MITSUO YAMAGUCHI
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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 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.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.