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Descripción
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| A thermal neutron device based on an 241Am/9Be source has been designed by Monte Carlo method. It is named TNMI (Thermal Neutron device for Material Identification) aiming to be used for Thermal Neutron Activation Analysis The TNMI has an 241Am/9Be neutron source of 111 GBq in a cylindrical cavity inside a high-density polyethylene (HDPE) parallelepiped, The device increases the thermal neutron flux by taking advantage of neutron moderation and termalization in the polyethylene, and the neutron scattering in the irradiation chamber walls, allowing to obtain thermal fluence rates of up to 904 cm-2.s-1, i.e. 13.5 cm-2 s-1 GBq-1, the fraction of thermal neutrons is 83% at (0, 40, 0) cm. The device has been designed through MCNP6 code searching for an optimized geometry in both the amount of HDPE and the thermal neutrons flux in the irradiation chamber. | |
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Internacional
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Si |
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Nombre congreso
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XVIII INTERNATIONAL SYMPOSIUM ON SOLID STATE DOSIMETRY (ISSSD 2018) |
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Tipo de participación
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970 |
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Lugar del congreso
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Oaxaca, México |
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Revisores
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ISBN o ISSN
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CDP08UPM |
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DOI
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Fecha inicio congreso
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24/09/2018 |
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Fecha fin congreso
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28/09/2018 |
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Desde la página
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103 |
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Hasta la página
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119 |
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Título de las actas
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XVIII INTERNATIONAL SYMPOSIUM ON SOLID STATE DOSIMETRY (ISSSD 2018). Proceedings (vol. 1) http://smid.org.mx/eng.htm |