A practical applicability of several techniques to a commercial dose-assessment service has been investigated for improving the energy dependence of the personal neutron dosemeter based on PADC plastic track detector. Under a constraint of no modification in detector material and the fixed chemical processes, two technical attempts have been investigated; an analysis of etch-pit data obtained by microscopic observation and a devise of radiator structure. In addition to the number of etch-pits, another information of their distribution in some parameter has been obtained in the former technique. It was found that the two-window method was possibly applicable to the distribution in the etch-pit size and the gray level. In the latter, a performance of radiator-degrader structure has been confirmed experimentally, and it was found to be one of most promising techniques.