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Remediation of radioiodine using polyamine anion exchange resins
Daniel N.T. Barton,Thomas J. Robshaw,Oluwatobi Okusanya,김대근,Sarah E. Pepper,Clint A. Sharrad,이택승,Mark D. Ogden 한국공업화학회 2019 Journal of Industrial and Engineering Chemistry Vol.78 No.-
Two weak base anion exchange resins, Lewatit A365 and Purolite MTS9850, have been tested for theremoval of aqueous iodide from conditions simulating nuclear waste reprocessing streams. pH variationand relevant co-contaminant addition (nitrate, molybdate and iodine) allowed for assessment of iodideextraction behaviour of each resin. Isotherm experiments were performed and maximum uptakecapacities obtained exceed current industrial adsorbents, such as silver-impregnated zeolites. Maximumloading capacities, determined by Dubinin–Radushkevich isotherm, were 76114 mg g 1 for MTS9850and 589 15 mg g 1 for A365. Uptake for both resins was significantly suppressed by nitrate andmolybdate ions. The presence of dissolved iodine in the raffinate however, was found to increase iodideuptake. This was explained by characterisation of the spent resin surface by infrared and Ramanspectroscopy, which determined the presence of triiodide, indicating charge-transfer complex formationon the surface. Dynamic studies assessed the effect of co-contaminants on iodide uptake in a columnenvironment. Data wasfitted to three dynamic models, with the Dose-Response model providing the bestdescription of breakthrough. In all cases iodide breakthrough was accelerated, indicating suppression ofuptake, but capacity was still significant.
SOHIO process legacy waste treatment: Uranium recovery using ion exchange
Richard I. Foster,James T.M. Amphlett,Kwang-Wook Kim,Timothy Kerry,Keun-Young Lee,Clint A. Sharrad 한국공업화학회 2020 Journal of Industrial and Engineering Chemistry Vol.81 No.-
The feasibility of employing ion-exchange resins for the selective removal of uranium from a complexwaste effluent has been investigated. The source of the effluent is a treatment process to reduce thevolume 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-housesynthesized polyamine functionalized resin. The Langmuir isotherm model produced the bestfit 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 allflow rates used and for allresins tested under dynamic testing conditions. The maximum uranium loading capacities underdynamic 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 theKorean release limit of 1 mg L 1. Over 99.9% uranium was successfully eluted from the resin bed in under20 BV with a mixed sodium carbonate/sulfate eluent.