Journal ArticleDOI
Removal of actinides from selected nuclear fuel reprocessing wastes
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In this paper, the authors present a cost-risk-benefit analysis of partitioning long-lived nuclides from waste and transmuting them to shorter-lived or stable Nuclides, and show that the use of tributyl phosphate (TBP) followed by extraction with a bidentate organophosphorous extractant (DHDECMP) appears to be the most efficient for removing actinides from saltmore waste.Abstract:
The US Department of Energy awarded Oak Ridge National Laboratory a program to develop a cost-risk-benefit analysis of partitioning long-lived nuclides from waste and transmuting them to shorter lived or stable nuclides. Two subtasks of this program were investigated at Rocky Flats. In the first subtask, methods for solubilizing actinides in incinerator ash were tested. Two methods appear to be preferable: reaction with ceric ion in nitric acid or carbonate-nitrate fusion. The ceric-nitric acid system solubilizes 95% of the actinides in ash; this can be increased by 2 to 4% by pretreating ash with sodium hydroxide to solubilize silica. The carbonate-nitrate fusion method solubilizes greater than or equal to 98% of the actinides, but requires sodium hydroxide pretreatment. Two additional disadvantages are that it is a high-temperature process, and that it generates a lot of salt waste. The second subtask comprises removing actinides from salt wastes likely to be produced during reactor fuel fabrication and reprocessing. A preliminary feasibility study of solvent extraction methods has been completed. The use of a two-step solvent extraction system - tributyl phosphate (TBP) followed by extraction with a bidentate organophosphorous extractant (DHDECMP) - appears to be the most efficient for removing actinides from saltmore » waste. The TBP step would remove most of the plutonium and > 99.99% of the uranium. The second step using DHDECMP would remove > 99.91% of the americium and the remaining plutonium (> 99.98%) and other actinides from the acidified salt waste. 8 figures, 11 tables.« lessread more
Citations
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Journal ArticleDOI
Actinide partitioning—a review
TL;DR: In this paper, a review of the state-of-the-art reagents and methods for hydrometallurgical partitioning of actinides from different types of transuranium wastes and dissolved fuels is presented.
Journal ArticleDOI
Aqueous Partitioning of Minor Actinides by Different Processes
TL;DR: In this article, the authors proposed a strategy for effective mitigation of the long-term hazards associated with high-level waste (HLW) by actinide partitioning, where substituted malonamide extractants such as DMDBTDMA and DMDOHEMA have emerged as viable green alternatives to phosphine oxides.
Book ChapterDOI
Actinide Separation Science and Technology
TL;DR: In this paper, it was shown that the field of metal ion separations, solvent extraction, and ion exchange in particular, would not be as important as it is today were it not for the discovery and exploitation of the actinides.
Journal ArticleDOI
Americium recovery and purification using a combined anion exchange‐extraction chromatography process
TL;DR: A combined anion exchange-extraction chromatography process for the recovery and purification of americium from molten salt extraction residues has been successfully demonstrated on a laboratory and pilot plant scale as mentioned in this paper.
Book ChapterDOI
Development of highly selective compounds for solvent extraction processes: partitioning and transmutation of long-lived radionuclides from spent nuclear fuels
TL;DR: In this paper, the authors discuss the methodology deployed in the European partitioning strategy to design highly selective extractants for long-lived radionuclide separation: calix[4]arenes for caesium, malonamides for the co-extraction of trivalent minor actinides (Am, Cm) and lanthanides (Ln(III)).
References
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ReportDOI
Preliminary assessment of partitioning and transmutation as a radioactive waste management concept
TL;DR: Partitioning the actinide elements from nuclear fuel cycle wastes and transmuting them to fission products in power reactors represents a potentially advanced concept of radioactive waste management which could reduce the long-term (greater than 1000 years) risk associated with geologic isolation of wastes as discussed by the authors.
ReportDOI
Actinide Partitioning and Transmutation Program. Progress report, April 1--June 30, 1977
D. W. Tedder,J. O. Blomeke +1 more
TL;DR: In this article, the 16 tasks comprising the Actinide Partitioning and Transmutation Program (JRD) were continued. Summaries of work are given on Purex Process modifications, actinide recovery, Am-Cm recovery, radiation effects on ion exchangers, LMFBR transmutation studies, thermal reactor transmutation, fuel cycle studies, and partitioning-transmutation evaluation.
ReportDOI
Fluidized bed incineration of radioactive waste. [Transuranics]
TL;DR: A fluidized-bed incineration facility is being designed for installation at the Rocky Flats Plant to demonstrate a process for the combustion of transuranic waste as discussed by the authors, which will utilize in situ neutralization of acid gases generated in the process.