Purification of lithium carbonate by ion-exchange processes for application in nuclear reactors

dc.creatorANDRADE, MARIANA N.
dc.creatorOLIVEIRA, GLAUCIA A.C.
dc.creatorPIRANI, DEBORA A.
dc.creatorCOUTINHO, JOAO F.
dc.creatorBERGAMASCHI, VANDERLEI S.
dc.creatorSENEDA, JOSE A.
dc.creatorBUSTILLOS, JOSE O.V.
dc.creatorINTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
dc.date2020-01-14T14:50:29Z
dc.date2020-01-14T14:50:29Z
dc.dateOctober 21-25, 2019
dc.date.accessioned2023-09-28T14:13:38Z
dc.date.available2023-09-28T14:13:38Z
dc.identifierhttp://repositorio.ipen.br/handle/123456789/30670
dc.identifier.urihttps://repositorioslatinoamericanos.uchile.cl/handle/2250/9000897
dc.descriptionLithium Compounds have applications in strategic areas for intern consumption of a country as well as international commerce. In nuclear industry, the lithium is used for the cooling of PWR reactors as a pH stabilizer. Based on this assumption, the generation of knowledge to master the processing cycle of these compounds is essential. The high degree of purity of lithium compounds is determinant to have success in these applications. Lithium hydroxide LiOH and lithium carbonate Li2CO3 are the main forms in which lithium is used industrially. To improve the quality of the starting product, purifying process were used until obtaining an adequate purity level of raw material (> 99%). The present work aims to make feasible a purification of Li2CO3 through ion-exchange chromatography from a 98.5% purity compound. The impurities present in higher content are sodium and calcium. To separate these two elements from lithium or at least to lower their concentrations, a column with cationic resin was used to fix lithium. The determination of lithium, sodium and calcium contents in the solutions was performed by inductively coupled plasma optical emission spectrometry, ICP-OES. The experiments performed to evaluate the best lithium purification condition were based on the variation of the main operational parameters: pH, flow and elution solution. The results indicate increased purity from the application of ion exchange operations obtaining a suitable condition for nuclear uses.
dc.format3153-3157
dc.publisherAssocia????o Brasileira de Energia Nuclear
dc.rightsopenAccess
dc.subjectaqueous solutions
dc.subjectcalcium
dc.subjectimpurities
dc.subjection exchange chromatography
dc.subjectlithium carbonates
dc.subjectpurification
dc.subjectsodium
dc.titlePurification of lithium carbonate by ion-exchange processes for application in nuclear reactors
dc.typeTexto completo de evento
dc.coverageI
dc.localRio de Janeiro


Este ítem pertenece a la siguiente institución