Nuclear Power Plants
Mostrando 13-23 de 23 artigos, teses e dissertações.
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13. O papel do pronuclear (1976 1986) na formação de recusos humanos para a área nuclear no Brasil
In 1975, an agreement between the governments of Brazil and West-Germany was signed for the construction of nuclear power plants in Brazil as well as the extraction, processing and enrichment of uranium. As the result of the first oil crisis and facing the perspective of a continuous world energy crisis, the Brazilian government decided to turn to nuclear po
Publicado em: 2006
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14. "Pré-processador matemático para o código Relap5 utilizando o Microsoft Excel" / MATHEMATIC PREPROCESSOR FOR RELAP5 CODE USING MICROSOFT EXCEL
Computational program are used for thermal hydraulic analysis of accidents and transients conditions in nuclear power plants. The RELAP5 code has been developed to simulate accidents and transients conditions, performing a best estimate analysis, in Pressurized Water Reactors (PWR) and auxiliary systems. The RELAP5 code, which has been used as a tool for lic
Publicado em: 2006
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15. "Armazenagem de combustível nuclear queimado" / SPENT NUCLEAR FUEL STORAGE
When a country becomes self-sufficient in part of the nuclear cycle, as production of fuel that will be used in nuclear power plants for energy generation, it is necessary to pay attention for the best method of storing the spent fuel. Temporary storage of spent nuclear fuel is a necessary practice and is applied nowadays all over the world, so much in count
Publicado em: 2005
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16. Avaliação numérica do comportamento à fratura de um protótipo de vaso de pressão de reator PWR submetido a choque térmico pressurizado / Numerical evaluation of the fracture behavior of a PWR reactor pressure vessel prototype under pressurized thermal shock
In the primary system of a pressurized water reactor (PWR) nuclear power plant, the reactor coolant is kept at internal temperature around 300 C and internal pressure in the order of 15,0 MPa, during normal operation. The reactor pressure vessel (RPV) contains the fuel assemblies and is considered the most important component of the reactor primary system. T
Publicado em: 2005
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17. Modeling of the Fluid-Structure Interaction in Inelastic Piping Systems
In many engineering applications, compliant piping systems conveying liquids are subjected to inelastic deformations due to severe pressure surges such as plastic tubes in modern water supply transmission lines and metallic pipings in nuclear power plants. In these cases the design of such systems may require an adequate modeling of the interactions between
Journal of the Brazilian Society of Mechanical Sciences. Publicado em: 2002-03
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18. AN ALTERNATIVE METHODOLOGY FOR THE SEISMIC STRUCTURAL ANALYSIS OF THERMO-NUCLEAR POWER PLANTS / ALTERNATIVA NA ANÁLISE DE ESTRUTURAS DE USINAS TERMONUCLEARES PARA CARGAS SÍSMICAS / ALTERNATIVA EN EL ANÁLISIS DE EXTRUCTURAS DE TERMONUCLEARES PARA CARGAS SÍSMICAS
The seismic analysis of nuclear power plant structures and components is considered to evaluate the convenience to update the brazilian design routine through the use of frequency domain techniques provided by codes such as SASSI. For this purpose one uses a FEM model of a reactor building which has been already analyzed by current techniques in time domain,
Publicado em: 1999
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19. DESARROLLO DE ESPECTROS DE RESPUESTA PARA ANÁLISIS EXTRUCTURAL SÍSMICA EN SISTEMAS DE TUBERÍAS / DESENVOLVIMENTO DE ESPECTROS DE RESPOSTA PARA A ANÁLISE ESTRUTURAL SÍSMICA EM SISTEMAS DE TUBULAÇÕES / DEVELOPMENT OF RESPONSE SPECTRA FOR THE SEISMIC STRUCTURAL ANALYSIS OF PIPING SYSTEMS
Los resultados presentados se refieran a la investigación de los mecanismos de interacción entre de los los sistemas Principal (SP) y el Secundario (S) de las plantas nucleares. Estos mecanismos son evaluados por medio de su influencia en los espectros de respuesta, en puntos de la extructura donde es posible(pausibles) la existencia de soportes de las lí
Publicado em: 1998
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20. THERMOHIDRAULIC MODEL FOR A TYPICAL STEAM GENERATOR OF PWR NUCLEAR POWER PLANTS / MODELO TERMOHIDRÁULICO PARA GERADOR DE VAPOR TÍPICO DE USINAS PWR
Muitas centrais nucleares do tipo PWR utilizam vapor produzido em geradores de vapor do tipo tubos em U invertido, com recirculação interna natural, nos quais o fluido primário escoa internamente aos tubos e o secundário, entre os tubos e a carcaça. No presente trabalho, é desenvolvido um modelo de simulação termohidráulica, para regime permanente,
IBICT - Instituto Brasileiro de Informação em Ciência e Tecnologia. Publicado em: 25/06/1980
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21. SARDAN - ONE PROGRAM TO TRANSIENT SIMULATION IN TYPICAL PWR NUCLEAR POWER PLANTS / SARDAN: UM PROGRAMA PARA SIMULAÇÃO DE TRANSITÓRIOS NUMA USINA PWR TÍPICA
No projeto de uma usina nuclear do tipo PWR, é necessário a verificação de que, nas diversas condições de operação, em regime permanente ou transitório, os limites de projeto de seus componentes não sejam atingidos. No presente trabalho, é desenvolvido um programa em linguagem FORTRAN-IV que simula o comportamento do circuito primário de uma usin
IBICT - Instituto Brasileiro de Informação em Ciência e Tecnologia. Publicado em: 29/10/1979
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22. Power Generation and the Environment
Environmental factors will play an ever-increasing role in planning for the location and design of future power generating plants. This planning must include all phases of furnishing electric power, such as the exploration for and mining of fossil and nuclear fuels; the transportation and storage of these fuels; power plant siting; the disposal of solid wast
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23. Molecular Aspects of Plant Adaptation to Life in the Chernobyl Zone1[w]
With each passing year since the Chernobyl accident of 1986, more questions arise about the potential for organisms to adapt to radiation exposure. Often this is thought to be attributed to somatic and germline mutation rates in various organisms. We analyzed the adaptability of native Arabidopsis plants collected from areas with different levels of contamin
American Society of Plant Biologists.