Purification and recovery of plutonium from uranium oxide obtained in the fast reactor fuel reprocessing plant using hydroxyurea as reductant

Spent fuel discharged from Fast Breeder Test Reactor (FBTR) in Kalpakkam is being reprocessed by modified plutonium uranium reduction extraction (PUREX) process using 30% TBP (tributylphosphate) as extractant in the presence of heavy normal paraffin (HNP) as diluent. Partitioning of uranium (U) and...

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Veröffentlicht in:Journal of radioanalytical and nuclear chemistry 2012-03, Vol.291 (3), p.763-767
Hauptverfasser: Sivakumar, P., Meenakshi, S., Rao, R. V. Subba
Format: Artikel
Sprache:eng
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