Technology for Obtaining Natural-Uranium Concentrates to ASTM C 967–08 Specifications

Peganov, V. A.; Molchanova, T. V.; Akimova, I. D.; Zharova, E. V.

doi:10.1007/s10512-015-9941-5

Cited by 5 publications

(4 citation statements)

References 1 publication

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“…Considering this range, we evaluated the intervals of ISL parameters for the selected uranium deposits (see Table 4). The parameters calculated by (Khomenko et al, 2017) vary within the intervals typical for uranium ISL under similar geological conditions in Kazakhstan, Uzbekistan, Ukraine, and other countries that were analysed by Peganov et al (2015). Based on the simulation results, using the methods of National Atomic Company "Kazatomprom" (Panova et al, 2021;Kopbaeva et al, 2016) to calculate ISL parameters, we evaluated technological parameters of hexagonal well arrangement for five ore bodies located at different depths (see Figures 5 and 6).…”

Section: Technological Parameters Of Horizon-oriented Islmentioning

confidence: 99%

Managing the Horizon-Oriented in-Situ Leaching for the Uranium Deposits of Mongolia

Khomenko,

Rudakov,

Lkhagva

et al. 2023

MGPB

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This paper summarizes the results of evaluating uranium in-situ leaching (ISL) parameters for hydrogenous deposits in eastern Mongolia. This method, also known as in-situ recovery (ISR) or solution mining was proposed for mining used to extract uranium from underground deposits without physically removing the ore. The studies included drilling, geophysical surveying, evaluations of rock properties and chemical composition of rocks and groundwater, as well as modelling coupled flow and transport for the “Ul’zit” deposit as a case study. The proposed horizon-oriented approach to process separate ore bodies at different depths allows for the mining process to be adapted to layered heterogeneity and allows successive leaching by wells of varying diameter and special design. This approach may reduce drilling costs and shorten the time for mining uranium deposits in Mongolia by 2 times on average. It was proven that this method is an environmentally friendly and cost-effective alternative to traditional underground or open-pit mining for uranium ore bodies. The economic evaluation confirms the effectiveness of the proposed solutions.

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Section: Technological Parameters Of Horizon-oriented Islmentioning

confidence: 99%

Managing the Horizon-Oriented in-Situ Leaching for the Uranium Deposits of Mongolia

Khomenko,

Rudakov,

Lkhagva

et al. 2023

MGPB

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“…The Purolite A660/4759 and VPAE resins were used in the work. The process of uranium elution from saturated anion exchangers under static conditions was carried out using three different eluents: solutions of sodium chloride (0.5-6 M), solutions of the ammonium carbonate/bicarbonate (50-180 g L -1 ), as well as nitrate-sulfate solutions (20-80 g L -1 NO3 -+ 0.1-0.25 mol L -1 H2SO4) [21][22][23][24]. According to the research results, when the chloride elution scheme is implemented, the uranium recovery from the saturated anion exchanger phase increases with growth NaCl concentration in the solution in the range 0.5-2 M (Fig.…”

Section: Regeneration In Static Modementioning

confidence: 99%

Processing of Chloride-Containing Productive Solutions after Uranium <i>in situ</i> Leaching by Ion Exchange Method

et al. 2019

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The uranium sorption from productive solutions containing chloride ions using anion-exchange resins was investigated. The VPAE ion exchanger had the highest values of the sorption capacity, which for the experiment in the static mode was 13 kg U m-3, and for the experiment in the dynamic mode, it was equal to 36 kg U m-3. The use of VPAE anion exchanger will make it possible for uranium recovery from productive solutions with an increased content of chloride without sacrificing the productivity of the sorption plant. The process of saturated resins regeneration by various reagents was investigated. The use of ammonium nitrate solution with sulfuric acid ensured maximum value of uranium recovery from the saturated resin phase (76–97%).

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“…The quality of uranium oxide concentrate (U 3 O 8 ) with a U content of ≥ 84% required additional costly operations to reduce U(VI) to U(IV) in a gaseous environment with hydrogen or membrane electrolyzers with purification of UF 4 from impurities that prevent its conversion into UF 6 [4].…”

Section: Introductionmentioning

confidence: 99%

Physical and Chemical Foundations of the Technology for Obtaining Uranium Oxides

Mukhachev¹,

Yelatontsev²,

Kharitonova³

2022

Problems of Atomic Science and Technology

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The article presents the results of industrial testing of processes for obtaining high-purity uranium compounds, including extraction, concentration, and purification of uranium from a mixture of nitric and phosphoric acids, solid-phase stripping, and reduction of U(VI) to U(IV). It is shown that the combination of three different extraction lines for the concentration and purification of uranium from accompanying valuable elements and radioactive isotopes makes it possible to obtain a natural uranium concentrate with a low content of impurities, which determine the economics of uranium hexafluoride production. The processes of drying and roasting of crystals of ammonium uranyl tricarbonate after solid-phase re-extraction in an atmosphere of reducing gases of ammonia and hydrogen make it possible to obtain uranium dioxide suitable for fluorination to obtain tetra and uranium hexafluoride.

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Technology for Obtaining Natural-Uranium Concentrates to ASTM C 967–08 Specifications

Cited by 5 publications

References 1 publication

Managing the Horizon-Oriented in-Situ Leaching for the Uranium Deposits of Mongolia

Managing the Horizon-Oriented in-Situ Leaching for the Uranium Deposits of Mongolia

Processing of Chloride-Containing Productive Solutions after Uranium <i>in situ</i> Leaching by Ion Exchange Method

Physical and Chemical Foundations of the Technology for Obtaining Uranium Oxides

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