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31	Frequencia de danos no nucleo por blecaute em reator nuclear de concepcao avancada CARVALHO, LUIZ S. 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:48:53Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:01:14Z (GMT). No. of bitstreams: 1 09627.pdf: 6224254 bytes, checksum: 0192b8abd2aed7811607e803516e20a7 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP reactor cores damage outages reactor safety rhr systems probability fault tree analysis
32	Determinacao das zonas de seguranca da central nuclear de Angra dos Reis conforme o modelo de difusao de radiacao na atmosfera DELLA SANTINA, MURILO 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:24:33Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:05:13Z (GMT). No. of bitstreams: 1 00376.pdf: 2599179 bytes, checksum: c0a89c9bf1cb4f69498ed0fb9b039e9d (MD5) / Dissertacao (Mestrado) / IEA/D / Escola Politecnica, Universidade de Sao Paulo - POLI/USP radiation doses reactor safety south america brazil water cooled reactors atmospheres pwr
33	Sistema de controle e instrumentacao do reator de potencia zero do IEA e o calculo de sua confiabilidade PELUSO, MARCOS A.V. 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:24:49Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:04:53Z (GMT). No. of bitstreams: 1 00422.pdf: 1756629 bytes, checksum: 85b8a14cae110a01c2e28df8958192d9 (MD5) / Dissertacao (Mestrado) / IEA/D / Escola Politecnica, Universidade de Sao Paulo - POLI/USP control systems reactor safety research reactors iea-zpr reactor south america brazil water cooled reactors
34	Avaliacao da integridade do vaso de pressao dos reatores Angra II/III pela analise de tensoes GOMES, EDSON 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:26:03Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:10:10Z (GMT). No. of bitstreams: 1 00721.pdf: 1565696 bytes, checksum: 317165c778a10488d3c186dc5f2ba1fc (MD5) / Dissertacao (Mestrado) / IEA/D / Instituto de Energia Atomica - IEA power plants nuclear power plants pressure vessels reactor safety water cooled reactors pressurized water reactors
35	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. Nuclear Engineering Metallurgy Chemistry materials corrosion nuclear power reactor safety loss of coolant accident design experiment
36	Benchmark of RELAP5 Check Valve Models against Experimental Data Gardell, Jens January 2013 (has links) The use of check valves in the nuclear industry is of great importance from a safety precaution point ofview (McElhaney, 1995). Choosing check valves for these high-pressurized systems comes with agreat challenge. The valves causes what is called check valve slams when closing, leading to a hugepressure wave traveling through the system. To prevent this from happening calculations have to bedone to see what kind of forces are generated during a check valve slam. When the forces are known itis easier designing systems that will endure these slams. A commonly used software in the nuclearindustry is RELAP5 (Reactor Excursion and Leak Analysis Program), its main purpose is to calculatetransients in piping systems. This program can also be used when calculating a check valve slam. Buthow precise is the code compared to the real event? By doing an experiment measuring pressures created by swing check valves during slams, the codewas compared to real data and analyzed to decide what was of importance when modeling for thesetypes of simulations. The RELAP5 code was not initially designed to calculate transients during a check valve slam. This isclearly shown when the code overestimates the pressure waves in the system when using themanufacturer data for the check valve model. Matching the data from the simulations in RELAP5 withthe data recorded from the experiment is not easy. The parameters used for this have no connection tothe specifications for the check valve, which means that transients are hard to estimate withoutexperimental data. RELAP5 check valve slam steam bubble collapse experimental data Benchmark inertia check valve pressure wave closing time reactor safety
37	Proposta de um nucleo de reator PWR avancado com caracteristicas adequadas para o conceito de seguranca passiva PERROTTA, JOSE A. 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:43:11Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:56:49Z (GMT). No. of bitstreams: 1 06476.pdf: 9927984 bytes, checksum: 071861dcaed4ce3370a5065fdd2ae525 (MD5) / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP PWR TYPE REACTORS REACTOR CORES FUEL ELEMENTS URANIUM DIOXIDE OPTIMIZATION REACTOR SAFETY COMPARATIVE EVALUATIONS FUEL ASSEMBLIES FUEL PLATES
38	Aplicacao da metodologia fuzzy na quantificacao da probabilidade de erro humano em instalacoes nucleares / Human error probability quantification using fuzzy methodology in nuclear plants NASCIMENTO, CLAUDIO S. do 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:27:19Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:59:13Z (GMT). No. of bitstreams: 0 / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP CALCULATION METHODS EMERGENCY PLANS ERROS EVALUATION FUZZY LOGIC PERFORMANCE PROBABILITY REACTOR OPERATORS REACTOR SAFETY RELIABILITY RESEARCH AND TEST REACTORS
39	Análise numérica da dinâmica do escoamento em circuitos de circulação natural / Numerical analysis of the fluid dynamics in a natural circulation loop ANGELO, GABRIEL 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:41:29Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:03:20Z (GMT). No. of bitstreams: 0 / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP BRAZILIAN CNEN NATURAL CONVECTION FLUID FLOW TURBULENCE FLOW HEAT TRANSFER HYDRODYNAMICS MATHEMATICAL MODELS REACTOR SAFETY PWR TYPE REACTORS
40	Sistema de controle e instrumentacao do reator de potencia zero do IEA e o calculo de sua confiabilidade PELUSO, MARCOS A.V. 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:24:49Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:04:53Z (GMT). No. of bitstreams: 1 00422.pdf: 1756629 bytes, checksum: 85b8a14cae110a01c2e28df8958192d9 (MD5) / Dissertacao (Mestrado) / IEA/D / Escola Politecnica, Universidade de Sao Paulo - POLI/USP control systems reactor safety research reactors IEA-ZPR-reactor south america brazil water cooled reactors IEA-ZPR-reactor

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