Abstract
A method of using aluminum for the determination of the neutron flux above 2.1 Mev is described. The amount of thermal and fast activation induced in the aluminum is determined by counting the gammas from the BETA decay products of Al/sup 28/ and Mg/sup 27/, formed by thermal and fast neutron reactions with Al/sup 27/. The fast flux is obtained by taking the ratio of the fast and thermal induced saturation activities. To determine the fast flux at a point in a reactor, four exposures are needed --two with bare indium and cadmium-covered medium to measure the absolute thermal flux and two with bare and cadmium-covered aluminum to measure the slow and fast gamma lines without much Compton electron background. The advantages of the method are listed. (J.S.R.)
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