TRUEX process

Troubleshooting Trouton constant Troxerutin [7085-55-4] Troysan 174 Troysan 192 True color holograms TrueType Truex process Truncatella sp. Truscottite [12425-42-2] Truxal Trycol... 

Of the many radioactive and inert constituents in waste solutions, only Tc and lanthanides coextract with actinides into the Truex process solvent. Trivalent lanthanides follow Am and Cm when the latter are stripped with dilute HNO3 depending on the disposition of the americium and... 

Fig. 12.10 Generic Truex process flow sheet for use with nitric acid wastes (NPH is a mixture of aliphatic hydrocarbons). 

During development of the Truex process, various monofunctional organophosphorus reagents [e.g., TBP DBBP (dibutylbutylphosphonate) HDEHP (di-(2-ethylhexyl)phosphoric acid)] were considered for removal of alpha-emitters from HNO3 waste solutions. Two typical flow sheets for the use of HDEHP and TBP are shown in Fig. 12.14. Because of the poor performance of these two extractants, the processes were complicated. Distribution ratios... 

T0066 Argonne National Laboratory, Transuranium Extraction (TRUEX) Process... 

T0066 Argonne National Laboratory, Transuranium Extraction (TRUEX) Process T0072 Atomic Energy of Canada Ltd. (AECL), CHEMIC Technology T0081 Battelle Memorial Institute, Liquid-Liquid Extraction of Metals (LLX)... 

T0005 Active Environmental Technologies, Inc., TechXtract T0066 Argonne National Laboratoiy, Transuranium Extraction (TRUEX) Process T0132 Brookhaven National Laboratory, Biochemical Recovery of Radionuclides and Heavy Metals... 

T0066 Argonne National Laboratory Transuranium Extraction (TRUEX) Process T0151 Ceramic Immobilization of Radioactive Wastes—General T0169 Clemson University, Sintered Ceramic Stabilization... 

In applications of TRUEX technology to the removal of actinides from hydrochloric acid media, CMPO will extract vanadium, iron, copper, zinc, gallium, zirconium, molybdenum, tin, and lead under the same conditions under which it will extract targeted actinides. The wastes extracted by the TRUEX process will require additional treatment before they may be safely disposed. 

Nuclear Waste Reprocessing. Liquid waste remaining from processing of spent reactor fuel for military plutonium production is typically acidic and contains substantial transuranic residues. The cleanup of such waste in 1996 is a higher priority than military plutonium processing. Cleanup requires removal of long-lived actinides from nitric or hydrochloric acid solutions. The transuranium extraction (Truex) process has been developed for... 

Because of the interest aroused by the properties of the title extractant, more commonly referred to as CMPO, for use in chromatographic columns1 and the TRUEX process,2 a more detailed description than previously published3 of the preparation, purification, and physical properties of (V,7V-diisobutyl-2-... 

To design and optimize flowsheets most appropriate for the objective application, the GTM program has been used (212, 213). After the 1990s, the application of the TRUEX process for practical purposes has been implemented successfully (214-219), parallel to fundamental investigations (220-225). 

Chiarizia, R., Horwitz, E.P. 1990. Secondary clean up of TRUEX process solvent. Solvent Extr. IonExch. 8 (6) 907-941. 

Chiarizia, R., Gasparini, G.M., Casarci, M., Rossi, M., Grossi, G. 1993. Italian experience with the TRUEX process. GLOBAL 93 Future Nuclear Systems Emerging Fuel Cycles and Waste Disposal Options. Seattle, WA, September 12-17. 

Ozawa, M., Hirano, H., Koma, Y., Kawata, T. 1995. Enhancing actinides separation by consolidated PUREX and TRUEX processes intensified by salt-free requisite. Int. Conf. Evaluation of Emerging Nuclear Fuel Cycle Systems. GLOBAL 95, Vol. 1, Versailles, France, September 11-14, pp. 585-594. 

Due to the ease of formation of third phase with CMPO, many literature reports are based on the use of the mixture of 0.2 M CMPO + 1.2 M TBP as the solvent (63). This mixture has also been used in the TRUEX process recommended for the partitioning of minor actinides from HLW. Some applications of CMPO for the separation of Pu include its recovery from assorted laboratory wastes and oxalate supernatant (64, 65). 

FIG U RE 3.1 n-Octyl-phenyl-W, W -di(/so )butyl-carbamoyl-methyl phosphine oxide (CMPO) used in the TRUEX process. 

Diphcnyl-/V,/V-di obutylcarbamoylmcthylphosphinc oxide (Ph2-CMPO, Figure 3.3), a bidentate neutral organophosphorus compound (BNOPC) derived from the TRUEX process, which proved to be efficient for the removal of actinides and REEs. 

It generally proceeds through the extraction of the Ln(III) at a pH ranging from 2 to 3, leaving the An(III) in the aqueous raffinate as polyaminopolycarboxylate complexes. Therefore, it requires a buffered feed, which could be the stripping solution of a front-end process (such as the TRUEX process). 

Horwitz, E.P., Schulz, W.W. 1990. The TRUEX process A vital tool for disposal of US defense nuclear wastes. Conference on New Separation Chemistry for Radioactive Waste and Other Specific Applications, May, Rome, Italy. 

Spencer, B., Egan, B.Z., Beahm, E.C., Chase, C.W., Dillow, T.A. 1999. Dissolution of ORNL HLW sludge and partitioning of the actinides using the TRUEX process. Separation Science and Technology 34(6 7) 1021-1042. 

Fujii, T., Yamana, H., Moriyama, H. 2002. Decontamination study of some noticeable fission products in the actinides recovery by TRUEX process. 7th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, October, Jeju, Republic of Korea. 

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