Abstract
Among the neutron dose equivalent dosemeters currently under investigation, the electrochemically etched CR-39 detector has shown promise in the field of fast neutron dosimetry. The present paper discusses: (i) the optimisation of processing conditions in order to minimise the background; (ii) the use of front radiators to overcome the problem of neutron energy dependence; (iii) calculation of the response of CR-39, with the optimised stack, for cylindrical and hemispherical fields of fast neutrons; and (iv) calculations concerning the detection of thermal neutrons using various detector/converter configurations. Here we conclude that a converter using the 6Li(n,a)3H reaction can yield an ECE spot density per unit dose equivalent from thermal neutrons which is comparable to that from fast neutrons.
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