Abstract
Approximate neutron energy spectra can be obtained by using a combination of dosimeter elements which have a different response for different neutrons energies. This paper describes a simple mathematical technique which can be applied to combination neutron dosimeter/spectrometers to increase the accuracy of the dose equivalent evaluation. A simple iterative algorithm is applied to determine the dose equivalent from CR-39 (polydiallyl-diglycol carbonate), polycarbonate, LR-115 (cellulose nitrate) track etch and albedo neutron detectors. The algorithm is simple enough to allow rapid evaluation of several different types of personnel neutron dosimeters with better accuracy than most existing methods.
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