Meeting on Nuclear Reactor Physics and Thermal Hydraulics (ENFIR)

All Items

• Virtual Visit to Research Reactor IPEN/MB-01

  Yulia Coelho, G. Sabundjian

  e2771

• Verification of Steel Plate as Target for 9-Meter-High Cask Drop Tests

  Heloisa Maria Santos Oliveira, Lucca Daré Venturini, Cláudio Cunha Lopes, Luiz Leite da Silva, Vitor Vasconcelos Araújo Silva, Emerson Giovani Rabello, Graiciany de Paula Barros, Andre Augusto Campagnole dos Santos

  e2710

• Use of clays in the treatment of  radioactive aqueous waste generated at the CDTN

  Hellen Késia Santos de Souza, Maria Judite Afonso Haucz, Carolina Braccini Freire

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• Use of Augmented Reality in the Design of Land Facilities Supporting Nuclear-Powered Submarines

  Cristiane Lopes Canuto, Rodrigo Toth Reis, Paulo Caixeta de Oliveira, Douglas Brandão Baroni, Thiago Rampim de Marcos, Sad Sandrini Borsoi, Gabriel Nóbile Diniz

  e2714

• Thermohydraulic Performance in SMR Reactors with Mixed Oxide (U, Th)O2 Fuel: A Computational Approach

  Pedro Emanuel Moraes Santos, Mariana Cecilia Betancourt, Leorlen Yunier Rojas Mazaira, Carlos Rafael García Hernández, Dany Sanchez Dominguez, Carlos Alberto Brayner de Oliveira Lira

  e2674

• Study on the Licensing Framework for Land Facilities Supporting Nuclear-powered Submarines in the United Kingdom

  Douglas Brandão Baroni, Sad Sandrini Borsoi, Yuri Sartore Almada Soares, Miguel Mattar Neto, Patrícia Silva Pagetti de Oliveira, Marcos Coelho Maturana

  e2672

• Steady-State Coupled Calculations (Serpent-GeN-FOAM) Applied to Molten Salt Fast Reactor (MSFR)

  Tiago Augusto Santiago Vieira, Geovana Loren Cruz, Yasmim Martins Carvalho, Geovana Carvalho Silva, Keferson Almeida Carvalho, Rebeca Cabral Gonçalves, Vitor Vasconcelos Araújo Silva, Graiciany Paula Barros, Andre Augusto Campagnole dos Santos

  2643

• Safety Analysis Reports of First-Of-A-Kind Nuclear Reactors in Brazil: Proposal of Content for Deterministic Safety Analysis

  Nelson Luiz Dias Ferreira, Claudia Giovedi Motta, Mike Modro, Alessandro Petruzzi

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• QUALITY CONTROL TESTS FOR CALIBRATION OF KAP METERS.

  José Neres de Almeida Junior, Dra. Maria da Penha Albuquerque Potiens, Dr. Orlando Rodrigues Junior

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• Proposal for Safety Classification of SSC for Land-Based Facilities to Support Nuclear-Powered Submarines

  Douglas Brandão Baroni, Hélio Massaharu Murata, Fagner Chagas Rother, Anelise Ruzzarin, William Henrique Silva Profeta, Sad Sandrini Borsoi, Eduardo Ascenso Reis Ribeiro, Luana Soares Jorge

  e2591

• Preliminary Risk Analysis for the Installation of Small Modular Reactors in Energy-Deficient Regions of Brazil

  Vitor Assi, Gaianê Sabundjian, Orlando Si Kae Fang

  e2779

• Overview of Fourth Generation Reactors Studied at the Universidade Federal de Minas Gerais (Brazil)

  Clarysson Alberto Mello da Silva, Anderson Altair Pinheiro de Macedo, Maurício Gilberti, Fabiano Cardoso da Silva, Isabella Resende Magalhães, Antonella Lombardi Costa, Claubia Pereira

  e2419

• Neutronic study of ELECTRA using reprocessed fuel and depleted uranium

  Clarysson Alberto Mello da silva, P. M. de Almeida, Pereira C.

  e2677

• Modeling nuclear fuel assemblies through porous zones in a Small Modular Reactor: fluid dinamic considerations

  Rebeca Cabral Gonçalves, Geovana Carvalho Silva, Fernando Lage Araújo Schweizer, Pedro Andrade Maia Vinhas, Keferson de Almeida Carvalho, Tiago Augusto Santiago Vieira, Vitor Vasconcelos Araújo Silva, Graiciany de Paula Barros, Andre Augusto Campagnole dos Santos

  e2708

• IPR-R1 Triga Reactor aging management approach

  Dra. Denise das mercês Camarano, Emanuelle Costa e Silva, Jefferson José Vilela, Amir Zacarias Mesquita

  e2670

• Initial Safety Parameter Evaluation of a PWR Loaded with Thorium and Reprocessed Fuel

  Matheus Henrique dos Santos Araújo, Graiciany de Paula Barros, Geovana Loren da Cruz, Keferson Almeida Carvalho, Vitor Silva, Andre Augusto Campagnole dos Santos

  2688

• Improvements and Safety Analysis on the Technologies of Current Nuclear Power Systems for Remote Places and Outer Space Melhorias e Análise de Segurança nas Tecnologias Atuais de Sistemas de Energia Nuclear para Lugares Remotos e Espaço Sideral

  Julio de Oliveira Jr., Dr D. S. Samokhin

  e2534

• Geometrical optimization of PWR spacer grids using GeN-Foam and Genetic Algorithms

  Carlos Rodrigo Dias, Tiago Augusto Santiago Vieira, Andre Augusto Campagnole dos Santos, Graiciany de Paula Barros, Vitor Vasconcelos Araújo Silva, Ana Luiza Miranda Froes, Rebeca Cabral Gonçalves, Keferson de Almeida Carvalho, Higor Fabiano Pereira de Castro

  e2704

• Floating NPP for co-generation of electricity and water desalination in Brazil

  Maritza R. Gual, Hugo Romberg, Araújo, Nathalia N., Marcos C. Maturana

  e2700

• Environmental costs of nuclear reactors: a literature review

  Flavia P. Biaty, Giovana Ciongoli, Patricia A. Paladino, Gaianê Sabundjian

  e2551

• Efficient Acceleration in Solving the 2D Neutron Diffusion Equation with CUDA: Exploring the Collaborative Practicality of Colab

  Paulo Igor de Oliveira Pessoa, Dr. Edson Henrice

  e2498

• Development of Monte Carlo Models for Neutronic Simulation of SEALER

  J. Q. C. Duarte, T. O. Campagnani, C. Pereira, Clarysson Alberto Mello da Silva

  e2678

• Development of a semi-analytical nodal methodology for one-dimensional eigenvalue problems based on multigroup neutron transport theory using the discrete ordinate formulation

  Natália Rocha Pinheiro, Francisco Bruno Souza Oliveira, Hermes Alves Filho

  e2940

• Depletion and inventory calculation for the new fuel of IEN's Argonauta reactor

  Iago Gomes, Victor Lassance, Maria de Lourdes Moreira

  e2772

• Computational Fluid Dynamics study of element type and turbulence model impact on a flow over a spacer grid using Simcenter STAR-CCM+

  Tiago Augusto Santiago Vieira, Yasmim Martins Carvalho, Higor Fabiano Pereira de Castro, Keferson Almeida Carvalho, Rebeca Cabral Gonçalves, Pedro Henrique Araújo, Davi Cury, Vitor Vasconcelos Araújo Silva, Graiciany Paula Barros, Andre Augusto Campagnole dos Santos

  e2658