Características dosimétricas de fuentes isotópicas de neutrones

Using Monte Carlo methods, the neutron spectra produced by 252Cf, 252Cf/D2O, 241AmBe, 239PuBe, 140LaBe, 239Pu18O2 and 226RaBewere calculated. The mean energy and the dosimetric features for each source were determined. The calculated dose were H, H*(10),Hp;slab(10,0±), EAP y EISO. During calculation...

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Detalles Bibliográficos
Autores: G. A. Mercado Sánchez, E. Gallego Díaz, A. Lorente Fillol, H. R. Vega-Carrillo, V.M. Hernández Dávila, E. Manzanares Acuña
Tipo de recurso: artículo
Estado:Versión publicada
Fecha de publicación:2005
País:México
Institución:Universidad Autónoma de Zacatecas
Repositorio:Redalyc-UAZ
OAI Identifier:oai:redalyc.org:57064109
Acceso en línea:https://www.redalyc.org/articulo.oa?id=57064109
https://www.redalyc.org/journal/570/57064109/
https://www.redalyc.org/journal/570/57064109/html/
https://www.redalyc.org/journal/570/57064109/57064109.epub
https://www.redalyc.org/journal/570/57064109/movil
Access Level:acceso abierto
Palabra clave:Física, Astronomía y Matemáticas
dosimetry
Monte Carlo
Neutron sources
Descripción
Sumario:Using Monte Carlo methods, the neutron spectra produced by 252Cf, 252Cf/D2O, 241AmBe, 239PuBe, 140LaBe, 239Pu18O2 and 226RaBewere calculated. The mean energy and the dosimetric features for each source were determined. The calculated dose were H, H*(10),Hp;slab(10,0±), EAP y EISO. During calculations the sources were modeled as point-like and the dosimetric features were determined invacuum. For 239PuBe and 241AmBe neutron sources the Monte Carlo calculations were carried out using the actual dimensions and theirdosimetric characteristics were evaluated inside of an air-filled region. These results were compared with experimental data.