Evaluation of the acid leaching technique for recovery of U3O8 and ThO2 in niobium/tantalum slag by Vanderlei Vilaça Moura, Talita Santos, Claubia Pereira

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Study of aluminothermic slag leaching for uranium and thorium recovery by VANDERLEI VILAÇA MOURA, Talita Santos, Claubia Pereira

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Artificial neural networks for spatial distribution of fuel assemblies in reload of PWR reactors by Edyene Oliveira, Victor Castro, Carlos Velasquez, Claubia Pereira

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Study of the physical properties of aluminothermic slags for the recovery of uranium and thorium by VANDERLEI VILAÇA MOURA, Talita Oliveira Santos, Claubia Pereira

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Radioactive Background of Granito Madeira, North Amazonas, Brazil by Vanderlei Vilaça MOURA, Talita Oliveira Santos, Claubia Pereira BEZERRA

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A comparative study of boron transport models in NRC thermal-hydraulic code TRACE by N Olmo-Juan, T Barrachina, R Miro, Claubia Lima, Claubia Pereira

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Energy and Exergy Analyses of Angra 2 Nuclear Power Plant by João G. O. Marques, Antonella Lombardi Costa, Claubia Pereira, Ângela Fortini

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Neutronic analysis of a fuel element with variations in fuel enrichment and burnable poison by R de Faria, Felipe Martins, Carlos Velasquez, Angela Fortini, Claubia Pereira

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Neutronic study of ELECTRA using reprocessed fuel and depleted uranium by Clarysson Alberto Mello da silva, Paola Machado de Almeida, Claubia Claubia Pereira

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Methodology for Management and Physicochemical Control of the Cooling Water of the IPR-R1 Triga Nuclear Research Reactor by João Gabriel Oliveira Marques, Amir Zacarias Mesquita, Antonella Lombardi Costa, Claubia Pereira

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Proposta de utilização de redes neurais feedforward multicamadas para a otimização de padrões de recarga do combustível em um reator PWR by Claubia Pereira, Wilmer Aruquipa, Edyene C. A. Oliveira, Clarysson Alberto M. Silva

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Seleção de áreas para a construção de um repositório geológico em Minas Gerais by Claubia Pereira, Raoni A. S. Jonusan, Raphael H. M. Silva, Clarysson Alberto M. Silva

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Neutronic Evaluation of MSBR System Using MCNP Code by Clarysson Alberto Mello da Silva, Alana Lima Vieira, Isabella Resende Magalhães, Claubia Pereira

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Criticality safety analysis of spent fuel pool for a PWR using UO2, MOX, (Th-U)O2 and (TRU-Th)O2 fuels by Claubia Pereira, Jéssica P. Achilles, Fabiano Cardoso, Victor F. Castro, Maria Auxiliadora F. Veloso

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Long term comparison between reprocessed nuclear fuel cycles by Fidéllis Bitencourt Gonzaga Louzada e Estanislau, Carlos Eduardo Velasquez, Antonella Lombardi Costa, Claubia Pereira

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Development of Monte Carlo Models for Neutronic Simulation of SEALER by Jefferson Quintão Campos Duarte, Thalles Oliveira Campagnani, Claubia Pereira, Clarysson Alberto Mello da Silva

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Hydrogen as a Nuclear Thermal Rocket Propellant by Antonella Lombardi Costa, Pedro Augusto Rezende, João Gabriel Oliveira, Claubia Pereira, José Eduardo Mautone

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TRISO fuel thermal simulations in the LS-VHTR by Mario C. Ramos, Maria E. Scari, Antonella Lombardi Costa, Claubia Pereira, Maria A. F. Veloso

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Thermal study of the modular high-temperature gas-cooled reactor by Antonella Lombardi Costa, Mario Cerrogrande Ramos, Vitor Vasconcelos Araújo Silva, Claubia Pereira, Maria Auxiliadora Fortini Veloso

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Simulation of a TRIGA Reactor Core Blockage Using RELAP5 Code by Patrícia A. L. Reis, Antonella L. Costa, Claubia Pereira, Maria Auxiliadora F. Veloso, Amir Z. Mesquita

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