Waste high-level liquid

The above information was used to develop conceptual flowsheets for the extraction of all of the actinides (U, Np, Pu, Am, and Cm) from high-level liquid waste from PUREX processing using 0.4 M 0fuel using 0.8 M DHDECMP in DEB. In both flowsheets, no oxidation state of Pu is necessary since the III, IV, and VI state extract into the organic phase. 

Conceptual flowsheet for the extraction of actinides from high-level liquid waste using 0.4 M 0<)>D[IB]CMP0 in DEB. 

Nigond, L. Musikas, C Cuillerdier, C. Solv. Extr. Ion Exch., 1994, 12, 297. Madic, C. Hudson, M. J. High Level Liquid Waste Partitioning by Means of Completely Incinerable Extractants, European Commission, Nuclear Science and Technology, EUR18038 EN 1998 p. 208. 

Demine, A. V., Krylova, N. V., Poluektov, P. P., Shestoperov, I. N., Smelova, T. V., Gorn, V. F. Medvedev, G. M. 2001. High level liquid waste solidification using a cold crucible induction melter. Materials Research Society Symposium Proceedings, 663, 27-34. 

High-Level Waste. There are approximately 285 million liters containing approximately 590 x 10 curies ( ) of military and 2.3 million liters of commercial high-level liquid waste (O presently stored in tanks. Although the volume of high-level military waste is much greater, the curie content of strontium 90 of both sources is approximately the same if stored spent fuel rods from commercial reactors are included in the inventory. The total curie content will be the same for both sources by 1985 at the present rate of use ( ). To date, there has been no disposal of any high-level waste. 

Horwitz, E.P., Schultz, W.W. 1999. Solvent extraction in the treatment of acidic high-level liquid waste Where do we stand In Metal Ion Separation and Preconcentration Progress and Opportunities. Bond, A.H., Dietz, M.L., Rogers, R.D. Eds. ACS Symposium Series 716, American Chemical Society, Washington, DC, pp. 20-50. 

Madic, C., Hudson, C. 1998. High level liquid waste partitioning by means of completely incinerable extractants. EUR 18038 EN. European Commission on Nuclear Science and Technology, Luxembourg. 

Wang, J., Song, C. 2001. Hot test of trialkyl phosphine oxide (TRPO) for removing actinides from highly saline high-level liquid waste (HLLW). Solvent Extr. Ion Exch. 19 (1) 231-242. 

Simon, N., Toumois, B., Eymard, S. et al. 2004. Cs selective extraction from high level liquid wastes with crown calixarenes Where are we today Atalante, Nimes, France, June 21-25, pp. 1-57. 

Morita, Y., Sasaki, Y., Tachimori, S. 2001. Development of TODGA extraction process for high-level liquid waste Preliminary evaluation of actinide separation by calculation. Proc GLOBAL 2001, Paris, France, September 9-13. 

Manohar, S., Sharma, J.N., Shah, B.V., Wattal, P.K. 2007. Process development for bulk separation of trivalent actinides and lanthanides from radioactive high-level liquid waste. Nuclear Science and Engineering 156 96-102. 

Morita, Y., Yamaguchi, I., Fujiwara, T., Koizumi, H., Kubota, M. 1998. The first test of 4-group partitioning process with real high-level liquid waste at NUCEF. NUCEF 98 Symposium Working Group, November, Hitachinaka, Ibaraki, Japan. 

Madic, C., Blanc, P., Condamines, N., Baron, P., Berthon, L., Nicol, C., Pozo, C., Lecomte, M., Philippe, M., Masson, M., Hequet, C., Hudson, M.J. 1994. Actinide partitioning from high level liquid waste using the DIAMEX process. RECOD 94, April, London, UK. 

Hirano, H., Koma, K., Koyama, T. 2002. Waste minimization in actinides(IH)/ lanthanides(III) separation process from high-level liquid waste. 7th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, October, Jeju, Republic of Korea. 

Ozawa, M., Koma, Y., Nomura, K., Tanaka, Y. Separation of actinides and fission products in high-level liquid wastes by the improved TRUEX process. J. Alloys Compd. (1998), 271-273, 538-543. 

Chinese scientists used trialkyl phosphine oxides (TRPO) to remove long-lived radioactive nuclides from high-level liquid waste (67, 167). TRPO is the trademark of a Chinese commercial product, consisting of a mixture of several TRPO (with alkyl chains from hexyl to octyl). The TRPO process has been tested in China and at ITU in Karlsruhe (2, 168-174). 

Tachimori, S., Ito, Y. 1979. Radiation damage of organic extractant in partitioning of high-level liquid waste, (I) Radiolysis of di(2-ethylhexyl)phosphoric acid by irradiation with cobalt-60 gamma rays. J. Nucl. Sci. Technol. 16(1) 49-56. 

Xuegang, L., Junfu, L., Jingming, X. 2004. Simplified Chinese TRPO Process to extract and recover transuranium elements from high-level liquid waste. Solvent Extr. Ion Exch. 22(2) 163-173. 

The INET annular centrifugal contactors are being used to partition high-level liquid waste so that the back end of the nuclear fuel cycle can be simplified. In particular, the TRPO process has been developed at INET for this application (Song, 2000), where TRPO is the extractant in the process solvent. Also known as Cyanex 923, TRPO is a trialkyl phosphine oxide that is made commercially by Cytec Industries (formerly American Cyanamid). It has a high affinity for the actinides. Further... 

Horwitz, E. P. and Schulz, W. W. Solvent Extraction in the Treatment of Acidic High-Level Liquid Waste, Where Do We Stand In Metal-Icm Separation and Preconcentration, Bond, A. H., Dietz, M. 

The CTH actinide separation process was developed as a possible means to reduce the expected long term dose to man from a geologic repository containing solidified radioactive waste from the reprocessing of spent nuclear fuel The distribution data for the elements present in significant amounts in the high level liquid waste (HLLW) from a Purex plant, the general principles and the flowsheet have been described in detail elsewhere A... 

The results show that separation of metals from simulated high level liquid wastes is possible and that approximately 42 wt% of the metals can be recovered. From the experiments performed, there is some interaction between the metals and redox couples must exist as determined by the change in oxidation states of Cr, Ce, and Pr from +3 to +4. Periodic table Group I metals were found to remain in solution. It is not known at this point whether the metals in solution are unreacted nitrates or whether they have reacted to some species that are soluble in 1.6 M HN03. A simple model based on an adsorption model was found to adequately describe the data. Because of the experimental technique, it is not possible to know the precise metals and percentages that can be recovered from the solutions studied at supercritical conditions. More detailed experiments with a flow experiment and further research will answer many of these questions. This research on these points is in progress. 

Elements and Concentration of Simulated High Level Liquid Waste (HLLW)... 

Kondo, Y and Kuboto, M., Precipitation Behavior of Platinum Group Metals from Simulated High Level Liquid Waste in Sequential Denitration Process, J. Nucl. Sci. Technol., 29(2), (1992), ppl40-l48. 

To date the ICPP has produced approximately 4.6 million gal of high-level liquid waste of which 2.0 million gal are in the liquid form as shown in Table IV and 2.6 million have been calcined to a solid. High-level wastes began accumulating at the ICPP in 1953 and the rate of production has steadily increased (3). New wastes are anticipated from new fuels and will be discussed later in this chapter. 

Solidification of High-Level Liquid Wastes in the Waste Calcining Facility (WCF)... 

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