Vol. 9 No. 2B (Suppl.) (2021)

DOI: https://doi.org/10.15392/bjrs.v9i2B

Published: 2021-07-25

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

A Method for the evaluation of knowledge management systems

Claudio Henrique dos Santos Grecco, Silas Cordeiro Augusto, Jaqueline Tavares Viana de Souza, Paulo Victor Rodrigues Carvalho, Adriana Loureiro Davila
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Experimental evaluation of natural convection in the IPR-R1 Triga research reactor at 264 kW and 105 kW

Amir Zacarias Mesquita
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Neutronic Evaluation of MSBR System Using MCNP Code

Clarysson Alberto Mello da Silva, Alana Lima Vieira, Isabella Resende Magalhães, Claubia Pereira
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Modified methodology for determining the temperature profiles of inverted u-tubes steam generators used in pwr power plants

Marcos Filardy Curi, José Luiz Zanon Zotin, Luiz Carlos Chaves
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Small break loss of coolant accident of 200 cm² in cold leg of primary loop of Angra2 nuclear power reactor evaluation

EDUARDO MADEIRA BORGES, GAIANÊ SABUNDJIAN
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One-step coupled calculations (Serpent-OpenFOAM) for a fuel rod of the IPR-R1 triga reactor

Tiago Augusto Santiago Vieira, Rebeca Cabral Gonçalves, Izabella Cristina de Paiva Machado, Guilherme Augusto Moura Vidal, Higor Fabiano Pereira Castro, Nataly Lamounier Ribeiro, Marcos Pais Barroso Filho, Wilker Gustavo Ferreira Santos, Daniel de Almeida Magalhães Campolina, Graiciany de Paula barros, Vitor Vasconcelos Araújo Silva, André Augusto Campagnole dos Santos
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Quality assurance program for Angra 1 licence renewal and long-term operation

YOUSSEF MORGHI, Amir Zacarias Mesquita, Ana Rosa BALIZA MAIA
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Thermal hydraulic analysis of a PWR loaded with annular fuel rods

Wallen Ferreira De Souza, Maria Auxiliadora Fortini Veloso, Antonella Lombardi Costa, Clubia Pereira
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DEVELOPED LIQUID FILMS FALLING AROUND TAYLOR BUBBLES INSIDE VERTICAL STAGNANT COLUMNS

Marcos Bertrand de Azevedo
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Thermal-hydraulics validation of CFD code for light water nuclear reactors against benchmark experimental results

Deiglys Borges Monteiro, Duvan Alejandro Castellanos Gonzalez, José Rubens Maiorino
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Scientific knowledge management about Monte Carlo method: a bibliometric analysis on IRD Postgraduate Program in Radiation Protection and Dosimetry

FELIPE DO CARMO AMORIM, PEDRO PACHECO DE QUEIROZ FILHO, Fernando Barcellos Razuck
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Simulation of transients in ads reactors in three-dimensional geometry

José Rafael Nicolao Carneiro, Zelmo Rodrigues de Lima, Alessandro da Cruz Gonçalves
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Computational simulation of a single Taylor bubble rising in a vertical column with stagnant liquid

Francisco Rogerio Teixeira Nascimento
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Entering new markets: nuclear industry challenges

Luciano Ondir Freire, Delvonei Alves de Andrade
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Potential advantages of molten salt reactor for merchant ship propulsion

Luiz Gonzaga de Freitas Neto, Luciano Ondir Freire, Adimir dos Santos, Delvonei Alves de Andrade
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Effect of compaction pressure on the thermal conductivity of UO2-BeO-Gd2O3 pellets

Denise das Mercês Camarano, Ana Maria Matildes Dos Santos, Fábio Abud Mansur
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Knowledge base about risk and safety of nuclear facilities to support analysts and decision-makers

Antonio Souza Vieira Neto, Amaury Muñoz Oliva, Patrícia da Silva Pagetti de Oliveira, Marcos Costa Hunold, Maria Eugênia Lago Jacques Sauer, Vinicius Andrea
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Core parametric study for enhancing the radioisotope production in the IEA-R1 research reactor

Giovanni Laranjo Stefani, Frederico Antônio Genezini, Thiago Augusto Santos, João Manoel de Losada Moreira
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Reliability and redundancy allocation analysis applied to a nuclear protection system

Alexander Lucas Busse, João Manoel Losada Moreira
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Overview of the seismic probabilistic safety assessment applied to a nuclear installation located in a low seismicity zone

Ellison Amaro de Oliveira, Patricia da Silva Pagetti de Oliveira, Miguel Mattar Neto, Marcos Coelho Maturana
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