conditions. Future expansion possibilities of the project include automated water level monitoring system and water filtration systems.

Submitted by Marco Antonio Oliveira da Silva (maosilva@ipen.br) on 2016-12-21T12:55:48Z No. of bitstreams: 0 / Made available in DSpace on 2016-12-21T12:55:48Z (GMT). No. of bitstreams: 0 / O reator IEA-R1 do Instituto de Pesquisas Energéticas e Nucleares (IPENCNEN/ SP) é um reator de pesquisa tipo piscina aberta, projetado e construído pela empresa norte-americana \"Babcock & Wilcox\", tendo, como refrigerante e moderador, água leve deionizada e berílio e grafite como refletores. Até cerca de 1988, os sistemas de segurança do reator recebiam alimentação de uma única fonte de energia. Nos anos de 1989 e 1990, uma reforma de modernização do sistema elétrico para aumentar a potência do reator e, também, para atender às normas técnicas da Comissão Nacional de Energia Nuclear (CNEN) e da Associação Brasileira de Normas Técnicas (ABNT) foi realizada. Este trabalho tem o objetivo de mostrar a relação entre o sistema de energia elétrica e a segurança do reator IEA-R1. Além disso, ele demonstra que, caso ocorra alguma interrupção de energia elétrica durante a operação do reator, esta ocorrência não irá começar um evento de acidente. / Dissertação (Mestrado em Tecnologia Nuclear) / IPEN/D / Instituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SP

The diploma thesis deals with the design of the heating and cooling system, inclu-ding hot water preparation for the administrative part of the production hall. The first part of the thesis briefly discusses the history of heating and cooling of office buildings, legislative requirements and current solutions. The second part contains the design of the entire heating and cooling system with heat pump as a source of heat and cold. The final part of the thesis describes the experimental measure-ment and evaluation of the efficiency of the ice rink source.

The topic of this diploma thesis is large area heating and cooling systems. Theoretical part of this thesis is focused on thermal comfort of people in interier and on theoretical calculation of heat transfer and on large area heating and cooling systems. Second part is devided to two variants. First variant is design of a heating system in kindergarden with floor heating combined with plate heating radiators. Second variant is heating system with only plate heating radiators. As source of heat is used condensing gas boiler. Part of a design is preparation of hot water. Experimental part of the thesis contains measurements of coefficient of heat transfer in floor heating and wall heating.