Separation of plutonium and uranium in bioassay samples

Uranium and transuranics (especially 239Pu) are handled at various stages of nuclear fuel cycle. This can lead to internal contamination of the radiation workers following the intake of radionuclides by inhalation. Therefore, prompt detection and estimation of the amount of 239Pu and 233U inhaled by the workers are necessary for the computation of internal dose. In-vitro bioassay techniques are known to be more sensitive and are therefore commonly used for assessment of intakes of actinides in the body. The conventional procedure for determination of low levels of 239Pu and 233U in urine samples is based on separation using anion exchange column. A radiochemical procedure for estimating the amount of 233U exerted in urine was standardized and its suitability for the assessment of occupational exposure due to intakes of 233U was studied