Nitric Acid Dissolution of Uranium-Molybdenum Alloy Reactor Fuels

Schulz, W.W.; Burns, R. E.; Duke, E.M.

doi:10.1021/i260002a017

Cited by 19 publications

(26 citation statements)

References 3 publications

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“…Long-term behaviour of stored radioactive materials can only be assessed when good thermodynamic data on a variety of uranium compounds are available. Uranyl molybdate, UO 2 MoO 4 , is one of a number of different uraniummolybdenum phases in the system U-Mo-O and it is important for technological reasons [1]. UO [2][3][4][5][6][7].…”

Section: Introductionmentioning

confidence: 99%

A calorimetric and thermodynamic investigation of uranyl molybdate UO2MoO4

Сулейманов

Голубев

Alekseev

et al. 2010

The Journal of Chemical Thermodynamics

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Section: Introductionmentioning

confidence: 99%

A calorimetric and thermodynamic investigation of uranyl molybdate UO2MoO4

Сулейманов

Голубев

Alekseev

et al. 2010

The Journal of Chemical Thermodynamics

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“…Polyions of the formula (Mo 6 O 21 ) 6-have been postulated to exist in acid molybdate solutions. (8) To evaluate the solubility data for the dissolution of U-10Mo metal alloy against literature data obtained by dissolving MoO 3 in solutions of U and HNO 3 , the data of Faugeras were interpolated.…”

Section: Solubilitymentioning

confidence: 99%

Purification of Uranium from a Uranium/Molybdenum Alloy

Visser¹,

Pierce²,

Laurinat³

2008

Separation Science and Technology

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The Savannah River Site will recycle a nuclear fuel comprised of 90% uranium-10% molybdenum by weight. The process flowsheet calls for dissolution of the material in nitric acid to a uranium concentration of 15-20 g/L without the formation of precipitates. The dissolution will be followed by separation of uranium from molybdenum using solvent extraction with 7.5% tributylphosphate in n-paraffin. Testing with the fuel validated dissolution and solubility data reported in the literature. Batch distribution coefficient measurements were performed for the extraction, strip and wash stages with particular focus on the distribution of molybdenum. uranium molybdenum solubility distribution solvent extraction

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“…Measurements of off gas during the dissolution of the Piqua (U-3Mo) fuels in H-Canyon yielded a maximum of 0.2 vol% H 2(9). Hydrogen gas measured from the dissolution of U-3Mo in HNO 3 -Fe(NO 3 ) 3 ranged from 0.05-0.20 vol% while U-10Mo showed no detectable H 2 under similar conditions(5). Less than 0.1 vol% H 2 was evolved for U metal dissolution at 100 o C in both 4 M HNO 3 and 7 M HNO 3(3).…”

mentioning

confidence: 92%

“…SRNL tests indicate that material dissolved in 6 M HNO 3 at 100 o C to concentrations as high as 2.3 g/L Mo with ~21 g/L U does not readily precipitate. If U-Mo solids happen to form, they are flocculent and can be removed with a centrifuge and then washed(5). Studies have indicated that most of the U in the solids can be removed by washing with acid.…”

mentioning

confidence: 99%

Uranium-Molybdenum Dissolution Flowsheet Studies

Pierce

2007

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The Super Kukla (SK) Prompt Burst Reactor operated at the Nevada Test Site from 1964 to 1978. The SK material is a uranium-molybdenum (U-Mo) alloy material of 90% U/10% Mo by weight at approximately 20% 235 U enrichment. H-Canyon Engineering (HCE) requested that the Savannah River National Lab (SRNL) define a flowsheet for safely and efficiently dissolving the SK material. The objective is to dissolve the material in nitric acid (HNO 3 ) in the H-Canyon dissolvers to a U concentration of 15-20 g/L (3-4 g/L 235 U) without the formation of precipitates or the generation of a flammable gas mixture.Testing with SK material validated the applicability of dissolution and solubility data reported in the literature for various U and U-Mo metals. Based on the data, the SK material can be dissolved in boiling 3.0-6.0 M HNO 3 to a U concentration of 15-20 g/L and a corresponding Mo concentration of 1.7-2.2 g/L. The optimum flowsheet will use 4.0-5.0 M HNO 3 for the starting acid. Any nickel (Ni) cladding associated with the material will dissolve readily. After dissolution is complete, traditional solvent extraction flowsheets can be used to recover and purify the U.

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Nitric Acid Dissolution of Uranium-Molybdenum Alloy Reactor Fuels

Cited by 19 publications

References 3 publications

A calorimetric and thermodynamic investigation of uranyl molybdate UO2MoO4

A calorimetric and thermodynamic investigation of uranyl molybdate UO2MoO4

Purification of Uranium from a Uranium/Molybdenum Alloy

Uranium-Molybdenum Dissolution Flowsheet Studies

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