Open AccessPUREX PROCESS FOR PLUTONIUM AND URANIUM RECOVERY
Author(s) -
W.B. Lanham,
T.C. Runion
Publication year - 1949
Language(s) - English
Resource type - Reports
DOI - 10.2172/4165457
Subject(s) - purex , plutonium , tributyl phosphate , uranium , human decontamination , radiochemistry , chemistry , neptunium , extraction (chemistry) , nuclear chemistry , solvent extraction , fission products , nuclear reprocessing , process (computing) , waste management , chromatography , materials science , metallurgy , computer science , engineering , operating system
Labcratory data which indicate that the recovery of Pu and U and decontamination from fission products are feasible in a solvent extraction process using tributyl phosphate are given. The procedure consists of extracting Pu(IV) and U with 15% TBP--85% Varsol using 5.0 N HNO/sub 3/ as a salting agent. (J.R.D.
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