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Title: Extraction chromatographic separation of minor actinides from PUREX high-level wastes using CMPO

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 TcO{sub 4}{sup {minus}} 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) ({approximately}0.6) was loaded on a small column containing 100 mg of CAC without any break-through. 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 activitymore » above the background level. The activities could subsequently be eluted with 0.0.4 M HNO{sub 3} (americium and rare earths), 0.01 M oxalic acid (plutonium), and 0.25 M Na{sub 2}CO{sub 3} [U(VI)]. The recoveries of these metal ions were found to be >99%.« less

Authors:
; ; ; ; ; ; ; ;  [1]
  1. Bhabha Atomic Research Centre, Bombay (India)
Publication Date:
OSTI Identifier:
109969
Resource Type:
Journal Article
Journal Name:
Nuclear Technology
Additional Journal Information:
Journal Volume: 109; Journal Issue: 2; Other Information: PBD: Feb 1995
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; HIGH-LEVEL RADIOACTIVE WASTES; RADIOACTIVE WASTE PROCESSING; ACTINIDES; EXTRACTION CHROMATOGRAPHY; URANIUM IONS; PLUTONIUM IONS; AMERICIUM IONS; EUROPIUM IONS; ZIRCONIUM IONS; IRON IONS; RUTHENIUM IONS; TECHNETIUM OXIDES; NEODYMIUM IONS; ACTIVITY LEVELS; NITRIC ACID; SODIUM CARBONATES; FISSION PRODUCTS; RARE EARTHS

Citation Formats

Mathur, J N, Murali, M S, Iyer, R H, Ramanujam, A, Dhami, P S, Gopalakrishnan, V, Rao, M K, Badheka, L P, and Banerji, A. Extraction chromatographic separation of minor actinides from PUREX high-level wastes using CMPO. United States: N. p., 1995. Web.
Mathur, J N, Murali, M S, Iyer, R H, Ramanujam, A, Dhami, P S, Gopalakrishnan, V, Rao, M K, Badheka, L P, & Banerji, A. Extraction chromatographic separation of minor actinides from PUREX high-level wastes using CMPO. United States.
Mathur, J N, Murali, M S, Iyer, R H, Ramanujam, A, Dhami, P S, Gopalakrishnan, V, Rao, M K, Badheka, L P, and Banerji, A. Wed . "Extraction chromatographic separation of minor actinides from PUREX high-level wastes using CMPO". United States.
@article{osti_109969,
title = {Extraction chromatographic separation of minor actinides from PUREX high-level wastes using CMPO},
author = {Mathur, J N and Murali, M S and Iyer, R H and Ramanujam, A and Dhami, P S and Gopalakrishnan, V and Rao, M K and Badheka, L P and Banerji, A},
abstractNote = {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 TcO{sub 4}{sup {minus}} 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) ({approximately}0.6) was loaded on a small column containing 100 mg of CAC without any break-through. 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 0.0.4 M HNO{sub 3} (americium and rare earths), 0.01 M oxalic acid (plutonium), and 0.25 M Na{sub 2}CO{sub 3} [U(VI)]. The recoveries of these metal ions were found to be >99%.},
doi = {},
url = {https://www.osti.gov/biblio/109969}, journal = {Nuclear Technology},
number = 2,
volume = 109,
place = {United States},
year = {1995},
month = {2}
}