Vol. 8 No. 3A (Suppl.) (2020): XXI ENFIR / VI ENIN 2019 - Vol A (Suppl.)

XXI Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XXI ENFIR) and VI ENIN 2019 - Vol A (Suppl.)

39 papers published.

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

Richard Brandão Nogueira Vital, Jefferson Borges Araujo, Tatiane Melo Vital
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Concentration and distribution of oil in the reservoir mineral Dolomite studied by neutron tomography

Reynaldo Pugliesi, Marco Antônio Stanojev Pereira, Marcos Leandro Garcia Andrade
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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
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Analysis of pressure drop in a numerical simulation of internal nanofluids flow

Marcos Barroso Filho
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Analysis of Heat Transfer Performance in a Brayton Cycle Recuperator

Elvis Falcão de Araújo, Guilherme Borges Ribeiro, Lamartine Nogueira Frutuoso Guimarães
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Commercial grade dedication challenges for Brazilian nuclear industry

ANA ROSA BALIZA MAIA, youssef morghi, AMIR ZACARIAS MESQUITA
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ASME in-service inspection and in-service testing programs for Angra 1

ANA ROSA BALIZA MAIA, youssef morghi, AMIR ZACARIAS MESQUITA
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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
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Lessons Learned: a knowledge management tool for learning about radiation accidents

Luis Carlos Jansen Silva, Fernando Barcellos Razuck
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MODELING LOFW IN A PWR USING MELCOR

Maritza Rodríguez Gual, Marcos C. Maturana, Nathália N. Araújo, Marcelo R. Martins
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MELCOR steady state calculation of the generic PWR of 40MWth

Maritza Rodríguez Gual, Nathalia N. Araújo, Marcos C. Maturana
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Knowledge management of research data: an initial analysis of Institute of Radiation Protection and Dosimetry

Fernando Barcellos Razuck
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Advanced Heavy Water Reactor: A New Step Toward Sustainability

Ricardo Bastos Smith, Mahima Sachdeva, Indranil Bisuri, Roberto Vicente
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FUNDING AND FINANCE ISSUES RELATED TO THE DECOMMISSIONING OF BRAZILIAN NPPS

Daniel Artur Pinheiro Palma, Anna Leticia Barbosa de Souza, Amir Zacarias Mesquita
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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
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Crystallographic texture of hot rolled uranium-molybdenum alloys

Guilherme Fernandes Nielsen, Nathanael Wagner Sales Morais, Nelson Batista de Lima
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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
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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
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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
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Dynamic mode decomposition of numerical data in natural circulation

José Luiz Horacio Faccini
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NUCLEAR SECURITY IN THE BRAZILIAN REALITY

RODRIGO CARNEIRO CURZIO, JOAO CLAUDIO BATISTA FIEL, BRUNO DA SILVA MOURA, WALINTON EVANGELISTA DE SOUSA, LUAN JARDIM BONFIM
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Modeling dynamic scenarios for safety, reliability, availability, and maintainability analysis

Cesar Augusto Gabe, Luciano Ondir Freire, Delvonei Alves de Andrade
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New 3D Diffusion Code Based on The Nodal Polynomial Expansion

Jadna Mara Santos Mendes, Sérgio Barros Paixão, Sergio de Oliveira Vellozo
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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
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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
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Simulation for non-homogeneous transport equation by Nyström method

Luana Lazzari, Esequia Sauter, Fábio Souto De Azevedo
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The future of nuclear energy and maritime power relations

Claudio Rodrigues Corrêa, Taíssi Pepe de Medeiros, Gustavo André Guimarães
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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
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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
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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
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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
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RELAP5 Modeling of a Siphon Break Effect on the Brazilian Multipurpose Reactor

Humberto Vitor Soares, Antonio Belchior Jr., Roberto Longo Freitas
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Preliminary neutronic study of the S-PRISM fast reactor

João Manoel Losada Moreira
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Nuclear qualification of electrical equipment: challenges for the Brazilian industry

João Manoel Losada Moreira
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Periodic Inspection Program of Nuclear PWR reactor Pressure Vessel

Anne Aguiar Araujo
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Recommendation for linearization procedure in nuclear pressure vessel-nozzle intersections

Carolina Della Ricco Figueiredo, Miguel Mattar Neto
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