Advanced Separation Technologies for Processing Spent Nuclear Fuel and the Potential Benefits to a Geologic Repository

Todd, T. A.; Wigeland, R. A.

doi:10.1021/bk-2006-0933.ch003

Cited by 40 publications

(39 citation statements)

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“…As well as their complexing properties, hydroxamic acids are hydroxylamine derivatives and are easily oxidized by metal ions such as Np(VI) [6,7]. Consequently, applications of simple hydrophilic hydroxamic ligands (R = H or CH 3 ) for the stripping of actinides in much simplified Purex solvent extraction flowsheets for advanced fuel cycles have been reported [8][9][10][11].…”

Section: Introductionmentioning

confidence: 99%

Oxidation–reduction reactions of simple hydroxamic acids and plutonium(IV) ions in nitric acid

Carrott¹,

Fox²,

LeGurun³

et al. 2008

Radiochimica Acta

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SummarySimple hydroxamic acids such as formo- and aceto-hydroxamic acids have been proposed as suitable reagents for the separation of either Pu and/or Np from U in modified or single cycle Purex based solvent extraction processes designed to meet the emerging requirements of advanced fuel cycles. The stability of these hydroxamic acids is dominated by their decomposition through acid hydrolysis. Kinetic studies of the acid hydrolysis of formo- and aceto-hydroxamic acids are reported in the absence and the presence of Pu(IV) ions. The slow reduction of these plutonium(IV) hydroxamate complexes to Pu(III) aquo-ions has been characterised by spectrophotometry and cyclic voltammetry. The reductions of Pu(IV) in the presence of FHA and AHA are consistent with a mechanism in which free hydroxamic acid in solution is hydrolysed whilst Pu(IV) ions remain fully complexed to hydroxamate ligands; then at some point close to a 1 : 1 Pu(IV) : XHA ratio, some free Pu

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Section: Introductionmentioning

confidence: 99%

Oxidation–reduction reactions of simple hydroxamic acids and plutonium(IV) ions in nitric acid

Carrott¹,

Fox²,

LeGurun³

et al. 2008

Radiochimica Acta

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“…Advanced fuel recycling technologies are capable of efficiently removing and transmuting the most radiotoxic long-lived portions of used nuclear fuel (UNF)the transuranics. 3,4 The primary resulting waste stream contains fission products, inert chemicals, and trace transuranics. This waste stream can be effectively immobilized by nuclear waste vitrification.…”

Section: Motivationmentioning

confidence: 99%

Nuclear Waste Vitrification in the United States: Recent Developments and Future Options

Vienna

2010

Int J of Appl Glass Sci

199

130

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Nuclear power plays a key role in maintaining current worldwide energy growth while minimizing the greenhouse gas emissions. A disposition path for used nuclear fuel (UNF) must be found for this technology to achieve its promise. One likely option is to recycle UNF and immobilize the high‐level waste (HLW) by vitrification. Vitrification is the technology of choice for immobilizing HLW from defense and commercial fuel reprocessing around the world. Recent advances in both recycling technology and vitrification show great promise in closing the U.S. nuclear fuel cycle in an efficient fashion. This article summarizes the recent trends, developments, and future options in waste vitrification for both defense waste cleanup and closing the nuclear fuel cycle in the United States.

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“…It is now well acknowledged and supported by extensive calculations that removal of between 99 and 99.9% of the U, Pu, Am and Cs and Sr can significantly reduce repository heat load and hence increase capacity by up to a factor of 50 [1][2][3][4][5]. In other words, the selective removal of high heat load elements from waste or used fuel can result in greatly enhanced repository utilization.…”

Section: Introductionmentioning

confidence: 98%

Tungstate-based glass–ceramics for the immobilization of radio cesium

Drabarek

McLeod

Hanna

et al. 2009

Journal of Nuclear Materials

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Advanced Separation Technologies for Processing Spent Nuclear Fuel and the Potential Benefits to a Geologic Repository

Cited by 40 publications

References 0 publications

Oxidation–reduction reactions of simple hydroxamic acids and plutonium(IV) ions in nitric acid

Oxidation–reduction reactions of simple hydroxamic acids and plutonium(IV) ions in nitric acid

Nuclear Waste Vitrification in the United States: Recent Developments and Future Options

Tungstate-based glass–ceramics for the immobilization of radio cesium

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