Published 2009 | Version v1
Book

Analytical method for uranium and plutonium determination in high level liquid waste (HLLW) stream samples of the PUREX process

  • 1. PREFRE Plant, Nuclear Recycle Group, Bhabha Atomic Research Centre, Tarapur (India)

Description

The method described herein involves the separation of U and Pu from suitably diluted sample aliquot of the high level liquid waste solution by co-extraction with 3% trialkyl phosphine oxide (TRPO) solution in normal paraffin hydrocarbon (NPH) at 3.5M HNO3. From loaded organic phase, U is stripped with 0.8 M oxalic acid and assayed by ICP-AES whereas Pu is reductively stripped with organic soluble tertiary butyl hydroquinone (TBH) and assayed by alpha-radiometry. The reliability of the method is checked by evaluating the analytical recovery of known amount of U and Pu spiked in diluted sample aliquots. The recovery is found quantitative within the experimental errors. Results of actual HLLW samples showed good agreement between existing and present method. (author)

Part of:
Proceedings of DAE-BRNS symposium on nuclear and radiochemistry

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of DAE-BRNS symposium on nuclear and radiochemistry
Imprint Pagination
679 p.
Journal Page Range
p. 427-428

Conference

Title
9. symposium on nuclear and radiochemistry
Acronym
NUCAR 2009
Dates
7-10 Jan 2009
Place
Mumbai (India)

Optional Information

Notes
3 refs., 3 tabs.