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Aspectos sismologicos no projeto de usinas nucleares tipo PWRANJOS, ALEXANDRE A. dos 09 October 2014 (has links)
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00703.pdf: 11134536 bytes, checksum: d90c9954ba13bad5e3bf731108fc7f92 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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Calculo de consumo de combustivel e distribuicao de potencia para um PWR, utilizando-se os programas Leopard e CitationBATISTA, JOSE L. 09 October 2014 (has links)
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01402.pdf: 2037029 bytes, checksum: 0aeb11d232f899f22a9ef9076c165456 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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Estudo da imobilização de rejeitos radioativos em matrizes asfálticas e resíduos elastoméricos utilizando a técnica de microondasCARATIN, REINALDO L. 09 October 2014 (has links)
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12213.pdf: 5005382 bytes, checksum: c4bde457760b3a6d6f53b64c21e33010 (MD5) / No presente trabalho, foi utilizada a técnica de aquecimento por microondas para estudar a imobilização de rejeitos radioativos de nível de atividade baixo e médio, como resinas de troca iônica exauridas, empregadas na remoção de íons indesejáveis dos circuitos primários de refrigeração de reatores nucleares refrigerados a água, e aquelas usadas em colunas de separação química e radionuclídica no controle de qualidade de radioisótopos. Matrizes betuminosas reforçadas com alguns tipos de borrachas (Neoprene®, Silicone e Etileno Vinil Acetato - EVA), provenientes de material descartado ou sobras de produção, foram utilizadas para incorporação dos rejeitos radioativos. As irradiações das amostras foram feitas em um forno de microondas caseiro, que opera com freqüência de 2.450MHz e possui potência de 1.000W. As amostras foram caracterizadas, empregando-se ensaios de penetração, resistência à lixiviação, pontos de amolecimento, fulgor e combustão, termogravimetria e microscopia óptica. Os resultados obtidos mostraram-se compatíveis com os padrões dos componentes das matrizes, indicando que esta técnica é uma alternativa bastante útil aos métodos de imobilização convencionais e para esses tipos de rejeitos radioativos. / Dissertação (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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Tensoes termicas no vaso de pressao de um reator a agua pressurizada (PWR)BASSEL, WAGEEH S. 09 October 2014 (has links)
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00653.pdf: 2722544 bytes, checksum: 26bcce3d962be5c281c69fd5f50fca70 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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Simulation of nuclear power plant pressurizers with application to an inherently safe reactor.Khamis, Ibrahim Ahmad. January 1988 (has links)
Pressurizer modeling for predicting the dynamic pressure of the PIUS system is presented. The transient behavior of this model for the PIUS system was investigated. The validity of this model for the PIUS system is limited to transients that are neither too large nor too long in duration. For example, the model is not capable of describing events following a complete loss of liquid for the pressurizer. However, the model can be used for qualitative prediction of the PIUS system behavior for a wide variety of severe transients. A review of pressurizer modeling indicates that the neglecting of the change in the internal energy of the subcooled water during transients is an acceptable assumption. The inherently safe feature of the PIUS system was confirmed through the self-shutdown of the reactor or, in some cases, through reactor power reduction as a result of the ingress of the pool boric acid solution into the primary system. This dynamic model was constructed of three major components: (1) The primary loop, (2) The secondary loop, and (3) The natural convection loop through the pool. A lumped parameter model, uniform heat transfer, and point kinetics have been the main approximations in this model. Other approximations are mentioned during the modeling of each component of the model. The dynamic model was simulated using the DARE-P continuous system simulation language which was developed in the Electrical Engineering Department at the University of Arizona.
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Development of a heat-transfer correlation for supercritical water in supercritical water-cooled reactor applicationsMokry, Sarah 01 December 2009 (has links)
A large set of experimental data, obtained in Russia, was analyzed and a new
heat-transfer correlation for supercritical water was developed. This
experimental dataset was obtained within conditions similar to those for proposed
SuperCritical Water-cooled nuclear Reactor (SCWR) concepts. Thus, this new
correlation, for forced convective heat transfer in the normal heat-transfer regime,
can be used for preliminary heat-transfer calculations in SCWR fuel channels. It
has demonstrated a good fit for Heat Transfer Coefficient (HTC) values (±25%)
and for wall temperature calculations (±15) for the analyzed dataset. This
correlation can be used for supercritical water heat exchangers linked to indirectcycle
concepts and the co-generation of hydrogen, for future comparisons with
other independent datasets, with bundle data, as the reference case, for the
verification of computer codes for SCWR core thermalhydraulics and for the
verification of scaling parameters between water and modeling fluids. / UOIT
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Monitoracao da potencia do reator nuclear IEAR-1 pela atividade do N 16SOUSA, JOEL A. de 09 October 2014 (has links)
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00511.pdf: 606198 bytes, checksum: fd262e7d323a2dca01ef1d5e7656e443 (MD5) / Dissertacao (Mestrado) / IEA/D / Escola Politecnica, Universidade de Sao Paulo - POLI/USP
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Aplicacao dos metodos de relaxacao dinamica e elementos finitos na analise estrutural de um modelo reduzido de vaso de pressao de concreto protendidoTAMURA, MASARU 09 October 2014 (has links)
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01099.pdf: 10225038 bytes, checksum: 113532b9074d64302ecc9c6015faef45 (MD5) / Dissertacao (Mestrado) / IEA/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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Evaluation of tight-pitch PWR coresCORREA, FRANCISCO 09 October 2014 (has links)
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00967.pdf: 5059113 bytes, checksum: bc1fb5c365357208caf91f4f11ac81ea (MD5) / Thesis (Doctor) / IEA/T / Massachusetts Institute of Technology - Cambridge, Mass - MIT
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Razao de conversao e consumo de material fissil em reatores PWRTIBA, CHIGUERU 09 October 2014 (has links)
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00880.pdf: 2598559 bytes, checksum: 89e13c93bf1cbf3a2e4a292aaa260a5d (MD5) / Dissertacao (Mestrado) / IEA/D / Escola Politecnica, Universidade de Sao Paulo - POLI/USP
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