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 F. and Vega-Carrillo, Héctor René and Guzmán-García, Karen Arlete (2018). Analysis by Monte Carlo of Thermal Neutron Flux from a 241Am/9Be source for a system of trace analysis in materials. In: "XVIII INTERNATIONAL SYMPOSIUM ON SOLID STATE DOSIMETRY (ISSSD 2018)", September 24 to 28th, 2018, Oaxaca, México. pp. 70-85.

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 F.
  • Vega-Carrillo, Héctor René
  • Guzmán-García, Karen Arlete
Item Type: Presentation at Congress or Conference (Article)
Event Title: XVIII INTERNATIONAL SYMPOSIUM ON SOLID STATE DOSIMETRY (ISSSD 2018)
Event Dates: September 24 to 28th, 2018
Event Location: Oaxaca, México
Title of Book: XVIII INTERNATIONAL SYMPOSIUM ON SOLID STATE DOSIMETRY (ISSSD 2018). PROCEEDINGS
Date: 2018
Subjects:
Freetext Keywords: MCNP6; 241Am/9Be source; traces detection; NAA
Faculty: E.T.S.I. Industriales (UPM)
Department: Ingeniería Energética
Creative Commons Licenses: Recognition - No derivative works - Non commercial

Full text

[img] PDF - Users in campus UPM only - Requires a PDF viewer, such as GSview, Xpdf or Adobe Acrobat Reader
Download (1MB)

Abstract

Neutron techniques to characterize materials have a wide range of applications, although the major development has been in the identification of terrorist threats with chemical, biological, radiological, nuclear and explosive, (CBRNE) materials. The main advantage is the high penetration of neutrons in matter and therefore threats as explosives, drugs or landmines can be detected even when they are hidden under layers of earth, or elements of high density. Through Monte Carlo techniques employing the MCNP6 code, three different configurations with polyethylene cylinders were simulated to choose the most optimal geometry of this part of a detection device. The thermal neutron irradiation system is based in a 241Am/9Be source inside of polyethylene cylinders moderators with different sizes. The designed system provides an irradiation chamber allowing take advantage of the backscattering neutrons, multiplied by the source strength (6.64 s-1 measured on 1969, date UPM certificate), achieving thermal fluence rates until 530 cm-2 s -1 . Once the geometry and configuration of the system has been optimized through different simulations, the theoretical model was replicated in the neutronic hall of Energy Engineering Department of Universidad Politécnica de Madrid (EED-UPM), carried out several experimental measures using a neutron detector based in BF3. The main conclusion is a high agreement between MCNP results and experimental values measured at the UPM neutronics hall. Consequently, the optimized model could be employed in future laboratory experiments, both in the identification of substances and in the calibration of neutron dosimetry equipment. The final aim of this work has been to design the geometry of moderator and to select the neutron source position, to optimize the thermal neutrons flux in the area where the sample to analyze must be placed. This optimal configuration can be employed hereafter in detection of trace in substances or materials, through the NAA (Neutron Activation Analysis) method.

Funding Projects

TypeCodeAcronymLeaderTitle
Madrid Regional GovernmentIND2017/AMB7797UnspecifiedUnspecifiedContributions to Shielding and Dosimetry of Neutrons in CPTC

More information

Item ID: 55088
DC Identifier: http://oa.upm.es/55088/
OAI Identifier: oai:oa.upm.es:55088
Official URL: http://www.smid.org.mx/eng.htm
Deposited by: Memoria Investigacion
Deposited on: 24 May 2019 17:44
Last Modified: 27 May 2019 14:23
  • Logo InvestigaM (UPM)
  • Logo GEOUP4
  • Logo Open Access
  • Open Access
  • Logo Sherpa/Romeo
    Check whether the anglo-saxon journal in which you have published an article allows you to also publish it under open access.
  • Logo Dulcinea
    Check whether the spanish journal in which you have published an article allows you to also publish it under open access.
  • Logo de Recolecta
  • Logo del Observatorio I+D+i UPM
  • Logo de OpenCourseWare UPM