Hot-Cell Studies of Aqueous Dissolution Processes for Irradiated Carbide Reactor Fuels

Flanary, J.R.; Goode, J.H.; Bradley, Mildred J.; Ullmann, J.W.; Ferris, L.M.; Wall, G.C.

doi:10.2172/4020314

Cited by 10 publications

(9 citation statements)

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“…Oxidation was then used to remove the filler carbon and the outer carbon layer, followed by crushing of the Sic shells and additional burning of the inner carbon layer. The remnant ashes were leached using nitric acid and the resulting solution interfaced with conventional solvent extraction (Flanary et al, 1964;Vaughen et al, 1970;Colby et al, 197 1). This technology was demonstrated for fuels in which the fissile components were either carbides or oxides.…”

Section: Previous Experiences Reported In the Literaturementioning

confidence: 99%

TRISO-Coated Fuel Processing to Support High Temperature Gas-Cooled Reactors

Cul¹

2002

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Section: Previous Experiences Reported In the Literaturementioning

confidence: 99%

TRISO-Coated Fuel Processing to Support High Temperature Gas-Cooled Reactors

Cul¹

2002

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“…A number of studies have been reported in the literature on the head-end treatment of carbide fuel f o r obtaining feed solutions compatible with the Purex process ( 1 ) . Of the methods reported, oxidation in 0 and C02 streams and pyrohydrolysis to convert the carbide to oxide have many disadvantages particularly in respect of carbide fuels with high-Pu content ( 1 ) .…”

Section: Photochemical Destruction Of Organic Compounds Formed Duringmentioning

confidence: 99%

“…The direct dissolution of carbides in nitric acid is a comparatively convenient procedure. However, this step leads to the formation of a number of organic compounds (1,2). During the dissolution, less than 60% of carbon is removed as C02, the exact percentage depending on the conditions of dissolution (3).…”

Section: Photochemical Destruction Of Organic Compounds Formed Duringmentioning

confidence: 99%

Photochemical Destruction of Organic Compounds Formed During Dissolution of Uranium Carbide in Nitric Acid

Nayak

Srinivasan

Rao

et al. 1988

Separation Science and Technology

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The dissolution of carbide fuels in nitric acid leads to the formation of a number of organic compounds which cause serious interference in the subsequent steps of reprocessing. In the present work, the optimum conditions for the photochemical destruction of these compounds by excited uranyl ion were established. The optimum concentration of uranium was found to be in the range 10 -45 mg/mL. The destruction rate was found to decrease with increase in acidity. It was established that apart from oxalic and mellitic acids, some other unidentified compounds were also responsible for the interference in solvent extraction.

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“…Flanary et al [20] carried out detailed investigations on both un-irradiated and irradiated carbide fuels, where even though pyrohydrolysis was employed no attention seemed to have been paid to identify the soluble organic species in the pyrohydrolysis distillate. It is known that the dissolution of uranium carbide fuel (both un-irradiated and irradiated) leads to the formation of a number of soluble organic acids and species which includes oxalic, mellitic and few un-identified acids [21][22][23][24].…”

Section: Introductionmentioning

confidence: 99%

Study on the identification of organic and common anions in the pyrohydrolysis distillate of mixed uranium-plutonium carbide for the interference free determination of chlorine and fluorine by ion chromatography

et al. 2014

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Identification of various soluble organic acids formed during the pyrohydrolysis of uranium-plutonium mixed carbide [(U,Pu)C] was carried out using ion chromatography. This has significant importance as the soluble organic acids can cause severe interferences during the ion chromatography separation and determination of Cl − and F − in the pyrohydrolysis distillate of (U,Pu)C. Determination of Cl and F is important in the chemical quality control of nuclear materials as these two elements can cause corrosion and hence, their concentrations in all nuclear materials are restricted to certain specified values. Since the pyrohydrolysis distillates contain both inorganic and organic acid anions, for the sake of separating and identifying organic acid anions from the common inorganic anions, three independent isocratic elutions using varying concentrations of NaOH eluent were employed for the separation of weakly, moderately and strongly retained anions. It was observed that pyrohydrolysis of (U,Pu)C also produced soluble organic acids as in the case of nitric acid dissolution of UC. The present investigation revealed the presence of formic, acetic, propionic, butyric, oxalic acid anions in the pyrohydrolysis distillate of (U,Pu)C in trace or ultra-trace concentrations. The presence of each organic acid identified in the chromatogram was confirmed with spike addition as well as by separating them by capillary electrophoresis method. The presence of lower aliphatic acids viz. formic and acetic acids was reconfirmed by carrying out an independent separation with tetraborate eluent. It is suggested that nitric acid being formed during pyrohydrolysis could be responsible for the formation of organic acids. Based on the findings, an ion chromatography separation method has been proposed for the interferencefree determination of chloride and fluoride in pyrohydrolysis distillate of (U,Pu)C.

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Hot-Cell Studies of Aqueous Dissolution Processes for Irradiated Carbide Reactor Fuels

Cited by 10 publications

References 0 publications

TRISO-Coated Fuel Processing to Support High Temperature Gas-Cooled Reactors

TRISO-Coated Fuel Processing to Support High Temperature Gas-Cooled Reactors

Photochemical Destruction of Organic Compounds Formed During Dissolution of Uranium Carbide in Nitric Acid

Study on the identification of organic and common anions in the pyrohydrolysis distillate of mixed uranium-plutonium carbide for the interference free determination of chlorine and fluorine by ion chromatography

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