NDLI: Neutron Shielding for a 252 Cf Source

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Neutron Shielding for a 252 Cf Source

Content Provider	Semantic Scholar
Author	Vega-Carrillo, Héctor René Manzanares-Acuña, Eduardo Hernández-Dávila, Víctor Martín Ciprés, Carolina Gallego, Eduardo Lorente, Adrián Abascal, José Gutiérrez De
Copyright Year	2006
Abstract	To determine the neutron shielding features of water-extended polyester a Monte Carlo study was carried out. Materials with low atomic number are predominantly used for neutron shielding because these materials effectively attenuate neutrons, mainly through inelastic collisions and absorption reactions. During the selection of materials to design a neutron shield, prompt gamma production as well as radionuclide production induced by neutron activation must be considered. In this investigation the Monte Carlo method was used to evaluate the performance of a water-extended polyester shield designed for the transportation, storage, and use of a 252 Cf isotopic neutron source. During calculations a detailed model for the 252 Cf and the shield was utilized. To compare the shielding features of water extended polyester, the calculations were also made for the bare 252 Cf in vacuum, air and the shield filled with water. For all cases the calculated neutron spectra was utilized to determine the ambient equivalent neutron dose at four sites around the shielding. In the case of water extended polyester and water shielding the calculations were extended to include the prompt gamma rays produced during neutron interactions, with this information the Kerma in air was calculated at the same locations where the ambient equivalent neutron dose was determined.
File Format	PDF HTM / HTML
Alternate Webpage(s)	http://www.iaea.org/inis/collection/nclcollectionstore/_public/38/048/38048838.pdf
Language	English
Access Restriction	Open
Content Type	Text
Resource Type	Article

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