A thermal neutron dosimeter based on a combination of a BN-1 (Kodak Pa
the, France) and CR-39 (TASL, England) neutron converter, a charged pa
rticle detector and the use of an electrochemical device and the TRACO
S automatic image analysis system was developed. The response of the d
osimeter was found to be (7.3 +/- 0.5) x 10(-3) tracks/n and is compar
able to that obtained by optimal chemical etching conditions (7.7 x 10
(-3) tracks/n). A thermal neutron fluence from 10(4) to 10(8) n/cm(2)
can be measured reliably.