Vol. 8 No. 3A (Suppl.) (2020)

DOI: https://doi.org/10.15392/bjrs.v8i3A
Published: 2020-12-01

XXI Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XXI ENFIR) and VI ENIN

  • Anatomical movement replicator applied to activities in ionizing radiation fields

    Amir Zacarias Mesquita
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1266

  • The modified spectral deterministic method applied to fixed–source discrete ordinates problems in X,Y–geometry

    Jesús Pérez Curbelo, Rafael Barbosa Libotte, Amaury Muñoz Oliva, Ricardo Carvalho Barros, Hermes Alves Filho
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1268

  • Thermophysical properties of nanofluids MWCNT (multi-walled carbon nanotubes) in water for emergency coolant from nuclear reactors

    Alexandre Melo Oliveira, Amir Zacarias Mesquita, Enio Pedone Bandarra, Daniel Flórez Morales
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1280

  • Nuclear Power Plants event classification based on International Reporting System (IRS)

    Richard Brandão Nogueira Vital, Jefferson Borges Araujo, Tatiane Melo Vital
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1282

  • Concentration and distribution of oil in the reservoir mineral Dolomite studied by neutron tomography

    Reynaldo Pugliesi, Marco Antônio Stanojev Pereira, Marcos Leandro Garcia Andrade
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1291

  • Numerical and experimental investigation of the water flow through PWR spacer grids

    Higor Fabiano Pereira de Castro, Guilherme Augusto Moura Vidal, Tiago Augusto Santiago Vieira, Vitor Vasconcelos Araújo Silva, Daniel de Almeida Magalhães Campolina, Graiciany de Paula Barros, Rebeca Cabral Gonçalves, Andre Augusto Campagnole dos Santos, Maria Auxiliadora Fortini Veloso
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1294

  • Analysis of pressure drop in a numerical simulation of internal nanofluids flow

    Marcos Barroso Filho
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1298

  • Analysis of Heat Transfer Performance in a Brayton Cycle Recuperator

    Elvis Falcão de Araújo, Guilherme Borges Ribeiro, Lamartine Nogueira Frutuoso Guimarães
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1300

  • Commercial grade dedication challenges for Brazilian nuclear industry

    ANA ROSA BALIZA MAIA, youssef morghi, AMIR ZACARIAS MESQUITA
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1302

  • ASME in-service inspection and in-service testing programs for Angra 1

    ANA ROSA BALIZA MAIA, youssef morghi, AMIR ZACARIAS MESQUITA
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1307

  • Knowledge Management in the Decommissioning of Nuclear Facilities in Brazil

    Ricardo Bastos Smith, Tereza Cristina Salvetti, Ana Paula Gimenes Tessaro, Júlio Takehiro Marumo, Roberto Vicente
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1315

  • Lessons Learned: a knowledge management tool for learning about radiation accidents

    Luis Carlos Jansen Silva, Fernando Barcellos Razuck
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1353

  • MODELING LOFW IN A PWR USING MELCOR

    Maritza Rodríguez Gual, Marcos C. Maturana, Nathália N. Araújo, Marcelo R. Martins
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1355

  • MELCOR steady state calculation of the generic PWR of 40MWth

    Maritza Rodríguez Gual, Nathalia N. Araújo, Marcos C. Maturana
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1357

  • Knowledge management of research data: an initial analysis of Institute of Radiation Protection and Dosimetry

    Fernando Barcellos Razuck
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1359

  • Advanced Heavy Water Reactor: A New Step Toward Sustainability

    Ricardo Bastos Smith, Mahima Sachdeva, Indranil Bisuri, Roberto Vicente
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1368

  • FUNDING AND FINANCE ISSUES RELATED TO THE DECOMMISSIONING OF BRAZILIAN NPPS

    Daniel Artur Pinheiro Palma, Anna Leticia Barbosa de Souza, Amir Zacarias Mesquita
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1369

  • Decommissioning cost estimation for a multiple reactor site with interdependent plants: case study using a new management tool and top-down approach

    Deiglys Borges Monteiro, João Manoel Lousada Moreira, José Rubens Maiorino
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1404

  • Crystallographic texture of hot rolled uranium-molybdenum alloys

    Guilherme Fernandes Nielsen, Nathanael Wagner Sales Morais, Nelson Batista de Lima
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1406

  • New advances in the computational simulation of Aqueous Homogeneous Reactor for medical isotopes production

    Daniel Milian Pérez, Liván Hernández Pardo, Daylen Milian Pérez, Abel Gámez Rodríguez, Daniel Evelio Milian Lorenzo, Carlos Alberto Brayner de Oliveira Lira
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1409

