Extraction processing of concentrated solutions of uranyl nitrate with high impurities content [Electronic resource] / V. M. Korotkevich [et al.]

Уровень набора: (RuTPU)RU\TPU\book\169973, Bulletin of the Tomsk Polytechnic University / Tomsk Polytechnic University (TPU) = 2006-2007Альтернативный автор-лицо: Korotkevich, V. M.;Lazarchuk, V. V.;Shikerun, T. G.;Shamin, V. I.;Mikhailova, N. A.;Dorda, F. A.Язык: английский ; оригинала, русский.Страна: Россия.Описание: 1 файл (210 Кб)Серия: ChemistryРезюме или реферат: 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.Примечания о наличии в документе библиографии/указателя: [Bibliography: p. 27 (5 titles)].Тематика: extraction processing | concentrated solutions | uranyl nitrate | impurities | flowsheet | purification | iron oxides | silicon oxides | molybdenum oxides | calcium oxides | hydroxides | soluble impurities | insoluble impurities | centrifugal extractors | re-extractors | water-tail solutions | электронный ресурс Ресурсы он-лайн:Щелкните здесь для доступа в онлайн
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[Bibliography: p. 27 (5 titles)]

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

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