Vol. 10 No. 3A (Suppl.) (2022): XXII ENFIR / VII ENIN

The XXII Meeting on Nuclear Reactor Physics and Thermal hydraulics (XXII ENFIR) and VII Meeting on Nuclear Industry (VII ENIN) (Suppl.)

DOI: https://doi.org/10.15392/bjrs.v10i3A
Published: 2022-12-04

INAC 2021_XXII ENFIR_VII_ENIN

  • Thermal study of the modular high-temperature gas-cooled reactor

    Antonella Lombardi Costa, Mario Cerrogrande Ramos, Vitor Vasconcelos Araújo Silva , Claubia Pereira, Maria Auxiliadora Fortini Veloso

  • Optimization of a microreactor core's dimensions using metaheuristic methods

    Nicolas Santana, Alexandre Caldeira, Angelo Passaro, Lamartine Guimaraes
    DOI: https://doi.org/10.15392/2319-0612.2022.1903

  • Computational model for thermohydraulic analysis of an integral pressurized water reactor with mixed oxide fuel (Th, Pu)O2

    Mariana Cecilia Betancourt, Pedro E Moraes Santos, Leorlen Y. Rojas Mazaira, Carlos R. García Hernández, Dany S Dominguez, Carlo A BRAYNER DE OLIVEIRA LIRA, Jesús A Rosales Garcías
    DOI: https://doi.org/10.15392/2319-0612.2022.1943

  • Comparison of Estimates of Costs involved between two Decommissioning Strategies for PWR type Nuclear Power Plants

    M. V. A. de Oliveira; G. L. de Stefanni
    01-06
    DOI: https://doi.org/10.15392/2319-0612.2022.1962

  • Decision Support Method in the Assessment of Nuclear Knowledge Management using Fuzzy Logic

    Claudio Henrique dos Santos Grecco, Jaqueline Tavares Viana de Souza, Paulo Victor Rodrigues Carvalho, Carlos Alberto Nunes Cosenza
    DOI: https://doi.org/10.15392/2319-0612.2022.1785

  • Radiation shielding for a nuclear fusion device with inertial electrostatic confinement

    Seung Min Lee, Eduardo Lobo Lustosa Cabral, Helio Yoriyaz
    DOI: https://doi.org/10.15392/2319-0612.2022.1997

  • The adjoint transport problem applied to estimate neutral particle leakage in the discrete ordinates formulations

    Jesús P. Curbelo, Ricardo C. Barros
    DOI: https://doi.org/10.15392/2319-0612.2022.1850

  • Encapsulated OSB Energy Absorption Potential A Preliminary Analysis

    Daniel Silva de Mello Carvalho, Miguel Mattar Neto
    DOI: https://doi.org/10.15392/2319-0612.2022.1874

  • IEA-R1 Renewed Primary System Pump B1-B Nozzles Stress Analysis

    A. A. Faloppa, G. Fainer, C. D. R. Figueiredo , D. S. M. Carvalho, M. Mattar Neto
    01-14
    DOI: https://doi.org/10.15392/2319-0612.2022.1892

  • Must Nuclear Energy be Increased on Brazilian Energy Mix in a Post-COVID-19 World?

    L. A. Ferrari, J. M. S. Ayoub, R. L. A. Tavares, A. L. C. Silva, J. A. Seneda
    01-20
    DOI: https://doi.org/10.15392/2319-0612.2022.1920

  • CFD analysis of a wire-wrapped infinite sub-channel using temperature-dependent LBE properties

    Ivan Keiti Umezu, Antonella Lombardi Costa, Dario Martin Godino, André Augusto Campagnole dos Santos
    DOI: https://doi.org/10.15392/2319-0612.2022.1949

  • Review of Regulatory Requirements for Implementing an Aging Management System for the IPR-R1 Triga Reactor of CDTN

    ANA ROSA BALIZA, AMIR ZACARIAS MESQUITA, youssef morghi
    DOI: https://doi.org/10.15392/2319-0612.2022.1985

  • The evolution of the nuclear emergency response plan using mechanisms of learning, innovation and communication

    André Luiz Quadros
    DOI: https://doi.org/10.15392/2319-0612.2022.1832

  • Risk-based design of electric power systems for non-conventional nuclear facilities at shutdown modes

    S. S. Borsoi, D. B. Baroni, M Mattar Neto, P. S. P. Oliveira, M. C. Maturana
    01-17
    DOI: https://doi.org/10.15392/2319-0612.2022.2063

  • Effect of Mounting Orientation on Testing Equipment on Elastic Compliance of Clamped SE(T) Specimens: an exploration

    Leonardo Andrade, Gustavo Donato, Miguel Mattar Neto
    DOI: https://doi.org/10.15392/2319-0612.2022.1863

  • The Study on the sociocultural profile of women working in a Brazilian nuclear area institution Study on the sociocultural profile of women working in a Brazilian nuclear area institution

    Ana Gabryele Moreira dos Santos, Priscila , Karoline Feitoza Suzart, Nelida del Mastro
    DOI: https://doi.org/10.15392/bjrs.v10i3A.1882

  • Passive Autocatalytic Recombiner Perfomance Assessment Using COCOSYS

    hugo pontes, gil teixeira, julian shorto, Alfredo abe, Cláudia Giovedi
    DOI: https://doi.org/10.15392/2319-0612.2022.1906

