Published 2012 | Version v1
Book

Removal of TBP degradation products from carbonate scrub solution using 2-ethyl-1-hexanol

  • 1. Reprocessing Plant Operation Division, Reprocessing Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)

Description

The reprocessing of spent nuclear fuel of FBTR having burn up (up to 155 GWd/t) was carried out in CORAL (Compact Reprocessing of Advanced fuel in Lead shielded cells) by following modified PUREX process. In this process, TBP diluted with n-dodecane is used as an extractant. TBP degrades significantly due to radiolysis and extracted metal ion as well as HNO3 hydrolysis leading to the formation of HDBP, H2MBP, H3PO4 etc which interfere with the liquid-liquid extraction process. Hence the spent solvent is periodically cleaned up with an alkaline solution of Na2CO3, (NH4)2CO3 or N2H4.H2CO3 . These carbonate solutions form water soluble salts with the acidic degradation products of TBP and complexes of the actinides like Pu, U and fission products like Zr and Ru

Part of:
Proceedings of DAE-BRNS biennial symposium on emerging trends in separation science and technology

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of DAE-BRNS biennial symposium on emerging trends in separation science and technology
Imprint Pagination
274 p.
Journal Page Range
p. 110

Conference

Title
5. DAE-BRNS biennial symposium on emerging trends in separation science and technology
Acronym
SESTEC-2012
Dates
27 Feb - 1 Mar 2012
Place
Mumbai (India)

Optional Information

Notes
3 refs., 2 tabs.