Vol. 7 No. 2B (Suppl.) (2019)

DOI: https://doi.org/10.15392/bjrs.v7i2B
Published: 2019-06-25

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
    DOI: https://doi.org/10.15392/bjrs.v7i2B.352

  • 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
    DOI: https://doi.org/10.15392/bjrs.v7i2B.355

  • 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
    DOI: https://doi.org/10.15392/bjrs.v7i2B.368

  • 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
    DOI: https://doi.org/10.15392/bjrs.v7i2B.386

  • 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
    DOI: https://doi.org/10.15392/bjrs.v7i2B.389

  • 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
    DOI: https://doi.org/10.15392/bjrs.v7i2B.396

  • 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
    DOI: https://doi.org/10.15392/bjrs.v7i2B.398

  • 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
    DOI: https://doi.org/10.15392/bjrs.v7i2B.411

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

    William Luna Salgado, Luis Eduardo Barreira Brandão
    DOI: https://doi.org/10.15392/bjrs.v7i2B.429

  • 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
    DOI: https://doi.org/10.15392/bjrs.v7i2B.431

  • 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
    DOI: https://doi.org/10.15392/bjrs.v7i2B.437

  • 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
    DOI: https://doi.org/10.15392/bjrs.v7i2B.523

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

    Rubens Cavalcante da Silva
    DOI: https://doi.org/10.15392/bjrs.v7i2B.615

  • 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
    DOI: https://doi.org/10.15392/bjrs.v7i2B.616

  • 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
    DOI: https://doi.org/10.15392/bjrs.v7i2B.621

  • 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
    DOI: https://doi.org/10.15392/bjrs.v7i2B.643

  • Energy and Exergy Analyses of Angra 2 Nuclear Power Plant

    João G. O. Marques, Antonella Lombardi Costa, Claubia Pereira, Ângela Fortini
    DOI: https://doi.org/10.15392/bjrs.v7i2B.647

  • TRISO fuel thermal simulations in the LS-VHTR

    Mario C. Ramos, Maria E. Scari, Antonella Lombardi Costa, Claubia Pereira, Maria A. F. Veloso
    DOI: https://doi.org/10.15392/bjrs.v7i2B.648

  • 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
    DOI: https://doi.org/10.15392/bjrs.v7i2B.682

  • 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
    DOI: https://doi.org/10.15392/bjrs.v7i2B.691

  • 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
    DOI: https://doi.org/10.15392/bjrs.v7i2B.756

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

    Edyene Oliveira, Victor Castro, Carlos Velasquez, Claubia Pereira
    DOI: https://doi.org/10.15392/bjrs.v7i2B.770

  • 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
    DOI: https://doi.org/10.15392/bjrs.v7i2B.769

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

    N Olmo-Juan, T Barrachina, R Miro, Claubia Lima, Claubia Pereira
    DOI: https://doi.org/10.15392/bjrs.v7i2B.767