SILVA, A.T.ALMEIDA, C.T.UMBEHAUN, P.E.YAMAGUSHI, M.SILVA, J.E.R.LUCKI, G.2014-11-172014-11-182015-04-012014-11-172014-11-182015-04-01SILVA, A.T.; ALMEIDA, C.T.; UMBEHAUN, P.E.; YAMAGUSHI, M.; SILVA, J.E.R.; LUCKI, G. Neutronic and thermal-hydraulics calculations of U-Mo dispersion fuel for utilization in the IEA-R1 reactor core. In: INTERNATIONAL TOPICAL MEETING ON RESEARCH REACTOR FUEL MANAGEMENT, 10th, April 30 - May 3, 2006, Sofia, Bulgaria. <b>Proceedings...</b> p. 145-149. DisponÃvel em: http://repositorio.ipen.br/handle/123456789/13771.http://repositorio.ipen.br/handle/123456789/13771145-149openAccessiear-1 reactorreactor coresuraniummolybdenumdispersion nuclear fuelsmaterials testing reactorsreactor operationprogrammingNeutronic and thermal-hydraulics calculations of U-Mo dispersion fuel for utilization in the IEA-R1 reactor coreTexto completo de eventohttps://orcid.org/0000-0001-7121-6632https://orcid.org/0000-0002-2887-0759https://orcid.org/0000-0002-7308-5784