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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 Arlete, Gallego Díaz, Eduardo F. 
ORCID: https://orcid.org/0000-0001-8338-4959 and Lorente Fillol, Alfredo ORCID: https://orcid.org/0000-0002-8243-3007
(2018).
Optimization of thermal neutron flux from a 241Am/9Be source through Monte Carlo methods using MCNP6 code for explosives detection.
In: "IRPACUBA 2018. XI Congreso de Seguridad Radiológica y Nuclear. Congreso IRPA Latinoamericano", 16 -20 de abril de 2018, La Habana, Cuba. p. 1.
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: | IRPACUBA 2018. XI Congreso de Seguridad Radiológica y Nuclear. Congreso IRPA Latinoamericano |
| Event Dates: | 16 -20 de abril de 2018 |
| Event Location: | La Habana, Cuba |
| Title of Book: | Memorias. IRPACUBA 2018. XI Congreso de Seguridad Radiológica y Nuclear. Congreso IRPA Latinoamericano |
| Date: | 2018 |
| Subjects: | |
| Faculty: | E.T.S.I. Industriales (UPM) |
| Department: | Ingeniería Energética |
| Creative Commons Licenses: | Recognition - No derivative works - Non commercial |
Abstract
A thermal neutron irradiation system has been designed, based on an 241Am/9Be source with cylindrical polyethylene moderators. The system has an irradiation cavity, allowing to take advantage of backscattered neutrons; with a source having a nominal emission rate of 6.4x106 ·s -1 , thermal fluence rates up to 530 cm-2 ·s-1 are obtained. Using Monte Carlo techniques (MCNP6 code) three different configurations were simulated using polyethylene cylinders. Once the geometric configuration of the system has been optimized, the model has been replicated experimentally in the neutron measurements hall of the Energy Engineering Department of Universidad Politécnica de Madrid (UPM), performing several measurements. 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: | 55107 |
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| DC Identifier: | https://oa.upm.es/55107/ |
| OAI Identifier: | oai:oa.upm.es:55107 |
| Official URL: | http://www.irpacuba.com/ |
| Deposited by: | Memoria Investigacion |
| Deposited on: | 27 May 2019 14:51 |
| Last Modified: | 27 May 2019 14:51 |
