The oxidative dissolution of unirradiated UO2 by hydrogen peroxide as a function of pH

Clarens, F.; Pablo, Joan de; Casas, I.; Giménez, Javier; Rovira, Miquel; Merino, Juan; Cera, E.; Bruno, Jordi; Quiñones, J.; Martínez-Esparza, A.

doi:10.1016/j.jnucmat.2005.06.002

Cited by 60 publications

(41 citation statements)

References 36 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The resulting rate constant is 4.2 ± 0.7 · 10 À9 mol dm À3 m min À1 (7 ± 1 · 10 À8 mol m À2 s À1 ). Interestingly, this rate constant is significantly (more than one order of magnitude) higher than previously reported rate constants for UO 2 dissolution in the presence of H 2 O 2 [11,19]. It should be noted that the previously reported values are based on measurements of uranium release while our value is based on consumption of H 2 O 2 .…”

Section: Resultscontrasting

confidence: 62%

Effects of on the kinetics of UO2 oxidation by H2O2

Hossain

Ekeroth

Jönsson

2006

Journal of Nuclear Materials

View full text Add to dashboard Cite

Section: Resultscontrasting

confidence: 62%

Effects of on the kinetics of UO2 oxidation by H2O2

Hossain

Ekeroth

Jönsson

2006

Journal of Nuclear Materials

View full text Add to dashboard Cite

“…There are several other reports of the formation of (meta)studtite upon H 2 O 2 oxidation of UO 2 [8,[13][14][15][16][17][18] and of the formation of schoepite by O 2 oxidation [6,19]. The mechanical weakness of the studtite layer has also been reported [11,16].…”

Section: Introductionmentioning

confidence: 93%

“…Oxidative UO 2 dissolution rates under various conditions have been reported in numerous publications [4,5,7,9,10,13,14,[21][22][23][30][31][32][33][34][35]44,48,50,53,54]. The studies considered here were all performed at room [7,10,34,44].…”

Section: Dissolution Of Oxidized Uo 2 (S)mentioning

confidence: 99%

See 1 more Smart Citation

Oxidation of UO2(s) in aqueous solution

Roth

Jönsson

2008

Open Chemistry

View full text Add to dashboard Cite

Abstract:In this review the kinetics and mechanism of oxidative dissolution of UO 2 (s), mainly under conditions of relevance for the safety assessment of a deep geological repository for spent nuclear fuel, are discussed. Rate constants for the elementary processes involved (oxidation of UO 2 and dissolution of oxidized UO 2 ) are used to calculate the rates of oxidative UO 2 (s) dissolution under various conditions (type of oxidant, oxidant concentration and HCO 3 -/CO 3 2-concentration) for which experimental data are also available. The calculated rates are compared to the corresponding experimental values under the assumption that the experimental numbers reflect the steady-state conditions of the system. The agreement between the calculated rates and the corresponding experimental ones is very good, in particular for the higher rates. In general, the calculated rates are somewhat higher than the experimental numbers. This can be due partly to the use of initial concentrations rather than steady-state concentrations in the calculations. The kinetic data are also used to quantitatively discuss the dynamics of spent nuclear fuel dissolution under deep geological repository conditions. © Versita Warsaw and Springer-Verlag Berlin Heidelberg.

show abstract

“…The available decontamination processes for equipment items often involve alkaline medium in which the formation of RuO 4 remains very limited [10,11], thereby limiting the transfer of contamination. To the best of our knowledge, relatively few studies have been carried out on the oxidative dissolution of fission product oxides [12][13][14][15][16][17][18][19] and only one example of complete oxidative dissolution of ruthenium oxides [20]. We therefore focused our investigation on the oxidative dissolution of RuO 2 ·xH 2 O in suspension or RuO(OH) 2 ·xH 2 O deposited on stainless steel surfaces by strong oxidizing agents in alkaline medium.…”

Section: Introductionmentioning

confidence: 99%

Oxidative dissolution of ruthenium deposits onto stainless steel by permanganate ions in alkaline medium

Floquet¹,

Eysseric

Maurel³

2008

Radiochimica Acta

View full text Add to dashboard Cite

Ruthenium / Ruthenium deposits / Permanganate ions / Oxidative dissolution / Alkaline medium / Waste reprocessingSummary. During spent nuclear fuel reprocessing ruthenium is liable to form black ruthenium deposits on the stainless steel walls of process equipments. These deposits promote corrosion and can eventually obstruct the off-gas lines. The results of decontamination of 304L stainless steel test specimens covered with RuO(OH) 2 ·xH 2 O deposits by permanganate ions in alkaline medium are described. The ruthenium deposits were dissolved by oxidation of RuO(OH) 2 to RuO 4 2− ions, while the permanganate ions were reduced to MnO 4 2− ions and then to manganese dioxide MnO 2 . The parameters affecting the kinetics of oxidative dissolution of these deposits were examined. The results indicate that the oxidative dissolution kinetics depends on the instantaneous surface area of the deposit, and that the dissolution rate increases with the concentrations of MnO 4 − and OH − ions.

show abstract

The oxidative dissolution of unirradiated UO2 by hydrogen peroxide as a function of pH

Cited by 60 publications

References 36 publications

Effects of on the kinetics of UO2 oxidation by H2O2

Effects of on the kinetics of UO2 oxidation by H2O2

Oxidation of UO2(s) in aqueous solution

Oxidative dissolution of ruthenium deposits onto stainless steel by permanganate ions in alkaline medium

Contact Info

Product

Resources

About