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J.T.M. Amphlett,S.E. Pepper,A.L. Riley,L.M. Harwood,J. Cowell,K.R. Whittle,T.S. Lee,M.D. Ogden 한국공업화학회 2020 Journal of Industrial and Engineering Chemistry Vol.82 No.-
Decommissioning is one of the most important phases in the life of a nuclear reactor, having a majorinfluence on public perception of such technology. Therefore, development of technologies that makedecommissioning more safe, effective and efficient is integral to the success of the nuclear industry. Inthis paper, phosphonic acid functionalised silica has been studied to determine its suitability for treatingnuclear decommissioning effluents produced in the HYBRID process, developed in South Korea. Cu2+recovery from HCl media in both static and dynamic modes was investigated, as well as the effect of Cu2+on Co2+ and Ni2+ recovery in a column loading system. Isothermal loading studies predicted a maximumloading capacity for Cu2+ of 22.82 mg g 1, however complex loading behaviour was observed. Cu2+sorption followed pseudo-second order kinetics with rapid uptake. Thermodynamic parameters havebeen extracted from collected kinetic data. Cu2+ outcompetes both Co2+ and Ni2+ for binding to the silicain column studies, which has implications for the use of phosphonic acid functionalised silica in treatingdecommissioning effluents. This work presents initial lab scale experiments, but shows the potential of Sibased extractants for use in metals recovery in the nuclear industry.
Dissolution behavior of SrO into molten LiCl for heat reduction in used nuclear fuel
Kang, Dokyu,Amphlett, James T.M.,Choi, Eun-Young,Bae, Sang-Eun,Choi, Sungyeol Korean Nuclear Society 2021 Nuclear Engineering and Technology Vol.53 No.5
This study reports on the dissolution behavior of SrO in LiCl at varying SrO concentrations from low concentrations to excess. The amount of SrO dissolved in the molten salt and the species present upon cooling were determined. The thermal behavior of LiCl containing various concentrations of SrO was investigated. The experimental results were compared with results from the simulated results using the HSC Chemistry software package. Although the reaction of SrO with LiCl in the standard state at 650 ℃ has a slightly positive Gibbs free energy, SrO was found to be highly soluble in LiCl. Experimentally determined SrO concentrations were found to be considerably higher than those present in used nuclear fuel (<2 g/kg). As Sr-90 is one of the most important heat-generating nuclides in used nuclear fuel, this finding will be impactful in the development of fast, simple, and proliferation-resistant heat reduction processes for used nuclear fuel without the need for separating nuclear materials. Heat reduction is important as it decreases both the volume necessary for final disposal and the worker handling risk.
Numerical study on the electrochemical properties of Ni, Fe, and Cr in molten LiCl-KCl
윤석주,( James T. M. Amphlett ),이윤우,강도규,최성열 한국공업화학회 2020 한국공업화학회 연구논문 초록집 Vol.2020 No.-
Molten salt electrorefining is widely adopted in various industries, including the nuclear industry where pyroprocessing is applied to lower the level of the radioactive wastes. For example, reactor internals of the pressurized water reactors, which are mainly composed of stainless steels, can be decontaminated by electrorefining processes. However, few studies have investigated the acquisition of electrochemical properties in the molten salt using computational modeling. This study obtains the electrochemical properties of the main elements in stainless steel (Fe, Cr, Ni) in molten LiCl-KCl by computational modeling. Cyclic voltammetry of Fe, Cr, and Ni in LiCl-KCl eutectic at 500°C is performed, and the voltammograms are analyzed by numerical fitting from the modeling using Digielch8. Properties such as apparent standard potential, diffusion coefficient, and heterogeneous rate constants are derived, and the reversibility of the electrode reaction is determined from the properties.
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.