Oxidative leaching of uranium from SIMFUEL using Na2CO3–H2O2 solution

Chung, Dong-Yong; Seo, Heui-Seung; Lee, Jae Won; Yang, Han-Beom; Lee, Eil‐Hee

doi:10.1007/s10967-009-0443-6

Cited by 41 publications

(14 citation statements)

References 17 publications

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“…The advantages of the alkaline leaching process include higher selectivity, a lower corrosively than acid leaching and insoluble of desirable metals, such as iron and silica. Chung et al (2010) explained a successful in the leaching of Polish sandstone ores by using the oxidative process for simulated nuclear fuel. The approximate complete extraction of uranium was attained in that case by Frackiewicz et al (2012).…”

Section: Introductionmentioning

confidence: 99%

Recovery of uranium and copper from mineralized dolostone, Gabal Allouga, Southwestern Sinai, Egypt

Orabi

El‐Sheikh

Saleh

et al. 2019

Journal of Radiation Research and Applied Sciences

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To avert excessive sulfuric acid exhaustion in the classical leaching procedure and to avoid leaching of other undesirable impurities, proper alkaline leaching has been achieved for dolostone of Gabal Allouga, Southwestern Sinai, Egypt. The relevant factors for alkaline leaching of a technological sample assaying 1.2% Cu and 0.15% U were examined using a mixture of Na 2 CO 3 / (NH 4) HCO 3 solution upon two samples namely; roasted sample at 540°C and raw materials un-roasted. The leaching kinetic results showed that the leaching procedure of uranium and copper from dolostone is controlled by shrinking core kinetic model 1-2/3(X)−(1−X) 2/3 = k d t.

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Section: Introductionmentioning

confidence: 99%

Recovery of uranium and copper from mineralized dolostone, Gabal Allouga, Southwestern Sinai, Egypt

Orabi

El‐Sheikh

Saleh

et al. 2019

Journal of Radiation Research and Applied Sciences

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“…An important feature is that hydrogen peroxide (H2O2) does not oxidize the Pu, Np, and Am oxides in contrast to UO2 which is oxidized to UO3 [13]. In this case, the oxide phases of the TUEs as a part of SNF should not be dissolved in carbonate solutions together with uranium in the oxidative leaching step [6,13,14]. In the case of anodic dissolution of SNF in carbonate media, Np(IV) in the form of NpO2 can be oxidized to a hexavalent oxidation state.…”

Section: Introductionmentioning

confidence: 99%

Oxidative Dissolution of Neptunium(iv) Oxide in Carbonate Solutions

Chervyakov¹,

Boyarintsev²,

Перевалов³

et al. 2021

RAD Conference Proceedings

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This article presents preliminary results of the study of neptunium(IV) oxide dissolution in aqueous solutions of Na2CO3 in the presence of ammonium persulfate and hydrogen peroxide. In these carbonate systems, the value of NpO2 dissolution yield did not exceed 1.5-1.6%. Ultrasonication makes it possible to significantly increase the dissolution rate of neptunium(IV) oxide in Na2CO3 solutions in the presence of hydrogen peroxide. Under such conditions, about 25% of neptunium(IV) oxide powder can be dissolved in one dissolution step (210-270 min). A possible factor affecting the increase of NpO2 dissolution yield is the increase of oxidative and reaction activity in the carbonate systems under ultrasonic impact.

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“…Specifically, oxidation is effective in increasing the amount of soluble uranium, which is generally accomplished by the use of oxidants such as sodium chlorate (NaClO 3 ), 18 20 and hydrogen peroxide (H 2 O 2 ). 21 Among these oxidants, H 2 O 2 is the only reagent that has no environmental effects and leads to a decrease in the acidity of the medium. 22 The effect of H 2 O 2 on uranium extraction has been shown previously.…”

Section: Introductionmentioning

confidence: 99%

Kinetics of Uranium Extraction from Uranium Tailings by Oxidative Leaching

Zhang

et al. 2016

JOM

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Extraction of uranium from uranium tailings by oxidative leaching with hydrogen peroxide (H 2 O 2 ) was studied. The effects of various extraction factors were investigated to optimize the dissolution conditions, as well as to determine the leaching kinetic parameters. The behavior of H 2 O 2 in the leaching process was determined through scanning electron microscopy-energy dispersive x-ray spectroscopy (SEM-EDX) and x-ray diffraction analysis of leaching residues. Results suggest that H 2 O 2 can significantly improve uranium extraction by decomposing the complex gangue structures in uranium tailings and by enhancing the reaction rate between uranium phases and the leaching agent. The extraction kinetics expression was changed from 1 À 3(1 À a) 2/3 + 2(1 À a) = K 0 (H 2 SO 4 ) À0.14903 (S/L) À1.80435 (R o ) 0.20023 e À1670.93/ T t (t ‡ 5) to 1 À 3(1 À a) 2/3 + 2(1 À a) = K 0 (H 2 SO 4 ) 0.01382 (S/L) À1.83275 (R o ) 0.25763 e À1654.59/T t (t ‡ 5) by the addition of H 2 O 2 in the leaching process. The use of H 2 O 2 in uranium leaching may help in extracting uranium more efficiently and rapidly from low-uranium-containing ores or tailings.

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Oxidative leaching of uranium from SIMFUEL using Na2CO3–H2O2 solution

Cited by 41 publications

References 17 publications

Recovery of uranium and copper from mineralized dolostone, Gabal Allouga, Southwestern Sinai, Egypt

Recovery of uranium and copper from mineralized dolostone, Gabal Allouga, Southwestern Sinai, Egypt

Oxidative Dissolution of Neptunium(iv) Oxide in Carbonate Solutions

Kinetics of Uranium Extraction from Uranium Tailings by Oxidative Leaching

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