Design by Monte Carlo method of a thermal neutron device using a 241Am/9Be source and high-density polyethylene moderator

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). Design by Monte Carlo method of a thermal neutron device using a 241Am/9Be source and high-density polyethylene moderator. "Applied Radiation and Isotopes", v. 151 ; pp. 150-156. ISSN 1872-9800. https://doi.org/10.1016/j.apradiso.2019.05.040.

Description

Title: Design by Monte Carlo method of a thermal neutron device using a 241Am/9Be source and high-density polyethylene moderator
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: MCNP6 code; 241Am /9Be source; Dosimetry equipment
Faculty: E.T.S.I. Industriales (UPM)
Department: Ingeniería Energética
Creative Commons Licenses: Recognition - No derivative works - Non commercial

Full text

[img]
Preview
PDF - Requires a PDF viewer, such as GSview, Xpdf or Adobe Acrobat Reader
Download (759kB) | Preview

Abstract

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 high-density 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.

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: 67855
DC Identifier: https://oa.upm.es/67855/
OAI Identifier: oai:oa.upm.es:67855
DOI: 10.1016/j.apradiso.2019.05.040
Official URL: https://www.sciencedirect.com/science/article/pii/S0969804318311655?via%3Dihub
Deposited by: Memoria Investigacion
Deposited on: 22 Jul 2021 14:42
Last Modified: 22 Jul 2021 14:42
  • 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