Memorias de investigación
Artículos en revistas:
Design by Monte Carlo method of a thermal neutron device using a 241Am/9Be source and high-density polyethylene moderator
Año:2019
Áreas de investigación
  • Mecanismos de interaccion,
  • Dosimetria,
  • Fuentes de radiacion y detectores
Datos
Descripción
A thermal neutron system intended to be used in neutron activation analysis has been designed by Monte Carlo methods. The device is based on a241Am/9Be neutron source of 111 GBq, placed inside a cylindrical cavity open inside a parallelepiped of moderator material. Three different moderator materials, water, graphite and highdensity polyethylene (HDPE), were simulated to check what is the most suitable for the detection system, concluding that HDPE reach the better performance. The device achieves an increased thermal neutron flux by taking advantage of neutron moderation in the polyethylene and the neutron scattering in the irradiation chamber walls. The thermal fluence rates obtained were 904 cm?2 s?1, i.e. 8.144 cm?2 s?1 GBq?1, with a fraction of thermal neutrons at the best point of 83% of pristine fast neutrons emitted by the source. The device has been designed by Monte Carlo techniques using the MCNP6 code, and the main tasks developed were to select the moderator material and to maximize the thermal neutrons flux in the irradiation chamber
Internacional
Si
JCR del ISI
Si
Título de la revista
Applied Radiation And Isotopes
ISSN
0969-8043
Factor de impacto JCR
1,27
Información de impacto
Volumen
DOI
10.1016/j.apradiso.2019.05.040
Número de revista
151
Desde la página
150
Hasta la página
156
Mes
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Participantes
Grupos de investigación, Departamentos, Centros e Institutos de I+D+i relacionados
  • Creador: Departamento: Ingeniería Energética
  • Departamento: Construcción y Tecnología Arquitectónicas