Estimation of neutron flux parameters f and Φth by using both reference soil materials and Al-Au alloy Irradiation
DOI:
https://doi.org/10.32685/2590-7468/invapnuclear.1.2017.18Keywords:
Instrumental Neutron Activation Analysis, validation, neutron flux parameters, gamma spectrometry
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Abstract
In this paper, the parameters thermal to epithermal neutron flux ratio (f) and thermal neutron flux (Φth) 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, γ) 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 n cm-2 s-1 (CV = 4 %).
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