Published December 1986 | Version v1
Book

Assay of uranium in fused salt cake generated at the natural uranium metal fuel fabrication plants by gamma-ray spectrometry

  • 1. Department of Atomic Energy, Bombay (India). Nuclear Materials Accounting Cell

Description

A passive gamma-ray spectroscopic method is employed for the assay of uranium in fused salt cake, a scrap produced at the natural uranium metal fuel fabrication plants. The method makes use of NaI(TI) detector coupled with a multichannel analyser. The 1 MeV gamma-ray of 238U was used for the calibration. The calibration curve was made by counting synthetic mixtures made of U3O8 powder, the heat treatment salt and iron in the form of fine powder. The uranium content in these synthetic mixtures was kept in the range of 1-11 per cent. 23 lots of the fused salt cake taken from three different batches of the salt cake were then analysed by this method. The uranium content of fused salt cake was found to be in the range of 1.70-11.43 per cent. To compare the gamma spectrometric results with a completely independent method, chemical analysis of all the fused salt cakes were also carried out. The NDA results were found to agree within ± 17 per cent with the chemical analysis results. (author)

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre.
Imprint Place
Bombay (India)
Imprint Title
Radiochemistry and radiation chemistry symposium (held at) Tirupati (during) 13-17 December 1986
Imprint Pagination
529 p.
Journal Page Range
p. 418-420.

Conference

Title
Radiochemistry and radiation chemistry symposium.
Dates
13-17 Dec 1986.
Place
Tirupati (India).