TEIXEIRA e SILVA, A.TERREMOTO, L.A.A.SILVA, J.E.R.ALMEIDA, C.T.DAMY, M.A.UMBEHAUN, P.E.YAMAGUCHI, M.2014-07-152014-07-302014-07-152014-07-302008TEIXEIRA e SILVA, A.; TERREMOTO, L.A.A.; SILVA, J.E.R.; ALMEIDA, C.T.; DAMY, M.A.; UMBEHAUN, P.E.; YAMAGUCHI, M. Qualification program of research reactor fuels manufactured at IPEN-CNEN/SP. <b>Progress in Nuclear Energy</b>, v. 50, n. 7, p. 795-799, 2008. DOI: <a href="https://dx.doi.org/10.1016/j.pnucene.2007.08.007">10.1016/j.pnucene.2007.08.007</a>. Disponível em: http://repositorio.ipen.br/handle/123456789/5107.0149-1970http://repositorio.ipen.br/handle/123456789/5107In 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.795-799openAccessiear-1 reactorresearch reactorsdispersion nuclear fuelsArtigo de periódico75010.1016/j.pnucene.2007.08.007https://orcid.org/0000-0002-2887-0759https://orcid.org/0000-0001-7121-6632https://orcid.org/0000-0002-7308-5784