Estimation of neutron flux parameters f and θth by using both reference soil materials and Al-Au alloy Irradiation
AbstractAbstract
[en] In this paper, the parameters thermal to epithermal neutron flux ratio (f) and thermal neutron flux (θth) are estimated (assuming α = 0) for the periphery irradiation positions (G3-G4) available at Nuclear Research Reactor IAN-R1 that belongs to the Colombian Geological Survey. This estimation was performed by measuring the induced activity, from neutron capture reactions (n, y) in two reference soils, which were irradiated (n = 4) together with Al-Au monitors. Four reference capture reactions were considered in soils, which involve isotopes of elements with certified mass fraction and 1/v behavior for cross section variation in the range of thermal neutron energy. An average value of 33 (CV = 9%) for f was found, considering 8 positions in the irradiation container; this value is comparable with measurements reported for periphery irradiation channels of TRIGA type reactors. The average thermal neutron flux determined for the 8 position of the container resulted in 1,5 *1011 ncm-2 s-1 (CV = 4 %).
Original Title
Estimacion de los parametros de flujo neutronico f y θth a partir de la irradiacion de suelos de referencia y monitores de Al-Au
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Journal Article
Journal
Revista de Investigaciones y Aplicaciones Nucleares; ISSN 2590-7468;
; v. 1; p. 24-29

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BARYONS, CHEMICAL ANALYSIS, DEVELOPING COUNTRIES, ELEMENTARY PARTICLES, ENRICHED URANIUM REACTORS, FERMIONS, HADRONS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, LATIN AMERICA, MEASURING INSTRUMENTS, NEUTRONS, NONDESTRUCTIVE ANALYSIS, NUCLEONS, POOL TYPE REACTORS, RADIATION FLUX, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SOLID HOMOGENEOUS REACTORS, SOUTH AMERICA, SPECTROMETERS, THERMAL REACTORS, TRAINING REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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