Extraction processing of concentrated solutions of uranyl nitrate with high impurities content

Detalles Bibliográficos
Parent link:Bulletin of the Tomsk Polytechnic University/ Tomsk Polytechnic University (TPU).— , 2006-2007
Vol. 311, № 3.— 2007.— [P. 23-27]
Outros autores: Korotkevich V. M., Lazarchuk V. V., Shikerun T. G., Shamin V. I., Mikhailova N. A., Dorda F. A.
Summary:Заглавие с титульного листа
Электронная версия печатной публикации
Process flowsheet of recycling uranium concentrated solutions with its purification from insoluble impurities of iron, silicon, molybdenum, calcium oxides and hydroxides and soluble impurities with application of centrifugal extractors cascade has been developed and suggested for commercial introduction. The process was carried out at extractant saturation (30 % tributyl phosphate in hydrocarbon diluent) in extraction assembly lower than a limiting level (85...95 g/l) and in wash assembly - at limiting saturation (up to 120 g/l). As a result the waste uranium content in water-tail solutions 0,01...0,04 g/l and minimal content of impurities in re-extractors is provided
Publicado: 2007
Series:Chemistry
Subjects:
Acceso en liña:http://www.lib.tpu.ru/fulltext/v/Bulletin_TPU/2007/v311eng/i3/05.pdf
Formato: Electrónico Capítulo de libro
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=182978
Descripción
Descrición Física:1 файл (210 Кб)
Summary:Заглавие с титульного листа
Электронная версия печатной публикации
Process flowsheet of recycling uranium concentrated solutions with its purification from insoluble impurities of iron, silicon, molybdenum, calcium oxides and hydroxides and soluble impurities with application of centrifugal extractors cascade has been developed and suggested for commercial introduction. The process was carried out at extractant saturation (30 % tributyl phosphate in hydrocarbon diluent) in extraction assembly lower than a limiting level (85...95 g/l) and in wash assembly - at limiting saturation (up to 120 g/l). As a result the waste uranium content in water-tail solutions 0,01...0,04 g/l and minimal content of impurities in re-extractors is provided