Abstract
In this paper is described in detail an irradiation and counting geometry for analysis using the inelastic scattering (n,n′ y) reaction with an isotopic ( 241Am- 9Be) neutron source. The optimum sample size required in such analysis is derived experimentally. The geometry requires the use of bulk samples, in which there could be appreciable depression in the neutron flux during irradiation. Calculations have been made for the average undisturbed flux within the sample. Analytical sensitivities for major and minor elements in rock and ore samples are also determined and results presented.
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