Vol. 8 No. 3B (Suppl.) (2020): XX ENFIR / 2019 - Vol B (Suppl.)

XX Meeting on Nuclear Reactor Physic and Thermal Hydraulic (XX ENFIR) - Vol B (Suppl.)

DOI: https://doi.org/10.15392/bjrs.v8i3B

Published: 2020-12-28

Articles

Comparação entre métodos de medição da camada semi-redutora em radiologia

Denyel Jefferson Prado Faria, Rafael Figueiredo Pohlmann Simões, Fernando Mecca Augusto, Leonardo Vieira Travassos, Beneth Costa Gomes
- PDF (Portuguese (Brazil))

XX Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XX ENFIR)

Probabilistic Safety Analysis and Risk-Based Inspection of nuclear research reactors: state-of-the-art and implementation proposal

Raíssa Oliveira Marques, Vanderley Vasconcelos, Wellington Antonio Soares, Silvério Ferreira Silva Júnior, Amanda Laureano Raso, Amir Zacarias Mesquita
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Performance of an extrapolation chamber in computed tomography standard beams

Maysa Costa Castro, Natállia Fiorini Silva, Linda Viola Ehlin Caldas
- PDF
A Continuous Energy Neutron Transport Monte Carlo Simulator Project: Decomposition of the Neutron Energy Spectrum by Target Nuclei Tagging

Luiz Felipe Fracasso Chaves Barcellos, Bardo Ernst Josef Bodmann, Sergio de Queiroz Bogado leite, Marco Túlio Menna Barreto de Vilhena
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Calculation of scale thickness in oil pipelines using transmission gamma

Tâmara Porfíro Teixeira, César Marques Salgado
- PDF
Assessing the management system to demonstrate the safe of transport of radioactive material

Natanael de Carvalho Bruno, Patricia Morais Mattar, André Teixeira Pontes
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Thermoluminescent properties of LaAlO3:C crystals synthesized by solid state reaction applied to UV Dosimetry

neriene alves, Wilmar Barbosa Ferraz, Luiz Oliveira Faria
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Occupational monitoring at radioactive waste deposit

Wagner de Souza Pereira, Alphonse G. A. C. Kelecom, Ademir Xavier da Silva, Franklin de Souza Cunha, Rosemary Lopes Faria, Leonardo Rabelo de Matos Silva, Fernando Pinheiro Saldanha, Adriana de Fonseca, Alexandre Kuster de Souza Paiva, Maxime Charles_Pierre
- PDF
Numerical Simulation Study on the Air/Water Counter- current Flow Limitation in Nuclear Reactors

youssef morghi, Amir Zacarias Mesquita
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Two-dimensional transient thermal analysis of a fuel rod by finite volume method

Rhayanne Yalle Negreiros Costa, Mário Augusto Bezerra da Silva, Carlos Alberto Brayner de Oliveira Lira
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Spectral Nodal Methodology for Multigroup Slab-Geometry Discrete Ordinates Neutron Transport Problems with Linearly Anisotropic Scattering

Amaury Muñoz Oliva, Hermes Alves Filho, Davi José Martins e Silva, Carlos Rafael García Hernández
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Solution of the Multigroup Neutron Diffusion Eigenvalue Problem in Slab Geometry by Modified Power Method

Rodrigo Zanette, Claudio Zen Petersen, Matheus Gularte Tavares
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Monitoring System for an Experimental Facility Using GMDH Methodology

Iraci Martinez Pereira, Davi Almeida Moraes
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CFD Analysis of the VHTR Prismatic Core with Variation of Geometry Parameters

Carlos Alberto Brayner Oliveira Lira, Pedro Paulo Dantas Souza Paiva
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CHF prediction in rod bundles using round tube data

Maria Auxiliadora Fortini Veloso, Wallen Ferreira De Souza
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Break location influence in pressure vessel SBLOCA scenarios

María Lorduy, Andrea Querol, Sergio Gallardo, Gumersindo Verdú
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Development of a PID-Fuzzy controller in the water level control of a pressurizer of a nuclear reactor

Thiago Souza Pereira de Brito, Carlos Alberto Brayner de Oliveira Lira, Wagner Eustáquio de Vasconcelos
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Curvilinear Coordinate System Used To Solve Tritium Dispersion In Complex Orographies.

André Meneghetti, Bardo Ernst Josef Bodmann, Marco Tullio Menna De Vilhena
- PDF