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Article(3)
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Applied Radiation and Isotopes(3)
Analysis 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 characterization and benchmarking of extended range REM meters for its application in shielding and radiation area monitoring in Compact Proton Therapy Centers (CPTC)
ArticleAbstract: Compact Proton Therapy Centers, CPTC, have a single treatment room, and are technologically more affPalabras claves:Ambient dose equivalent, Compact proton therapy centers, LUPIN-II, MCNP6, Proton therapy, WENDI-IIAutores:Gallego E., Garcia-Baonza R., García-Fernandez G.F., Guzmán-García K.A., Ibañez S., Lenin E. Cevallos Robalino, Lorente A., Vega-Carrillo H.R.Fuentes:googlescopus