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Updated: Jul 4, 2026

Neutron Radiography and Computed Tomography of Biological Systems at the Oak Ridge National Laboratory's High Flux Isotope Reactor
Published on: May 7, 2021
The determination of reactor neutron spectrum-averaged cross-sections in miniature neutron source reactor facility
S A Jonah1, Y V Ibrahim, E H K Akaho
1Centre for Energy Research and Training, Ahmadu Bello University, P.M.B. 1014, Zaria, Nigeria. jonahsa2001@yahoo.com
Abstract:
A comparator method based on the resonance integral of (197)Au(n,gamma)(198)Au reaction has been used to determine fast neutron spectrum-averaged cross-section data of some dosimetry reactions in a miniature neutron source reactor (MNSR) facility. Target materials of low- and medium-mass nuclei, which are of interest in reactor dosimetry and NAA were investigated. Irradiation was performed under Cd cover in an inner irradiation channel of the Nigeria Research Reactor-1 (NIRR-1) currently fueled with highly enriched uranium (HEU). Spectrum-averaged cross-section data were calculated on the basis of the epithermal neutron flux monitored by the Al-0.1%Au foil irradiated along with the target materials. Results of (n,p) reaction on (27)Al, (28)Si, (29)Si, (46)Ti, (47)Ti, (56)Fe, (58)Ni, and (n,alpha) reaction on (30)Si were found to be in good agreement with recommended data within standard deviation. However, data obtained for the (27)Al(n,alpha) (24)Na and (64)Zn (n,p) (64)Cu reactions using the Al-0.1%Au foil as the flux monitor for both the comparator approach and the conventional method are higher than recommended data from the literature by over 25%.
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