Authors:
P. Sawant Bhabha Atomic Research Centre Internal Dosimetry Division Trombay, Mumbai 400 085 India

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P. Kalsi Bhabha Atomic Research Centre Radiochemistry Division Trombay, Mumbai 400 085 India

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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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Journal of Radionalytical and Nuclear Chemistry
Language English
Size A4
Year of
Foundation
1968
Volumes
per Year
1
Issues
per Year
12
Founder Akadémiai Kiadó
Founder's
Address
H-1117 Budapest, Hungary 1516 Budapest, PO Box 245.
Publisher Akadémiai Kiadó
Springer Nature Switzerland AG
Publisher's
Address
H-1117 Budapest, Hungary 1516 Budapest, PO Box 245.
CH-6330 Cham, Switzerland Gewerbestrasse 11.
Responsible
Publisher
Chief Executive Officer, Akadémiai Kiadó
ISSN 0236-5731 (Print)
ISSN 1588-2780 (Online)