Vol. 10 Núm. 3A (Suppl.) (2022): XXII ENFIR / VII ENIN

INAC 2021_XXII ENFIR_VII_ENIN

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

  Luiz Antonio Ferrari

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

  Andre S Aguiar, Seung Min Lee, Gaianê Sabundjian

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• 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

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

  Ana Luiza Pereira Oliveira, Clarysson Alberto Mello da Silva

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• 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

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• PSO-based modeling particulate emission rates in nuclear accidents

  Douglas Rodriguez Brasil, Andressa dos Santos Nicolau, Roberto Schirru, Cláudio Márcio do Nascimento Abreu Pereira

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• 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

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• 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

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

  Douglas Brandão Baroni, Sad Sandrini Borsoi, Patrícia Pagetti de Oliveira, Miguel Mattar Neto, Marcos Coelho Maturana

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• 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

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• Passive Autocatalytic Recombiner Perfomance Assessment Using COCOSYS

  hugo pontes, gil teixeira, julian shorto, Alfredo abe, Cláudia Giovedi

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• 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

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• 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

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

  Augusto Soave, Miguel Mattar Neto

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

  Seung Min Lee, Eduardo Lobo Lustosa Cabral, Helio Yoriyaz

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• Long term comparison between reprocessed nuclear fuel cycles

  Fidéllis Bitencourt Gonzaga Louzada e Estanislau, Carlos Eduardo Velasquez, Antonella Lombardi Costa, Claubia Pereira

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

  Adilson Costa da Silva, Aquilino Martinez, Rodrigo Diniz, Alessandro Gonçalves

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• 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

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

  Douglas Baroni, S Borsoi, M Mattar Neto, P Oliveira, M Maturana

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

  P. A. P. Celestino, G. M. A. A. Sordi

  01-16

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• Hydrogen as a Nuclear Thermal Rocket Propellant

  Antonella Lombardi Costa, Pedro Augusto Rezende , João Gabriel Oliveira, Claubia Pereira, José Eduardo Mautone

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• 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

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

  André Luiz Quadros

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• 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

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

  Jesús Pérez Curbelo, Ricardo Carvalho de Barros

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• 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

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• 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

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

  Leonardo Andrade, Gustavo Donato, Miguel Mattar Neto

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• 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

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• Encapsulated OSB Energy Absorption Potential A Preliminary Analysis

  Daniel Silva de Mello Carvalho, Miguel Mattar Neto

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• Copper water heat pipe applied for Stirling engine

  Ana Carolina Santos, Lamartine Nogueira Frutuoso Guimarães , Valéria Serrano Faillace Oliveira Leite

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• 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

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• 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 Santos Rodrigues, Karoline Feitoza Suzart, Nelida del Mastro

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

  Guilherme Costa de Oliveira

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• 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

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

  Rócio Gloria dos Reis, Ana Cristina de Melo Ferreira

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

  Nicolas Santana, Alexandre Caldeira, Angelo Passaro, Lamartine Guimaraes

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