1984•University of North Texas Digital Library (University of North Texas)Open access
TRU decontamination of high-level Purex waste by solvent extraction using a mixed octyl(phenyl)-N,N-diisobutyl-carbamoylmethylphosphine oxide/TBP/NPH (TRUEX) solvent
E. Philip Horwitz, Dale G. Kalina, H. Diamond, Louis A. Kaplan, G.F. Vandegrift, R. A. Leonard, M.J. Steindler, W.W. Schulz
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Abstract
The TRUEX (transuranium extraction) process was tested on a simulated high-level dissolved sludge waste (DSW). A batch counter-current extraction mode was used for seven extraction and three scrub stages. One additional extraction stage and two scrub stages and all strip stages were performed by batch extraction. The TRUEX solvent consisted of 0.20 M octyl(phenyl)-N,N-diisobutylcarbamoyl-methylphosphine oxide-1.4 M TBP in Conoco (C/sub 12/-C/sub 14/). The feed solution was 1.0 M in HNO/sub 3/, 0.3 M in H/sub 2/C/sub 2/O/sub 4/ and contained mixed (stable) fission products, U, Np, Pu, and Am, and a number of inert constituents, e.g., Fe and Al. The test showed that the process is capable of reducing the TRU concentration in the DSW by a factor of 4 x 10/sup 4/ (to <100 nCi/g of disposed form) and reducing the quantity of TRU waste by two orders of magnitude.
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