Highly-active waste

Apostilidos, C., Meester, R., de Koch, L. et al. 1990. The extraction of actinides and other constituents from highly-active waste (HAW) by trialkyl phosphine oxide (TRPO). Technical seminar on new separation chemistry techniques for radioactive waste and other specific applications, Rome (Italy), May 16-18. EUR-13390-EN. 

Zhu, Y., Song, C. 1992. Recovery of neptunium, plutonium and americium from highly active waste. Tri-alkyl phosphine oxide extraction. In Transuranium Elements A Half Century. Morss, L.R. Fuger, J., Eds. ACS, Washington, DC, pp. 318-330. 

Zhu, Y., Jiao, R. 1994. Chinese experience in the removal of actinides from highly active waste by trialkyl phosphine oxide extraction. Nucl. Technol. 108 361-369. 

Wood, D.J., Law, J.D., Todd, T.A. 1998. Demonstration of a SREX process for the treatment of actual high activity waste at the INEEL using centrifugal contactors. Science and Technology for Disposal of Radioactive Tank Waste, Schulx, W.W., Lombardo, NJ. Eds. Plenum, New York, pp. 255-268. 

Apostolidis, C. Meester, R. De. Koch, L. Molinet, R. Liang, J. Zhu, Y. The Extraction of Actinides and Other Constituents from Highly Active Waste (HAW) by Triallkyl Phosphine Oxide. In New Separation Techniques for Radioactive Waste and Other Specific Applications, L. Cecille, M. Casa, and L. Pietrelli (Eds.), Elsevier Applied Science, Rome Italy (1990), p. 80. 

In a test at Mayak nuclear fuel reprocessing plant in Russia, alkaline high-active waste was subjected to extraction by a mixture of parent /-butyl calix[6]arene, 2- [bis(2-hydroxyethyl)amino]methyl -4-alkylphenol, and a solubilizer in dodecane. 

Bibler, J. P., Wallace, R. M., and Bray, L. A. Testing a New Cesium-Specific Ion Exchange Resin for Decontamination of Alkaline High-Activity Waste, Report WSRC-RP-89, Westinghouse Savannah River Co., Aiken, SC, 1989. 

Recovery of Americium—Curium From High-Activity Waste Concentrate by In-Canyon-Tank Precipitation as Oxalates... 

Mousty, F. Toussaint, J. Godfrin, J., "Separation of Actinides from High Activity Waste. The Oxal Process," Radiochem. Radioanal. Lett., 1977, 31, 918. 

Some research groups worldwide are currently working on the application of membrane technology to the treatment of radioactive liquid wastes with different levels of activity, from low to high activity waste. Research is mainly focused on wastes from the nuclear industry. However, the nuclear industry is not the only source of radioactive wastes medical and research applications of radioisotopes also generate radioactive wastes. 

The annual yield in vitrified high activity waste from the spent fuel elements of a 1000 MW nuclear power only amounts to 3 m-. ... 

Separation of Actinides from Purex-Type High Active Waste Raffinates... 

Separation of Actinides from High Active Waste by Means of Counter Current Ion Migration... 

The use of nuclear power as energy source is determined by the safe handling and deposition of the nuclear waste. High active waste solutions must be transformed into stable solid form which is suitable for final disposal. The separation of the actinides from the waste before its solidification (e.g. vitrification) is advantageous (or may be even necessary) from two points of view ... 

During the decontamination steps, acid streams containing small amounts of actinides and fission products are produced. These streams are evaporated to concentrate the metal ions and recycle them. Nitric acid is recovered from the condensates and recycled. Excess HNO3 may be destroyed by formaldehyde. Fission product concentrates are routed to the aqueous raffinate of the first extractor of the partitioning cycle which contains > 99% of the FP. This constitutes the high level liquid waste (HLLW, or alternatively called HAW, high active waste). All other liquid wastes can be subdivided into intermediate level waste... 

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