Published August 2014 | Version v1
Miscellaneous Open

Neutrons characterization of the nuclear reactor Ian-R1 of Colombia

  • 1. Universidad Pedagogica y Tecnologica de Colombia, Grupo de Fisica Nuclear Aplicada y Simulacion, Carretera Central del Norte Km. 1, Via Paipa, 150003 Tunja, Boyaca (Colombia)
  • 2. Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas (Mexico)

Description

By means of Monte Carlo methods, with the code MCNPX, the neutron characteristics of the research nuclear reactor Ian-R1 of Colombia, in power off but with the neutrons source in their start position, have been valued. The neutrons spectra, the total flow and their average power were calculated in the irradiation spaces inside the graphite reflector, as well as in the cells with air. Also the spectra, the total flow and the absorbed dose were calculated in several places distributed along the radial shaft inside the water moderator. The neutrons total flow was also considered to the long of the axial shaft. The characteristics of the neutrons spectra vary depending on their position regarding the source and the material that surrounds to the cell where the calculation was made. (Author)

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Additional details

Additional titles

Original title (Spanish)
Caracterizacion de los neutrones del reactor nuclear IAN-R1 de Colombia

Publishing Information

Publisher
Sociedad Mexicana de Irradiacion y Dosimetria
Imprint Place
Mexico, D. F. (Mexico)
Imprint Pagination
17 p.
Report number
INIS-MX--2739

Conference

Title
14. International Symposium on Solid State Dosimetry
Original Conference Title
14. Conferencia Internacional sobre Dosimetria de Estado Solido
Dates
13-16 Apr 2014
Place
Cusco (Peru)