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Design 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