Use of fission track analysis technique for the determination of MicroBequerel level of 239Pu in urine samples from radiation workers handling MOX fuel

Fission track analysis (FTA) technique for the determination of 239Pu excreted through urine has been standardized using blank samples, tracer and 239Pu spikes. Double stage anion exchange separation protocol has been applied and an average radiochemical recovery of 239Pu of 18% was obtained. An average track registration efficiency of 11 tracks per μBq of 239Pu, irradiated to 0.35×1017 neutron fluence was established. Reagent blank urine samples from 11 controlled subjects were analyzed by FTA and an average of 149±14 tracks was obtained. Minimum detectable activity of 34 μBq L−1 of urine sample was obtained and will be useful for monitoring chronic exposure cases handling MOX fuel.