DOMINGOS, D.B.SILVA, A.T.SILVA, J.E.R.2014-11-172014-11-182015-04-022014-11-172014-11-182015-04-02DOMINGOS, D.B.; SILVA, A.T.; SILVA, J.E.R. Qualification process of dispersion fuels in the IEA-R1 research reactor. In: INTERNATIONAL TOPICAL MEETING ON RESEARCH REACTOR FUEL MANAGEMENT, 14th, March 21-25, 2010, Marrakech, Morocco. <b>Proceedings...</b> Disponível em: http://repositorio.ipen.br/handle/123456789/17801.http://repositorio.ipen.br/handle/123456789/17801Neutronic, thermal-hydraulics and accident analysis calculations were developed to estimate the safety of a miniplate irradiation device (MID) to be placed in the IEAR1 reactor core. The irradiation device will be used to receive miniplates of U3O8-Al and U3Si2-Al dispersion fuels, LEU type (19,9% of 235U) with uranium densities of, respectively, 3.0 gU/cm3 and 4.8 gU/cm3 . The fuel miniplates will be irradiated to nominal 235U burnup levels of 50% and 80%, in order to qualify the above highdensity dispersion fuels to be used in the Brazilian Multipurpose Reactor (RMB), now in the conception phase. For the neutronic calculation, the computer codes CITATION and TWODB were 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 code LOSS and TEMPLOCA, allowing the calculation of the fuel miniplate temperatures after the reactor pool draining. This paper also presents a system designed for fuel swelling evaluation. The determination of the fuel swelling will be performed by means of the fuel miniplate thickness measurements along the irradiation time.openAccessiear-1 reactordispersion nuclear fuelsswellingTexto completo de eventohttps://orcid.org/0000-0001-7121-6632https://orcid.org/0000-0002-7308-5784