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Alfredo Lorente Fillol

22

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Monte Carlo design of a moderator to produce a thermal neutron source from a 241Am/9Be source

2019
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Optimization of thermal neutron flux from a 241Am/9Be source through Monte Carlo methods using MCNP6 code for explosives detection

2018
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Analysis by Monte Carlo of Thermal Neutron Flux from a 241Am/9Be source for a system of trace analysis in materials

2018
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Performance of B-10 + ZnS(Ag) neutron detectors in RPM for the detection of special nuclear materials

2017 Radiation Measurements
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A 222 Energy Bins Response Matrix fora 6LiI Scintillator BSS system

2016
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Neutron detectors of 10B+ZnS(Ag) as an alternative to 3He-based installed in the Radiation Portal Monitors in homeland Security

2016
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Detectores de Neutrones de 10B+ZnS(Ag) como alternativa a los detectores de 3He instalados en los Monitores de Radiación tipo Pórtico RPM`s. Neutron Detectors 10B+ZnS(Ag) as an alternative to 3He-based installed in the Radiation Portal Monitors, RPM's

2016
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Optimización de parámetros del detector N-15 de 10B+ZnS(Ag)

2015
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Cálculo de la respuesta del detector de neutrones 10B+ZnS(Ag) con el código MCNPX

2015
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Educating Nuclear Engineers by Nuclear Science and TEchnology Master at UPM

2014
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