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Article(2)
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Applied Radiation and Isotopes(2)
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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:googlescopusNeutron dosimetry and shielding verification in commissioning of Compact Proton Therapy Centers (CPTC) using MCNP6.2 Monte Carlo code
ArticleAbstract: Proton therapy (PT) is an external radiotherapy using proton beams with energies between 70 and 230Palabras claves:Ambient dose equivalent, Compact proton therapy centers, MCNP6.2, Operational radiation protection, Shielding commissioningAutores:Gallego E., Garcia-Baonza R., García-Fernandez G.F., Gomez-Ros J.M., Guzmán-García K.A., Lenin E. Cevallos Robalino, Vega-Carrillo H.R.Fuentes:googlescopus