Estimation with Monte Carlo of thermal neutrons in the FANT, using 252Cf and 241Am/9Be neutron source

Lenin E. Cevallos-Robalino; Gonzalo García-Fernández; Eduardo Gallego; Hector Rene Vega-Carrillo; Roberto García-Baonza; Orlando Barcia-Ayala; Bremnen Veliz

doi:10.1016/j.apradiso.2023.110694

Estimation with Monte Carlo of thermal neutrons in the FANT, using ²⁵²Cf and ²⁴¹Am/⁹Be neutron source

Lenin E. Cevallos-Robalino, Gonzalo García-Fernández, Eduardo Gallego, Hector Rene Vega-Carrillo, Roberto García-Baonza, Orlando Barcia-Ayala, Bremnen Veliz

Research output: Contribution to journal › Article › peer-review

2 Scopus citations

Abstract

The thermal neutron irradiation device (FANT), developed at the Neutron Measurements Laboratory of the Energy Engineering Department at Universidad Politécnica de Madrid, is a high-density polyethylene regular parallelepiped, with a rather uniform neutron fluence inside its irradiation chamber. It uses a Am95241/Be49 neutron source aiming to provide thermal neutron fluence rates. Neutron spectra and neutron fluences were estimated with Monte Carlo methods in the FANT irradiation chamber when a Cf98252 neutron source is used and were compared with the results obtained with the Am95241/Be49 source. Regardless of the neutron source, the largest contribution is due to thermal neutrons, producing also epithermal and fast neutrons. Per neutron emitted by the source, the use of Cf98252 produces a larger amount of neutrons.

Original language	English
Article number	110694
Journal	Applied Radiation and Isotopes
Volume	194
DOIs	https://doi.org/10.1016/j.apradiso.2023.110694
State	Published - Apr 2023

Bibliographical note

Funding Information:
The first author Lenin E. Cevallos-Robalino, thanks to the Universidad Politécnica Salesiana (UPS), for the support received, and to Grupo de Investigación en Micro-Nanotecnología y Energía Nuclear (NANOTECH).

Publisher Copyright:
© 2023 Elsevier Ltd

Keywords

Am95241/Be49
Cf98252
FANT
Monte Carlo
Neutron spectra

Access to Document

10.1016/j.apradiso.2023.110694

Cite this

@article{a69d9e68e6a84fa1953d86ead14fe099,

title = "Estimation with Monte Carlo of thermal neutrons in the FANT, using 252Cf and 241Am/9Be neutron source",

abstract = "The thermal neutron irradiation device (FANT), developed at the Neutron Measurements Laboratory of the Energy Engineering Department at Universidad Polit{\'e}cnica de Madrid, is a high-density polyethylene regular parallelepiped, with a rather uniform neutron fluence inside its irradiation chamber. It uses a Am95241/Be49 neutron source aiming to provide thermal neutron fluence rates. Neutron spectra and neutron fluences were estimated with Monte Carlo methods in the FANT irradiation chamber when a Cf98252 neutron source is used and were compared with the results obtained with the Am95241/Be49 source. Regardless of the neutron source, the largest contribution is due to thermal neutrons, producing also epithermal and fast neutrons. Per neutron emitted by the source, the use of Cf98252 produces a larger amount of neutrons.",

keywords = "Am95241/Be49, Cf98252, FANT, Monte Carlo, Neutron spectra",

author = "Cevallos-Robalino, {Lenin E.} and Gonzalo Garc{\'i}a-Fern{\'a}ndez and Eduardo Gallego and Vega-Carrillo, {Hector Rene} and Roberto Garc{\'i}a-Baonza and Orlando Barcia-Ayala and Bremnen Veliz",

note = "Publisher Copyright: {\textcopyright} 2023 Elsevier Ltd",

year = "2023",

month = apr,

doi = "10.1016/j.apradiso.2023.110694",

language = "English",

volume = "194",

journal = "Applied Radiation and Isotopes",

issn = "0969-8043",

publisher = "Elsevier Ltd",

}

TY - JOUR

T1 - Estimation with Monte Carlo of thermal neutrons in the FANT, using 252Cf and 241Am/9Be neutron source

AU - Cevallos-Robalino, Lenin E.

AU - García-Fernández, Gonzalo

AU - Gallego, Eduardo

AU - Vega-Carrillo, Hector Rene

AU - García-Baonza, Roberto

AU - Barcia-Ayala, Orlando

AU - Veliz, Bremnen

PY - 2023/4

Y1 - 2023/4

N2 - The thermal neutron irradiation device (FANT), developed at the Neutron Measurements Laboratory of the Energy Engineering Department at Universidad Politécnica de Madrid, is a high-density polyethylene regular parallelepiped, with a rather uniform neutron fluence inside its irradiation chamber. It uses a Am95241/Be49 neutron source aiming to provide thermal neutron fluence rates. Neutron spectra and neutron fluences were estimated with Monte Carlo methods in the FANT irradiation chamber when a Cf98252 neutron source is used and were compared with the results obtained with the Am95241/Be49 source. Regardless of the neutron source, the largest contribution is due to thermal neutrons, producing also epithermal and fast neutrons. Per neutron emitted by the source, the use of Cf98252 produces a larger amount of neutrons.

AB - The thermal neutron irradiation device (FANT), developed at the Neutron Measurements Laboratory of the Energy Engineering Department at Universidad Politécnica de Madrid, is a high-density polyethylene regular parallelepiped, with a rather uniform neutron fluence inside its irradiation chamber. It uses a Am95241/Be49 neutron source aiming to provide thermal neutron fluence rates. Neutron spectra and neutron fluences were estimated with Monte Carlo methods in the FANT irradiation chamber when a Cf98252 neutron source is used and were compared with the results obtained with the Am95241/Be49 source. Regardless of the neutron source, the largest contribution is due to thermal neutrons, producing also epithermal and fast neutrons. Per neutron emitted by the source, the use of Cf98252 produces a larger amount of neutrons.

KW - Am95241/Be49

KW - Cf98252

KW - FANT

KW - Monte Carlo

KW - Neutron spectra

UR - http://www.scopus.com/inward/record.url?scp=85147119640&partnerID=8YFLogxK

U2 - 10.1016/j.apradiso.2023.110694

DO - 10.1016/j.apradiso.2023.110694

M3 - Article

AN - SCOPUS:85147119640

SN - 0969-8043

VL - 194

JO - Applied Radiation and Isotopes

JF - Applied Radiation and Isotopes

M1 - 110694

ER -