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Measurement of the correct neutron fluence in various energy intervals in and around the neutron sources is important for the purpose of personnel and environmental neutron dosimetry. In the present paper we present a method for the measurement of neutron fluence using a CR-39 plastic track detector. The samples exposed to fission neutrons from a reactor with 10¹²–10¹⁶cm^-2 fluence and to fast neutrons from a ²⁴¹Am–Be source with a fluence of 3.0×10¹²cm^-2 were etched for 14 time intervals starting from 10 to 570min in 6N NaOH at 70^∘C. The etched samples were exposed to the monochromatic light signal from an iodine–tungsten lamp and the transmittance was measured after each etching time interval using a UV Spectrophotometer. An exponential decay of the transmittance has been observed with increasing etching time. The behaviour of the fission neutrons having four different values of fluence …