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Bernal García, Álvaro
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Bernal García, Álvaro
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Bernal García, Álvaro
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1
Development of a 3D Modal Neutron Code with the Finite Volume Method for the Diffusion and Discrete Ordinates Transport Equations. Application to Nuclear Safety Analyses
by
Bernal
García
,
Álvaro
Published 2018
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Doctoral Thesis
2
Contributions to solve the Multi-group Neutron Transport equation with different Angular Approaches
by
Morato Rafet, Sergio
Published 2021
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Doctoral Thesis
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