Recovery of Fission Products from Waste Solutions by Solvent Extraction
Author : D. E. Horner
Publisher :
Page : 46 pages
File Size : 23,97 MB
Release : 1963
Category : Fission products
ISBN :
Author : D. E. Horner
Publisher :
Page : 46 pages
File Size : 23,97 MB
Release : 1963
Category : Fission products
ISBN :
Author :
Publisher :
Page : pages
File Size : 29,13 MB
Release : 1963
Category :
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Solvent-extraction techniques for recovering fission products from reactor fuel process waste liquors are discussed. Topics covered include composition of feed -liquors, experimental techniques, recovery of strontium and rare earths, promethium and rare earth separations, cesium recovery, zirconium - niobium recovery, and aqueous feed pretreatment with amines. A flowsheet for the techniques described is presented. (M.C.G.).
Author : R. L. Moore
Publisher :
Page : 11 pages
File Size : 21,37 MB
Release : 1958
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Processes are described for the recovery of cesium137 from Purex type, first cycle waste solutions which result from the solvent extraction reprocessing of reactor fuels. Flowsheets are presented for recovering cesium from neutralized wastes by coprecititation with zinc ferrocyanide or from acidic solution by precipitation with zinc ferricyanide or zinc cobalticyanide. Further processing converts the cesium to cesium chloride, a stable form suitable for use in high intensity gamma irradiation sources. Modification of the cesium recovery process enables isolation of other valuable products including rare earths, cerium-144, and strontium-90 activities. Experience at Hanford Atomic Products Operation in the use of similar procedures for rge to the ground is described. A comparison of objectives and gested for fission product recovery is made. The effect of recovering certain fission products, particularly longlived nuclides, from effluents on temporary or long term storage or disposal of the effluent is discussed. (auth).
Author : International Atomic Energy Agency
Publisher :
Page : 262 pages
File Size : 11,50 MB
Release : 1967
Category : Fission products
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Author :
Publisher :
Page : pages
File Size : 13,30 MB
Release : 1958
Category :
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Processes are described for the recovery of cesium137 from Purex type, first cycle waste solutions which result from the solvent extraction reprocessing of reactor fuels. Flowsheets are presented for recovering cesium from neutralized wastes by coprecititation with zinc ferrocyanide or from acidic solution by precipitation with zinc ferricyanide or zinc cobalticyanide. Further processing converts the cesium to cesium chloride, a stable form suitable for use in high intensity gamma irradiation sources. Modification of the cesium recovery process enables isolation of other valuable products including rare earths, cerium-144, and strontium-90 activities. Experience at Hanford Atomic Products Operation in the use of similar procedures for rge to the ground is described. A comparison of objectives and gested for fission product recovery is made. The effect of recovering certain fission products, particularly longlived nuclides, from effluents on temporary or long term storage or disposal of the effluent is discussed. (auth).
Author : R. L. Moore
Publisher :
Page : 40 pages
File Size : 10,78 MB
Release : 1964
Category : Cerium
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Author : R. P. Wischow
Publisher :
Page : 56 pages
File Size : 41,60 MB
Release : 1962
Category : Solvent extraction
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Author :
Publisher :
Page : 9 pages
File Size : 21,63 MB
Release : 1998
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Two main objectives concerning removal of fission products from high-level tank wastes will be accomplished in this project. The first objective entails the development of an acid-side Cs solvent-extraction (SX) process applicable to remediation of the sodium-bearing waste (SBW) and dissolved calcine waste (DCW) at INEEL. The second objective is to develop alkaline-side SX processes for the combined removal of Tc, Cs, and possibly Sr and for individual separation of Tc (alone or together with Sr) and Cs. These alkaline-side processes apply to tank wastes stored at Hanford, Savannah River, and Oak Ridge. This work exploits the useful properties of crown ethers and calixarenes and has shown that such compounds may be economically adapted to practical processing conditions. Potential benefits for both acid- and alkaline-side processing include order-of-magnitude concentration factors, high rejection of bulk sodium and potassium salts, and stripping with dilute (typically 10 mM) nitric acid. These benefits minimize the subsequent burden on the very expensive vitrification and storage of the high-activity waste. In the case of the SRTALK process for Tc extraction as pertechnetate anion from alkaline waste, such benefits have now been proven at the scale of a 12-stage flowsheet tested in 2-cm centrifugal contactors with a Hanford supernatant waste simulant. SRTALK employs a crown ether in a TBP-modified aliphatic kerosene diluent, is economically competitive with other applicable separation processes being considered, and has been successfully tested in batch extraction of actual Hanford double-shell slurry feed (DSSF).
Author : R. A. Leonard
Publisher :
Page : 88 pages
File Size : 20,92 MB
Release : 1985
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Page : pages
File Size : 18,38 MB
Release : 1985
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This report summarizes the work done to date on the application of the TRUEX solvent extraction process for removing and separately recovering plutonium and americium from a nitric acid waste solution containing these elements, uranium, and a complement of inert metal ions. This simulated waste stream is typical of a raffinate from a tributyl phosphate (TBP)-based solvent extraction process for removing uranium and plutonium from dissolved plutonium-containing metallurgical scrap. The TRUEX process solvent in these experiments was a solution of TBP and octyl(phenyl)-N, N-diisobutylcarbamoylmethylphosphine oxide (CMPO) dissolved in carbon tetrachloride. A flowsheet was designed on the basis of measured batch distribution ratios to reduce the TRU content of the solidified raffinate to less than or equal to 10 nCi/g and was tested in a countercurrent experiment performed in a 14-stage Argonne-model centrifugal contractor. The process solvent was recycled without cleanup. An unexpectedly high evaporative loss of CCl4 resulted in concentration of the active extractant, CMPO, to nearly 0.30M in the solvent. Results are consistent with this higher CMPO concentration. The raffinate contained only 2 nCi/g of TRU, but the higher CMPO concentration resulted in reduced effectiveness in the stripping of americium from the solvent. Conditions can be easily adjusted to give high yields and good separation of americium and plutonium. Experimental studies of the hydrolytic and gamma-radiolytic degradation of the TRUEX-CCl4 showed that solvent degradation would be (1) minimal for a year of processing this typical feed, which contained no fission products, and (2) could be explained almost entirely by hydrolytic and radiolytic damage to TBP. Even for gross amounts of solvent damage, scrubbing with aqueous sodium carbonate solution restored the original americium extraction and stripping capability of the solvent. 43 refs., 5 figs., 36 tabs.