  • PSO-based modeling particulate emission rates in nuclear accidents

    Douglas Rodriguez Brasil, Andressa dos Santos Nicolau, Roberto Schirru, Cláudio Márcio do Nascimento Abreu Pereira
    DOI: https://doi.org/10.15392/2319-0612.2022.1944

  • Energy and Covid 19 Analysis of the Impact on the Global Energy Matrix

    Luiz Antonio Ferrari
    DOI: https://doi.org/10.15392/2319-0612.2022.1966

  • Hydrogen as a Nuclear Thermal Rocket Propellant

    Antonella Lombardi Costa, Pedro Augusto Rezende , João Gabriel Oliveira, Claubia Pereira, José Eduardo Mautone
    DOI: https://doi.org/10.15392/2319-0612.2022.1825

  • Long term comparison between reprocessed nuclear fuel cycles

    Fidéllis Bitencourt Gonzaga Louzada e Estanislau, Carlos Eduardo Velasquez, Antonella Lombardi Costa, Claubia Pereira
    DOI: https://doi.org/10.15392/2319-0612.2022.1999

  • PLATAGAM: a videogame structured as a didactical material for divulgation of some of the benefits of the Gamma Radiation produced in the Cobalt-60 Multipurpose Irradiator at IPEN’s facilities

    Patricia Andrea Paladino, Flavia Paladino Biaty, Arthur Pires Julião, Gaianê Sabundjian
    DOI: https://doi.org/10.15392/2319-0612.2022.1851

  • Copper water heat pipe applied for Stirling engine

    Ana Carolina Santos, Lamartine Nogueira Frutuoso Guimarães , Valéria Serrano Faillace Oliveira Leite
    DOI: https://doi.org/10.15392/2319-0612.2022.1876

  • An Analysis of Scientific Literature Production Related to Radiation Protection and Strategic Environmental Assessment

    Rócio Gloria dos Reis, Ana Cristina de Melo Ferreira
    DOI: https://doi.org/10.15392/2319-0612.2022.1893

  • A Criticality and depletion analysis of the European Lead-Cooled Training Reactor (ELECTRA)

    Ana Luiza Pereira Oliveira, Clarysson Alberto Mello da Silva
    DOI: https://doi.org/10.15392/2319-0612.2022.1940

  • Evaluation of “Safety Related” and “Important to Safety” terminology for safety classification of nuclear installation items in Brazil

    Douglas, Sad, Patrícia, Miguel, Marcos
    DOI: https://doi.org/10.15392/2319-0612.2022.1960

  • Design considerations for rectangular bolted full face flanged joints for surface condensers

    Augusto Soave, Miguel Mattar Neto
    DOI: https://doi.org/10.15392/2319-0612.2022.1989

  • Molten Salt Reactor thermal-fluid dynamics evaluation using a CFD code for a theoretical power density distribution

    Deiglys Borges Monteiro, Letícia Caroline Gonçalvez, José Rubens Maiorino, Pedro Carlos Russo Rossi
    DOI: https://doi.org/10.15392/2319-0612.2022.1833

  • Licensing Approach Applicable to Land Facilities Supporting Nuclear-Powered Submarines

    Douglas Baroni, S Borsoi, M Mattar Neto, P Oliveira, M Maturana
    DOI: https://doi.org/10.15392/2319-0612.2022.2083

  • Study of radiation protection vestments for maintenance of mobile nuclear power plants

    Pedro Celestino, Dr. Gian Maria Angelo Agostinho Sordi
    01-16
    DOI: https://doi.org/10.15392/2319-0612.2022.1867

  • The Validation Analysis Methodology to Determine the Cadmium, Indium and Impurities Concentration in Nuclear Grade Silver-indium-cadmium Alloys

    Guilherme Costa de Oliveira
    DOI: https://doi.org/10.15392/2319-0612.2022.1883

  • Consequence Analysis of a Station Blackout in Brazilian Nuclear Power Plant Angra 2

    Andre S Aguiar, Seung Min Lee, Gaianê Sabundjian
    DOI: https://doi.org/10.15392/2319-0612.2022.1918

  • Macroscopic cross section generation with WIMS-ANL for a PWR

    Wilmer Aruquipa Coloma, Patrícia Amélia de Lima Reis, Clarysson Alberto Mello da Silva, Claubia Pereira Bezerra Lima
    DOI: https://doi.org/10.15392/2319-0612.2022.1948

  • External Events PSA – Requirements Applicable to New Nuclear Installations Projects after Fukushima Daiichi Accident

    T. P. Silva, M. C. Maturanaa, P. S. P. de Oliveira, M. Mattar Neto
    DOI: https://doi.org/10.15392/2319-0612.2022.1977

  • Simulation of steady-state and transient loss of cooling accident of a channel in a reactor plate-type fuel element

    D. B. Monteiro, J. R. Maiorino
    01-14
    DOI: https://doi.org/10.15392/2319-0612.2022.1829

  • Analytical solution of the multigroup neutron diffusion equation coupled with an iterative method

    Adilson Costa da Silva, Aquilino Martinez, Rodrigo Diniz, Alessandro Gonçalves
    DOI: https://doi.org/10.15392/2319-0612.2022.2005

  • Methodology for Management and Physicochemical Control of the Cooling Water of the IPR-R1 Triga Nuclear Research Reactor

    João Gabriel Oliveira Marques, Amir Zacarias Mesquita, Antonella Lombardi Costa, Claubia Pereira
    DOI: https://doi.org/10.15392/2319-0612.2022.1857