title: Graphite moderated (252)Cf source.
abstract: The Thorium molten-salt reactor is an attractive and affordable nuclear power option for developing countries with insufficient infrastructure and limited technological capability. In the aim of personnel training and experience gathering at the Universidad Simon Bolivar there is in progress a project of developing a subcritical thorium liquid-fuel reactor. The neutron source to run this subcritical reactor is a (252)Cf source and the reactor will use high-purity graphite as moderator. Using the MCNP5 code the neutron spectra of the (252)Cf in the center of the graphite moderator has been estimated along the channel where the liquid thorium salt will be inserted; also the ambient dose equivalent due to the source has been determined around the moderator.
authors.affiliation: Universidad Simón Bolívar, Nuclear Physics Laboratory, Apdo 89000, Caracas 1080A, Venezuela. Electronic address: sajobohus@gmail.com.
authors.forename: Laszlo
authors.initials: L
authors.lastname: Sajo-Bohus
authors.affiliation: Universidad Simón Bolívar, Nuclear Physics Laboratory, Apdo 89000, Caracas 1080A, Venezuela.
authors.forename: Haydn
authors.initials: H
authors.lastname: Barros
authors.affiliation: Universidad Simón Bolívar, Nuclear Physics Laboratory, Apdo 89000, Caracas 1080A, Venezuela.
authors.forename: Eduardo D
authors.initials: ED
authors.lastname: Greaves
authors.affiliation: Unidad Academica de Estudios Nucleares, Universidad Autónoma de Zacatecas, C. Ciprés 10 Fracc. La Peñuela, 98068 Zacatecas, Zac., Mexico. Electronic address: fermineutron@yahoo.com.
authors.forename: Hector Rene
authors.initials: HR
authors.lastname: Vega-Carrillo
keywords: (252)Cf; Ambient dose equivalent; Monte Carlo; Neutrons