Abstract
Various plutonium compounds are handled in nuclear facilities of BARC. Hence, there is a possibility of occupational workers getting exposed to Pu. In vitro bioassay monitoring in which Pu is separated by chemical procedures from excreta samples and estimated by alpha-spectrometry, is the method of choice for the evaluation of internal dose to the occupational workers handling Pu. However, this method requires a suitable Pu tracer for reducing the uncertainties due to chemical yield in the separation, electro-deposition and counting efficiency. 242Pu is commonly used as a tracer but due to its non-availability, efforts were made earlier to indigenously synthesis 236Pu by proton irradiation of 237Np in BARC-TIFR pelletron facility. The present study, reports the feasibility of using 236Pu as a radiochemical yield monitor (tracer) in bioassay samples.
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Sawant, P.D., Kalsi, P.C. Feasibility studies to assess the use of 236Pu as a radiochemical yield monitor in bioassay samples. J Radioanal Nucl Chem 274, 67–69 (2007). https://doi.org/10.1007/s10967-006-6903-3
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DOI: https://doi.org/10.1007/s10967-006-6903-3