Extraction chromatographic separation of minor actinides from purex high-level wastes using CMPO

J. N. Mathur, M. S. Murali, R. H. Iyer, A. Ramanujam, P. S. Dhami, V. Gopalakrishnan, L. P. Badheka, Asoke Banerji

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Abstract

An extraction chromatographic technique using octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) adsorbed on chromosorb-102 (CAC) has been tested as an alternative to the TRUEX solvent extraction process, where CMPO has been used as the extracting agent to recover minor actinides from high-activity waste (HAW) solutions of PUREX origin. The batchwise uptake behavior of U(VI), Pu(IV), Am(III), Eu(III), Zr(IV), Fe(III), Ru(III), and TcO4- from a nitric acid medium by CAC has been studied. The uptake of actinides and lanthanides are higher than those of other fission products and inert materials. The batchwise loading experiments in the presence of Nd(III)/U(VI) have shown that at lower concentrations of these metal ions, the uptake of Pu(IV), U(VI), and Am(III) are reasonably high. Studies on loading of Nd(III), U(VI), and Pu(IV) on a column containing 1.7 g of CAC have shown that Nd(III) (30 mg) and U(VI) (90 mg) could be loaded, while Pu(IV) (approx.0.6 mg) was loaded on a small column containing 100 mg of CAC without any breakthrough. Further, a synthetic HAW solution as such and the actual PUREX HAW solution, after depleting the uranium content by a 30% tributyl-phosphate contact, were loaded on a CAC column. The effluents did not contain any alpha activity above the background level. The activities could subsequently be eluted with 0.04 M HNO3 (americium and rare earths), 0.01 M oxalic acid (plutonium), and 0.25 M Na2CO3 [U (VI)]. The recoveries of these metal ions were found to be > 99%.

Original languageEnglish
Pages (from-to)216-225
Number of pages10
JournalNuclear Technology
Volume109
Issue number2
Publication statusPublished - 02-1995

Fingerprint

Actinides
Metal ions
Americium
Oxalic acid
Fission products
Plutonium
Solvent extraction
Nitric acid
Rare earth elements
metal ions
Uranium
Rare earths
Effluents
Phosphates
americium
solvent extraction
oxalic acid
fission products
effluents
plutonium

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • Condensed Matter Physics

Cite this

Mathur, J. N., Murali, M. S., Iyer, R. H., Ramanujam, A., Dhami, P. S., Gopalakrishnan, V., ... Banerji, A. (1995). Extraction chromatographic separation of minor actinides from purex high-level wastes using CMPO. Nuclear Technology, 109(2), 216-225.
Mathur, J. N. ; Murali, M. S. ; Iyer, R. H. ; Ramanujam, A. ; Dhami, P. S. ; Gopalakrishnan, V. ; Badheka, L. P. ; Banerji, Asoke. / Extraction chromatographic separation of minor actinides from purex high-level wastes using CMPO. In: Nuclear Technology. 1995 ; Vol. 109, No. 2. pp. 216-225.
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Mathur, JN, Murali, MS, Iyer, RH, Ramanujam, A, Dhami, PS, Gopalakrishnan, V, Badheka, LP & Banerji, A 1995, 'Extraction chromatographic separation of minor actinides from purex high-level wastes using CMPO', Nuclear Technology, vol. 109, no. 2, pp. 216-225.

Extraction chromatographic separation of minor actinides from purex high-level wastes using CMPO. / Mathur, J. N.; Murali, M. S.; Iyer, R. H.; Ramanujam, A.; Dhami, P. S.; Gopalakrishnan, V.; Badheka, L. P.; Banerji, Asoke.

In: Nuclear Technology, Vol. 109, No. 2, 02.1995, p. 216-225.

Research output: Contribution to journalArticle

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AU - Mathur, J. N.

AU - Murali, M. S.

AU - Iyer, R. H.

AU - Ramanujam, A.

AU - Dhami, P. S.

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AU - Banerji, Asoke

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N2 - An extraction chromatographic technique using octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) adsorbed on chromosorb-102 (CAC) has been tested as an alternative to the TRUEX solvent extraction process, where CMPO has been used as the extracting agent to recover minor actinides from high-activity waste (HAW) solutions of PUREX origin. The batchwise uptake behavior of U(VI), Pu(IV), Am(III), Eu(III), Zr(IV), Fe(III), Ru(III), and TcO4- from a nitric acid medium by CAC has been studied. The uptake of actinides and lanthanides are higher than those of other fission products and inert materials. The batchwise loading experiments in the presence of Nd(III)/U(VI) have shown that at lower concentrations of these metal ions, the uptake of Pu(IV), U(VI), and Am(III) are reasonably high. Studies on loading of Nd(III), U(VI), and Pu(IV) on a column containing 1.7 g of CAC have shown that Nd(III) (30 mg) and U(VI) (90 mg) could be loaded, while Pu(IV) (approx.0.6 mg) was loaded on a small column containing 100 mg of CAC without any breakthrough. Further, a synthetic HAW solution as such and the actual PUREX HAW solution, after depleting the uranium content by a 30% tributyl-phosphate contact, were loaded on a CAC column. The effluents did not contain any alpha activity above the background level. The activities could subsequently be eluted with 0.04 M HNO3 (americium and rare earths), 0.01 M oxalic acid (plutonium), and 0.25 M Na2CO3 [U (VI)]. The recoveries of these metal ions were found to be > 99%.

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Mathur JN, Murali MS, Iyer RH, Ramanujam A, Dhami PS, Gopalakrishnan V et al. Extraction chromatographic separation of minor actinides from purex high-level wastes using CMPO. Nuclear Technology. 1995 Feb;109(2):216-225.