Comparison of neutron tract detector sensitivity as a function of the etching process

The use of neutron track detectors made of allyl diglycol carbonate (ADC) is increasing as the international nuclear community seeks better methods to to measure dose to personnel occupationally exposed to neutrons. The dosimetry-grade polymer ADC (CR-39), produced by PPG Industries, has undergone extensive evaluation in the past six years to prepare for its routine use at U.S. Department of Energy facilities. During this time many changes have been made in the way the CR-39 is processed. Each major improvement in the speed of processing or ease of readout has been adopted and current procedures provide excellent sensitivity and a nearly energy-independent energy response over the range of 144 keV to 2.8 MeV