MITSUO YAMAGUCHI
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Artigo 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 10310 Fuel burnup calculation and measurement at IEA-R1 research reactor2001 - TERREMOTO, L.A.A.; ZEITUNI, C.A.; PERROTTA, J.A.; TEIXEIRA e SILVA, A.; SILVA, J.E.R.; YAMAGUCHI, M.; TONDIN, J.B.M.; FRAJNDLICH, R.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 12260 Qualification program of research reactor fuels manufactured at IPEN-CNEN/SP2008 - TEIXEIRA e SILVA, A.; TERREMOTO, L.A.A.; SILVA, J.E.R.; ALMEIDA, C.T.; DAMY, M.A.; UMBEHAUN, P.E.; YAMAGUCHI, M.In the last years, IPEN-CNEN/SP has developed the project, technical specifications and the manufacturing of U3O8-Al and U3Si2-Al dispersion fuels. Non-destructive analysis techniques have been an important part of the qualification program of these fuels. Today, for utilization in the IEA-R1 research reactor core of IPEN, the U3O8-Al fuel is qualified up to a uranium density of 2.3 gU/cm3 and the U3Si2-Al fuel up to a uranium density of 3.0 gU/cm3. Also, analogous to the qualification process of U3O8-Al and U3Si2-Al fuels, an extended bibliography revision on the irradiation performance of U-Mo alloy dispersed in aluminum matrix (Al) was carried out to establish a set of parameters that could help in the definition of the technical specifications for manufacturing of this type of fuel at IPEN aiming its posterior utilization in the IEA-R1 reactor. The irradiation performance aspects were associated to the neutronic and thermal-hydraulics aspects in order to propose a new core configuration to the IEA-R1 research reactor using U-Mo dispersion fuels. Core configurations using U-10Mo-Al fuels with uranium densities ranging from 3 to 8 gU/cm3 were analyzed with the computational programs CITATION and MTRCR-IEA-R1. Core configurations for fuels with uranium densities ranging from 3 to 5 gU/cm3 showed to be adequate to be used in IEA-R1 reactor and would present a stable in-reactor performance even at high burnup.