SR7  Energia Eólica, Solar e Nuclear    Titulo: PARAMETRIC ANALYSIS OF CRITICAL HEAT FLUX IN WATER FLOW IN ROD BUNDLES THROUGH ARTIFICIAL NEURAL NETS   Resumo : THE OCCURRENCE OF CRITICAL HEAT FLUX REPRESENTS THE MAJOR THERMALHYDRAULIC LIMIT IN THE DESIGN OF PWR (PRESSURIZED WATER REACTORS) TYPE REACTORS. IN THIS KIND OF REACTORS, THE FUEL ELEMENTS CONSIST OF ROD BUNDLES, HELD BY GRIDS, IN SQUARE ARRAYS, WITH THE WATER FLOWING AXIALLY ALONG THE PINS. IN THE PRESENT WORK, IT IS DEVELOPED AN ARTIFICIAL NEURAL NET TO SIMULATE THE OCCURRENCE OF CRITICAL HEAT FLUX, UTILIZING EXPERIMENTAL DATA OBTAINED IN ROD BUNDLES WITH UNIFORM AXIAL HEAT, TO TRAIN THE NET. WITH THE DEVELOPED NET, THE EFFECTS OF AVERAGE MASS FLUX, OUTLET PRESSURE AND INLET QUALITY WERE ANALYZED FOR TWO TEST SECTIONS WITH 3X3 AND 5X5 ARRAYS. KEYWORDS: CRITICAL HEAT FLUX. NUCLEAR SAFETY. ARTIFICIAL NEURAL NETS.     Autores : Carajilescov, Pedro 0     Trabalho Completo :   COBEM99 | Comissão  Organizadora | Palestras | Sessões Técnicas | Autor | Simpósios e Sessões Especiais | Revisores |  Título  dos  Trabalhos | Local