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

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

Description

Title: Monte Carlo calculation of the Response Matrix of a Bonner spheres spectrometer
Author/s:
  • Vega-Carrillo, Héctor René
  • Gallego Díaz, Eduardo F.
  • Manzanares-Acuña, Eduardo
  • Lorente Fillol, Alfredo
Item Type: Presentation at Congress or Conference (Article)
Event Title: 12th International Congress of the International Radiation Protection Association, IRPA-12
Event Dates: 19/10/2008-24/10/2008
Event Location: Buenos Aires, Argentina
Title of Book: Proceedings of the 12th International Congress of the International Radiation Protection Association, IRPA-12
Date: 2008
Subjects:
Freetext Keywords: Monte Carlo, Bonner spheres spectrometer, Matrix response, neutrons
Faculty: E.T.S.I. Industriales (UPM)
Department: Ingeniería Nuclear [hasta 2014]
Creative Commons Licenses: Recognition - No derivative works - Non commercial

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Abstract

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.

More information

Item ID: 4595
DC Identifier: http://oa.upm.es/4595/
OAI Identifier: oai:oa.upm.es:4595
Official URL: http://www.irpa12.org.ar/index.php
Deposited by: Memoria Investigacion
Deposited on: 13 Oct 2010 11:15
Last Modified: 20 Apr 2016 13:44
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