SOHIO process legacy waste treatment: Uranium recovery using ion exchange
| Autor: | Clint A. Sharrad, James T.M. Amphlett, Keun-Young Lee, Kwang-Wook Kim, Timothy Kerry, Richard I. Foster |
|---|---|
| Rok vydání: | 2020 |
| Předmět: |
General Chemical Engineering
chemistry.chemical_element 02 engineering and technology 010402 general chemistry 01 natural sciences symbols.namesake chemistry.chemical_compound Adsorption SOHIO process Effluent Ion exchange Elution Chemistry Effluent treatment Langmuir adsorption model Uranium 021001 nanoscience & nanotechnology 0104 chemical sciences Waste catalyst Waste treatment symbols 0210 nano-technology Sodium carbonate Nuclear chemistry |
| Zdroj: | Foster, R, Amphlett, J, Kim, K-W, Kerry, T, Lee, K & Sharrad, C 2020, ' SOHIO process legacy waste treatment: Uranium recovery using ion exchange ', Journal of Industrial and Engineering Chemistry, vol. 81, pp. 144-152 . https://doi.org/10.1016/j.jiec.2019.09.001 |
| ISSN: | 1226-086X |
| DOI: | 10.1016/j.jiec.2019.09.001 |
| Popis: | The feasibility of employing ion-exchange resins for the selective removal of uranium from a complex waste effluent has been investigated. The source of the effluent is a treatment process to reduce the volume of a spent uranium containing catalyst prior to its immobilisation and disposal in South Korea. Commercial anion exchange and chelation resins have been screened, along with an in-house synthesized polyamine functionalized resin. The Langmuir isotherm model produced the best fit for UO22+ binding to all resins, with Purolite MTS957, a mixed sulfonic/phosphonic acid functionalised resin, showing the highest equilibrium adsorption capacity for UO22+, 96.15 mg g-1. The Modified Dose-Response Model was found to adequately represent breakthrough across all flow rates used and for all resins tested under dynamic testing conditions. The maximum uranium loading capacities under dynamic conditions for simulant and real wastes were established as 131.52 mg g-1 and 68.62 mg g-1,respectively. Purolite MTS957 effectively decontaminated the real effluent to uranium levels below the Korean release limit of 1 mg L-1. Over 99.9% uranium was successfully eluted from the resin bed in under 20 BV with a mixed sodium carbonate/sulfate eluent. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
|
Full Text from ScienceDirect