Analysis by Monte Carlo of thermal neutron flux from a 241Am/9Be source for a system of trace analysis in materials

Cevallos Robalino, Lenin Estuardo and García Fernández, Gonzalo and Lorente Fillol, Alfredo and Gallego Díaz, Eduardo Florentino and Vega Carrillo, Héctor René and Guzmán García, Karen Arlet (2019). Analysis by Monte Carlo of thermal neutron flux from a 241Am/9Be source for a system of trace analysis in materials. "Applied Radiation and Isotopes", v. 151 ; pp. 19-24. ISSN 1872-9800. https://doi.org/10.1016/j.apradiso.2019.04.041.

Description

Title: Analysis by Monte Carlo of thermal neutron flux from a 241Am/9Be source for a system of trace analysis in materials
Author/s:
  • Cevallos Robalino, Lenin Estuardo
  • García Fernández, Gonzalo
  • Lorente Fillol, Alfredo
  • Gallego Díaz, Eduardo Florentino
  • Vega Carrillo, Héctor René
  • Guzmán García, Karen Arlet
Item Type: Article
Título de Revista/Publicación: Applied Radiation and Isotopes
Date: May 2019
ISSN: 1872-9800
Volume: 151
Subjects:
Freetext Keywords: (241)Am/(9)Be neutron source; MCNP6; NAA; Trace detection
Faculty: E.T.S.I. Industriales (UPM)
Department: Ingeniería Energética
Creative Commons Licenses: Recognition - No derivative works - Non commercial

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Abstract

Neutron techniques to characterize materials have a wide range of applications, one of the major developments being the identification of terrorist threats with chemical, biological, radiological, nuclear and explosives (CBRNE) materials. In this work, a thermal neutron irradiation system, using a241Am/9Be source of 111 GBq inside polyethylene cylindrical moderators, has been designed, built and tested. The geometry of moderator and the neutron source position were fixed trying to maximize the thermal neutrons flux emitted from the system. Therefore, the system is in fact a thermalized neutron source taking advantage of the backscattered neutrons, achieving thermal fluence rates of up to 5.3x102 cm-2 s-1, with dominantly thermal spectra. Samples can be placed there for several hours and thereafter be measured to identify their component elements by NAA (Neutron Activation Analysis). Through Monte Carlo techniques employing the MCNP6 code (Pelowitz et al., 2014), four different configurations with polyethylene cylinders were simulated to choose the most adequate geometry. The theoretical model was then replicated in the neutronics hall of the Neutron Measurements Laboratory of the Energy Engineering Department of Universidad Politécnica de Madrid (LMN-UPM), carrying out experimental measurements using a BF3 neutron detector. A high agreement between MCNP6 results and the experimental values measured was observed. Consequently, the system developed could be employed in future laboratory experiments, both for the identification of trace substances by NAA and for the calibration of neutron detection equipment.

Funding Projects

TypeCodeAcronymLeaderTitle
Madrid Regional GovernmentIND2017/AMB-7797UnspecifiedUnspecifiedAportaciones al blindaje y la dosimetría de neutrones en instalaciones de hadronterapia con protones

More information

Item ID: 67852
DC Identifier: https://oa.upm.es/67852/
OAI Identifier: oai:oa.upm.es:67852
DOI: 10.1016/j.apradiso.2019.04.041
Official URL: https://www.sciencedirect.com/science/article/pii/S0969804318311680?via%3Dihub
Deposited by: Memoria Investigacion
Deposited on: 22 Jul 2021 14:28
Last Modified: 22 Jul 2021 14:28
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