  • A NOVEL COARSE-MESH METHOD APPLIED TO NEUTRON SHIELDING PROBLEMS USING THE MULTIGROUP TRANSPORT THEORY IN DISCRETE ORDINATES FORMULATIONS

    Rafael Barbosa Libotte, Hermes Alves Filho, Ricardo Carvalho de Barros
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1421

  • Neutron angular flux reconstruction in slab geometry using multigroup discrete ordinates transport models

    F. T. C. S. Balbina, R. C. Barros, H. Alves Filho
    01-18
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1429

  • Dynamic mode decomposition of numerical data in natural circulation

    José Luiz Horacio Faccini
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1431

  • NUCLEAR SECURITY IN THE BRAZILIAN REALITY

    RODRIGO CARNEIRO CURZIO, JOAO CLAUDIO BATISTA FIEL, BRUNO DA SILVA MOURA, WALINTON EVANGELISTA DE SOUSA, LUAN JARDIM BONFIM
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1452

  • Modeling dynamic scenarios for safety, reliability, availability, and maintainability analysis

    Cesar Augusto Gabe, Luciano Ondir Freire, Delvonei Alves de Andrade
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1464

  • New 3D Diffusion Code Based on The Nodal Polynomial Expansion

    Jadna Mara Santos Mendes, Sérgio Barros Paixão, Sergio de Oliveira Vellozo
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1489

  • On the spectral Green’s function-constant nodal method for fixed-source SN problems in X,Y-geometry with arbitrary L’th-order anisotropic scattering

    Welton Menezes, Gustavo Alvarez, Ricardo Barros
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1490

  • Determination of fluid dynamic parameters through imports of CFD images validated in experiments for the MCNPX code.

    Victor Hugo Farias Ferreira da Silva, Carlos Costa Dantas, Silvio de Barros Melo, Fernando Roberto de Andrade Lima, Pamalla Rafaelly Barbosa de Oliveira, Tennyson Accetti Resende Filho, Jorge Alexandre Gomes Lins, Eudes Bertony Vieira, Bruno Gomes Andrade, Milton Santos Viana
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1498

  • Simulation for non-homogeneous transport equation by Nyström method

    Luana Lazzari, Esequia Sauter, Fábio Souto De Azevedo
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1507

  • The future of nuclear energy and maritime power relations

    Claudio Rodrigues Corrêa, Taíssi Pepe de Medeiros, Gustavo André Guimarães
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1520

  • Technology transfer: the case of the Centro de Desenvolvimento da Tecnologia Nuclear (Nuclear Technology Development Center)

    Xênia Aparecida Chaves Santos, Régia Ruth Ramirez Guimarães, Gustavo José Pereira, Sérgio Almeida Cunha Filgueiras
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1521

  • Computational simulation of a test facility in reduced scale for analysis of boron dispersion in a pressurizer of an integral compact and modular reactor

    Leorlen Y. Rojas Mazaira, Carlos R. Garcia, Carlos Alberto Brayner Oliveira Lira, Dany S. Dominguez, Abel Gámez, Daniel González, Jesús A. Rosales, Fernando R.A. Lima, Jair L. Bezerra, Mário A.B. Silva
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1535

  • Impact of variable porosity models on the safety of high temperature pebble bed gas-cooled reactors

    ABEL GÁMEZ RODRÍGUEZ, Leorlen Y Rojas Mazaira, Daniel Milian Perez, Dany Sanchez Dominguez, Carlos Rafael García Hernández, Carlos Alberto Brayner de Oliveira Lira
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1542

  • RMB experimental program on the hydrodynamical behavior of fuel assemblies

    Walmir Máximo Torres, Pedro Ernesto Umbehaun, Miguel Mattar Neto, Antonio Belchior Jr., Roberto Longo Freitas
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1555

  • RELAP5 Modeling of a Siphon Break Effect on the Brazilian Multipurpose Reactor

    Humberto Vitor Soares, Antonio Belchior Jr., Roberto Longo Freitas
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1563

  • Preliminary neutronic study of the S-PRISM fast reactor

    João Manoel Losada Moreira
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1580

  • Nuclear qualification of electrical equipment: challenges for the Brazilian industry

    João Manoel Losada Moreira
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1581

  • Periodic Inspection Program of Nuclear PWR reactor Pressure Vessel

    Anne Aguiar Araujo
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1587

  • Recommendation for linearization procedure in nuclear pressure vessel-nozzle intersections

    Carolina Della Ricco Figueiredo, Miguel Mattar Neto
    DOI: https://doi.org/10.15392/bjrs.v8i3A.1572