MITSUO YAMAGUCHI
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Capítulo IPEN-doc 13929 Critical loading configurations of the IPEN/MB-01 reactor with UOsub(2) and borated stainless steel plates2006 - SANTOS, ADIMIR dos; ANDRADE e SILVA, G.S.D.; FANARO, LEDA C.C.B.; YAMAGUCHI, MITSUO; JEREZ, ROGERIOArtigo IPEN-doc 10707 Proposta de aumento de potencia do reator IPEN/MB-012005 - BITELLI, U.D.; JEREZ, R.; YAMAGUCHI, M.; UMBEHAUN, P.E.; SANTOS, A.; VENEZIANI, C.L.Artigo IPEN-doc 10710 Metodologia de calculo dos parametros cineticos com o sistema NJOY/AMPX-II/TORT2005 - SANTOS, A.; YAMAGUCHI, M.; ANDRADE e SILVA, G.S.; DINIZ, R.; JEREZ, R.; MAI, L.A.; MENDONCA, A.G.Artigo IPEN-doc 15266 Critical loading configurations of the IPEN/MB-01 reactor with UOsub(2)GDsun(2)Osub(3) burnable poison rods2009 - ABE, ALFREDO; FUGA, RINALDO; SANTOS, ADIMIR dos; ANDRADE e SILVA, GRACIETE S. de; FANARO, LEDA C.C.B.; YAMAGUCHI, MITSUO; JEREZ, ROGERIOArtigo IPEN-doc 15265 Neutronic, thermal-hydraulic and accident analysis calculations for an irradiation device to be used in the qualification process of dispersion fuels in the IEA-R1 research reactor2009 - DOMINGOS, DOUGLAS B.; TEIXEIRA e SILVA, ANTONIO; UMBEHAUN, PEDRO E.; SILVA, JOSE E.R. da; CONTI, THADEU das N.; YAMAGUCHI, MITSUONeutronic, thermal-hydraulics and accident analysis calculations were developed to estimate the safety of an irradiation device placed in the IEA-R1 reactor core. The irradiation device will be used to receive miniplates of U3O8-Al e U3Si2-Al dispersion fuels, LEU type (19.9% of 235U), with uranium densities of, respectively, 3.0 gU/cm3 and 4.8gU/cm3 . The fuel miniplates will be irradiated to nominal 235U burnup levels of 50% and 80%, in order to qualify the above high-density dispersion fuels to be used in the Brazilian Multipurpose Reactor, now in the conception phase. For the neutronic calculation, the computer code CITATION was utilized. The computer code FLOW was used to calculate the coolant flow rate in the irradiation device, allowing the determination of the fuel miniplate temperatures with the computer model MTRCR-IEA-R1. A postulated Loss of Coolant Accident (LOCA) was analyzed with the computer codes LOSS and TEMPLOCA, allowing the calculation of the fuel miniplate temperatures after the reactor pool draining. The calculations showed that the irradiation of the fuel miniplates will happen without any adverse consequence in the IEA-R1 reactor.Artigo IPEN-doc 04155 Incorporacao de um modulo termo-hidraulico ao programa CITATION1991 - YORIYAZ, H.; ROSSINI, M.R.; YAMAGUCHI, M.Artigo IPEN-doc 15470 Neutronic and thermal-hydraulics calculations of U-Mo dispersion fuel for utilization in the IEA-R1 reactor core2006 - SILVA, A.T.; ALMEIDA, C.T.; UMBEHAUN, P.E.; YAMAGUSHI, M.; SILVA, J.E.R.; LUCKI, G.Artigo IPEN-doc 06927 Monte Carlo burnup analysis of the nuclear research reactor IEAR-1 using MCNP-4B code2000 - CABEZAS SOLORZANO, R.; YORIYAZ, H.; SANTOS, A.; YAMAGUCHI, M.Artigo IPEN-doc 06250 Core calculations for the upgrading of the IEA-R1 Research Reactor1998 - SANTOS, A.; PERROTTA, J.A.; BASTOS, J.L.F.; YAMAGUCHI, M.; UMBEHAUN, P.E.Artigo IPEN-doc 06252 Studies for a multipurpose research reactor for the CRCN/CNEN-PE1998 - BARROSO, A.C.O.; MAIORINO, J.R.; MOREIRA, J.M.L.; BASTOS, J.L.F.; SILVA, J.E.R.; LIMA, F.R.A.; YAMAGUCHI, M.; LYRA, C.A.B.O.; AZEVEDO, C.V.G.; UMBEHAUN, P.E.; FERREIRA, C.R.; MAPRELIAN, E.; ANDRADE e SILVA, G.S.; YORIYAZ, H.; BARROS FILHO, J.A.; TERREMOTO, L.A.A.; SANTOS, R.S.