ABSTRACT
The plutonium-uranium extraction (PUREX) process has been universally used for the reprocessing of spent nuclear fuel. Many computer codes have been developed for the mathematical modeling of the PUREX process including the SEPHIS, PULSTX, SOLVEX, and MIXSET4 computer codes. The transuranic extraction (TRUEX) process was developed by E. P. Horwitz at Argonne National Laboratory for the separation of transuranic elements from acidic nuclear waste solutions. This solvent extraction process can be used to reduce the quantity of transuranics in a waste solution to a level where the waste can be classified as non- transuranics. Experimental data generated for the separation of actinides from sodium-bearing waste (SBW) were compared to results predicted by the generic TRUEX model (GTM) in order to determine the applicability of the GTM to Idaho Chemical Processing Plant (ICPP) SBW. These data were generated from TRUEX tests performed on simulated ICPP SBW with radioactive tracers.
