Vol. 7 Núm. 2B (Suppl.) (2019): XX ENFIR (Suppl.)

XX Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XX ENFIR)

• Removal of cobalt from lubricant oil by the use of bentonite: equilibrium, kinetic and adsorption preliminary studies

  VALERIA CUCCIA, SANDRO ROGÉRIO NOVAES SELES, ANA CLAUDIA QUEIROZ LADEIRA

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• Image quality assessment using NEMA NU 4/2008 standards in small animal PET scanner

  Andréa Vidal Ferreira, Rodrigo Modesto Gadelha Gontijo, Juliana Batista Silva, Marcelo Henrique Mamede

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• Human reliability in non-destructive inspections of nuclear power plant components: modeling and analysis

  Vanderley Vasconcelos, Wellington Antonio Soares, Raissa Oliveira Marques, Silvério Ferreira Silva Jr, Amanda Laureano Raso

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• Determination of the Scattered Radiation at the Neutron Calibration Laboratory of IPEN using the Shadow Cone Method

  Tallyson Sarmento Alvarenga, Bruno Mendes Freitas, Evaldo S Fonseca, Walsan W Pereira, Linda V.E Caldas

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• Analytical representation of the solution of the space kinetic diffusion equation in a one-dimensional and homogeneous domain

  Fernanda Tumelero, Celso M. F. Lapa, Bardo E. J Bodmann, Marco T. Vilhena

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• Human factors engineering and participatory design in the project of a nuclear research reactor control centre

  Larissa Pereira Farias, Isaac Antônio Luquetti dos Santos, Paulo Victor Rodrigues de Carvalho, Beany Guimaraes Monteiro

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• Simulation of Mechanical Behavior of Fuel Pellets With Different Geometries

  Amanda Abati Aguiar, Danilo Faria, José Berretta, Paulo Afonso Rodi, Marcelo Santos, Antônio Teixeira e Silva

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• Release of alpha emitters into the environment by nuclear industries of Brazil in Resende

  Wagner Souza Pereira, Alphonse Kelecom, Rodney Santos, Maysa Fernades Martins Santos, Vinicius Romero Mozer Torres, Jessica Julielle da Silva Rodrigues, César Marques Salgado, Izabella Christynne Ribeiro Pinto Valadão

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• Study of volume fractions on biphasic stratified regime using gamma ray

  William Luna Salgado, Luis Eduardo Barreira Brandão

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• Investigation of polymer-based BaO and rGO nanocomposites for application in low energy X ray attenuation

  LILIANE Aparecida SILVA, adriana Batistab, Jefferson Nascimentoc, Clascidia Furtadoc, Luiz Faria

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• A CFD analysis of blockage length on a partially blocked fuel rod

  Nikolas Lymberis Scuro, Pedro Ernesto Umbehaun, Edvaldo Angelo, Gabriel Angelo, Delvonei Alves de Andrade

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• DOSE RATE IN A DEACTIVATED URANIUM MINE

  Wagner De Souza Pereira, Alphonse Kelecom, Ademir Xavier da Silva, José Marquez Lopes, Alessander Sá do Carmo, Ayandra Oliveira Dias, Carlos Eduardo Cogo Pinto

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• Experimental Estimation of Moderator Temperature Coefficient of the IPEN-MB-01 Reactor

  Rubens Cavalcante da Silva

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• Definition of parameters for a test section for the analysis of natural convection and coolant loss in the AP1000 nuclear reactor by similarity laws and fractional scaling analysis

  Luis Felipe Serra Cadiz, Mario Silva, Fernando Roberto de Andrade Lima, Carlos Alberto Oliveira

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• Simplified CFD model of coolant channels typical of a plate-type fuel element: an exhaustive verification of the simulations

  Javier González Mantecón, Miguel Mattar Neto

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• Applying Human Factors Engineering Program to the Modernization Project of NPP Control Room in accordance with U.S.NRC and KTA Regulations

  Renato Koga de Avellar, Roberto Schirru

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• Energy and Exergy Analyses of Angra 2 Nuclear Power Plant

  João G. O. Marques, Antonella Lombardi Costa, Claubia Pereira, Ângela Fortini

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• TRISO fuel thermal simulations in the LS-VHTR

  Mario C. Ramos, Maria E. Scari, Antonella Lombardi Costa, Claubia Pereira, Maria A. F. Veloso

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• Simulation of a severe accident at a typical PWR due to break of a hot leg ECCS injection line using MELCOR code.

  Seung Min Lee, Nelbia da Silva Lapa, Gaianê Sabundjian

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• Design of a digital system for operational parameters simulation of IPR-R1 Triga nuclear research reactor

  Aldo Márcio Fonseca Lage, Adriano Almeida Massaud Felippe, Amir Zacarias Mesquita

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• Brayton cycle numerical modeling using the RELAP5-3D code, version 4.3.4

  Eduardo Pedroso Longhini, Paulo David de Castro Lobo, Lamartine Nogueira Frutuoso Guimarães, Francisco Antonio Braz Filho, Guilherme Borges Ribeiro

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• Artificial neural networks for spatial distribution of fuel assemblies in reload of PWR reactors

  Edyene Oliveira, Victor Castro, Carlos Velasquez, Claubia Pereira

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• Neutronic analysis of a fuel element with variations in fuel enrichment and burnable poison

  R de Faria, Felipe Martins, Carlos Velasquez, Angela Fortini, Claubia Pereira

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• A comparative study of boron transport models in NRC thermal-hydraulic code TRACE

  N Olmo-Juan, T Barrachina, R Miro, Claubia Lima, Claubia Pereira

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