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Optimization of thermal neutron flux from a 241Am/9Be source through Monte Carlo methods using MCNP6 code for explosives detection
Citation
Cevallos Robalino, Lenin Estuardo, García Fernández, Gonzalo, Guzmán García, Karen Arlet, Gallego Díaz, Eduardo Florentino 
ORCID: https://orcid.org/0000-0001-8338-4959 and Lorente Fillol, Alfredo ORCID: https://orcid.org/0000-0002-8243-3007
(2019).
Optimization of thermal neutron flux from a 241Am/9Be source through Monte Carlo methods using MCNP6 code for explosives detection.
In: "IRPA 2018. 5th European IRPA Congress.", 4-9 June 2018, The Hague, The Netherlands. p. 31.
Description
| Title: | Optimization of thermal neutron flux from a 241Am/9Be source through Monte Carlo methods using MCNP6 code for explosives detection |
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| Author/s: |
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| Item Type: | Presentation at Congress or Conference (Poster) |
| Event Title: | IRPA 2018. 5th European IRPA Congress. |
| Event Dates: | 4-9 June 2018 |
| Event Location: | The Hague, The Netherlands |
| Title of Book: | IRPA 2018. Posters |
| Date: | February 2019 |
| Subjects: | |
| Faculty: | E.T.S.I. Industriales (UPM) |
| Department: | Ingeniería Energética |
| Creative Commons Licenses: | Recognition - No derivative works - Non commercial |
Abstract
The aim of this work has been the design of the system and its geometry, maximizing the thermal neutron flux for the intended purpose of using it for explosives detection applying the PGNAA (Prompt Gamma Neutron Activation Analysis) method.
More information
| Item ID: | 65942 |
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| DC Identifier: | https://oa.upm.es/65942/ |
| OAI Identifier: | oai:oa.upm.es:65942 |
| Official URL: | https://irpa2018europe.com/ |
| Deposited by: | Memoria Investigacion |
| Deposited on: | 18 Feb 2021 15:03 |
| Last Modified: | 18 Feb 2021 15:03 |
