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Estimation with Monte Carlo of thermal neutrons in the FANT, using <sup>252</sup>Cf and <sup>241</sup>Am/<sup>9</sup>Be neutron source
ArticleAbstract: The thermal neutron irradiation device (FANT), developed at the Neutron Measurements Laboratory of tPalabras claves:Am95241/Be49, Cf98252, FANT, Monte Carlo, Neutron spectraAutores:Bremnen Veliz Orcid, Gallego E., Garcia-Baonza R., García-Fernandez G.F., Lenin E. Cevallos Robalino, Orlando Giovanni Barcia Ayala, Vega-Carrillo H.R.Fuentes:googlescopusAnalysis by Monte Carlo of thermal neutron flux from a <sup>241</sup>Am/<sup>9</sup>Be source for a system of trace analysis in materials
ArticleAbstract: Neutron techniques to characterize materials have a wide range of applications, one of the major devPalabras claves:241 9 Am/ Be neutron source, MCNP6, NAA, Trace detectionAutores:Gallego E., García-Fernandez G.F., Guzmán-García K.A., Lenin E. Cevallos Robalino, Lorente A., Vega-Carrillo H.R.Fuentes:googlescopusDesign by Monte Carlo method of a thermal neutron device using a <sup>241</sup>Am/<sup>9</sup>Be source and high-density polyethylene moderator
ArticleAbstract: A thermal neutron system intended to be used in neutron activation analysis has been designed by MonPalabras claves:241 9 Am / Be source, Dosimetry equipment, MCNP6 codeAutores:Gallego E., García-Fernandez G.F., Guzmán-García K.A., Lenin E. Cevallos Robalino, Lorente A., Vega-Carrillo H.R.Fuentes:googlescopusMonte Carlo design and experimental characterization of a moderator device to produce a thermal neutron source from a <sup>241</sup>Am/<sup>9</sup>Be source
ArticleAbstract: A moderator device to produce a uniform thermal neutron field has been designed by Monte Carlo methoPalabras claves:241 9 Am / Be neutron source, Gold activation foils, MCNP6 code, Neutron moderator, Thermal neutronsAutores:Gallego E., García-Fernandez G.F., Guzmán-García K.A., Ibañez-Fernández S., Lenin E. Cevallos Robalino, Lorente A., Vega-Carrillo H.R.Fuentes:googlescopus