Monte Carlo calculation of the Response Matrix of a Bonner spheres spectrometer

Vega-Carrillo, Héctor René; Gallego Díaz, Eduardo F.; Manzanares-Acuña, Eduardo y Lorente Fillol, Alfredo (2008). Monte Carlo calculation of the Response Matrix of a Bonner spheres spectrometer. En: "12th International Congress of the International Radiation Protection Association, IRPA-12", 19/10/2008-24/10/2008, Buenos Aires, Argentina.

Descripción

Título: Monte Carlo calculation of the Response Matrix of a Bonner spheres spectrometer
Autor/es:
  • Vega-Carrillo, Héctor René
  • Gallego Díaz, Eduardo F.
  • Manzanares-Acuña, Eduardo
  • Lorente Fillol, Alfredo
Tipo de Documento: Ponencia en Congreso o Jornada (Artículo)
Título del Evento: 12th International Congress of the International Radiation Protection Association, IRPA-12
Fechas del Evento: 19/10/2008-24/10/2008
Lugar del Evento: Buenos Aires, Argentina
Título del Libro: Proceedings of the 12th International Congress of the International Radiation Protection Association, IRPA-12
Fecha: 2008
Materias:
Palabras Clave Informales: Monte Carlo, Bonner spheres spectrometer, Matrix response, neutrons
Escuela: E.T.S.I. Industriales (UPM)
Departamento: Ingeniería Nuclear [hasta 2014]
Licencias Creative Commons: Reconocimiento - Sin obra derivada - No comercial

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Resumen

The Bonner spheres spectrometer is utilized to estimate the neutron spectrum of neutrons from thermal up to several MeV neutrons. Its response is increased to few GeV neutrons by introducing large Z materials as inner shells. To use the spectrometer a matrix response and an unfolding method are required; these are crucial to assure the quality of spectrometer output. The response matrix of a Bonner sphere spectrometer was calculated by use of the MCNP code. As thermal neutron counter the spectrometer has a 0.4 Ø × 0.4 cm26LiI(Eu) scintilla or which is located at the centre of a set of polyethylene spheres. The response functions were calculated for 0, 2, 3, 5, 8, 10, and 12 inches-diameter polyethylene spheres for neutrons whose energy goes from 10-8 to 100 MeV. For energies from 10-8 to 20 MeV the MCNP4C code was utilized while for neutrons from 20 to 100 MeV calculations were carried out with MCNPX code. The response functions were compared with those reported in the literature.

Más información

ID de Registro: 4595
Identificador DC: http://oa.upm.es/4595/
Identificador OAI: oai:oa.upm.es:4595
URL Oficial: http://www.irpa12.org.ar/index.php
Depositado por: Memoria Investigacion
Depositado el: 13 Oct 2010 11:15
Ultima Modificación: 20 Abr 2016 13:44
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