Abstract
The method for computing absolute thermal neutron fiux from measurements made with activated indium foils is described, By combining data from the conuting rate of indium foils in 2 pi proportional counters with appropriate corrections for foil weights and neutron effects, the thermal flux is expressed in terms of sigma o, the thermal absorption cross section of In/sup 115/. This procedure may be used by laboratories which do not have access to a standard graphite pile or to a standard neutron source. This method has an estimated error less than 5% which is a function of the accuracy with which it is possible to determine the various correc tion factors for beta counting, A possible fixed erro in the value of sigma /sup 0 can easily be corrected for and incorporated into the methods used. (auth)
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