Waste management analysis for the nuclear fuel cycle: Parts I and II. Progress report, April 1--September 30, 1977. [Actinide recovery from waste]

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A preliminary evaluation of methods for the salt waste and waste water streams and recycle preparation problems was completed. A feasibility study for removing actinides from synthetic salt waste showed that a bidentate organophosphorus extractant is the most efficient for actinide removal. The evaluation of adsorbents for removing detergents and anions from waste water suggests the use of a combination of non-ionic and a strong base ion exchange resin for best results. Evaluation of leaching and dissolution methods for the recovery of actinides from combustible waste (incinerator ash) was continued. Two promising recovery methods are: (1) reaction with cerium(IV) in ... continued below

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Pages: 27

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Navratil, J. D.; Martella, L. L.; Smith, C. M.; Thompson, G. H.; Cash, D. L.; Childs, E. L. et al. October 23, 1978.

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A preliminary evaluation of methods for the salt waste and waste water streams and recycle preparation problems was completed. A feasibility study for removing actinides from synthetic salt waste showed that a bidentate organophosphorus extractant is the most efficient for actinide removal. The evaluation of adsorbents for removing detergents and anions from waste water suggests the use of a combination of non-ionic and a strong base ion exchange resin for best results. Evaluation of leaching and dissolution methods for the recovery of actinides from combustible waste (incinerator ash) was continued. Two promising recovery methods are: (1) reaction with cerium(IV) in nitric acid to solubilize carbon and actinide oxides, and (2) fusion with carbonate--nitrate mixtures. Silica proved to be a problem. If dissolved, it interferes with subsequent actinide recovery by forming polysilicic acid upon acidification. If not solubilized, silica-encapsulated actinide oxides may not be contacted by the dissolvent. Pretreatment of ash by refluxing with greater than or equal to 6M sodium hydroxide appears to remove silica, simplifying subsequent recovery steps.

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Pages: 27

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Dep. NTIS, PC A03/MF A01.

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  • Report No.: RFP-2749
  • Grant Number: EY-76-C-04-3533
  • DOI: 10.2172/6441796 | External Link
  • Office of Scientific & Technical Information Report Number: 6441796
  • Archival Resource Key: ark:/67531/metadc1208674

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  • October 23, 1978

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  • July 5, 2018, 11:11 p.m.

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  • Aug. 31, 2018, 12:41 p.m.

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Navratil, J. D.; Martella, L. L.; Smith, C. M.; Thompson, G. H.; Cash, D. L.; Childs, E. L. et al. Waste management analysis for the nuclear fuel cycle: Parts I and II. Progress report, April 1--September 30, 1977. [Actinide recovery from waste], report, October 23, 1978; United States. (digital.library.unt.edu/ark:/67531/metadc1208674/: accessed January 20, 2019), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.