Vol. 9 Núm. 2A (Suppl.) (2021)

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

• A fuzzy method for the usability evaluation of nuclear medical equipment

  Cláudio Henrique dos Santos Grecco, Isaac José Antonio Luquetti dos Santos, Marcos Santana Farias, Larissa Pereira de Farias, Alfredo Marques Vianna Filho

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• Study of radioactive particle tracking using MCNP-X code and artificial neural network

  Roos Sophia de Freitas Dam, César Marques Salgado

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• Modification of fuel performance code to evaluate iron-based alloy behavior under LOCA scenario

  Claudia Giovedi, Alfredo Abe, Rafael O. R. Muniz, Daniel S. Gomes, Antonio T. Silva, Marcelo R. Martins

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• Simulation of the burnup in cell calculation using the wimsd-5b code considering different nuclear data libraries

  Desirée Yael de Sena Tavares, Adilson Costa da Silva, Zelmo Rodrigues de Lima

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• Study of gas pipelines cracks using transmission and Compton scattering

  Marcela Ferreira Freitas, Cesar Marques Salgado

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• Quantification of effluents in the production of nuclear fuel

  Mayara Costa de Castro Becca Sakai, Humberto G Riella, Elita Fontenele Urano de Carvalho

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• The Importance of Probabilistic Safety Assessment in the Careful Study of Risks Envolved to New Nuclear Power Plant Projects

  Jônatas Franco Campos da Mata, Amir Zacarias Mesquita

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• Computational Fluid Dynamics Applied to Study Coolant Loss Regimes in Very High Temperature Reactors

  Uebert Gonçalves Moreira, Dany Sanchez Dominguez, Leorlen Yunier Rojas Mazaira, Carlos Alberto Brayner de Oliveira Lira, Carlos Rafael García Henández

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• Human factors engineering and participatory design in the project of a nuclear research reactor control centre

  Larissa Pereira Farias, Isaac Antônio Luquetti dos Santos, Paulo Victor Rodrigues de Carvalho, Beany Guimaraes Monteiro

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• Solution for the Multigroup Neutron Space Kinetics Equations by Source Iterative Method

  Matheus Gularte Tavares, Claudio Zen Petersen, Marcelo Schramm, Rodrigo Zanette

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