Open AccessSolvent extraction studies of coprocessing flowsheets: results from campaigns 3 and 4 of the Solvent-Extraction Test Facility (SETF)
Author(s) -
E.D. Collins,
Dennis Benker,
J.E. Bigelow,
F.R. Chattin,
L.J. King,
R. G. Ross,
H.C. Savage
Publication year - 1982
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/707068
Subject(s) - plutonium , solvent , extraction (chemistry) , uranium , transuranium element , stripping (fiber) , dissolution , boiling point , boiling , solvent extraction , boiling water reactor , chemistry , waste management , nuclear chemistry , radiochemistry , environmental science , chromatography , materials science , metallurgy , nuclear engineering , organic chemistry , engineering , composite material
Experiments on tri-n-butyl phosphate solvent extraction of uranium and plutonium at full activity levels (Campaigns 3 and 4) were conducted in the Solvent Extraction Test Facility (SETF), located in one of the heavily shielded cells of the Transuranium Processing Plant. The primary objectives were: (1) to demonstrate and evaluate the first two cycles of the Hot Engineering Facility flowsheets (codecontamination and partial partitioning), and (2) to investigate and evaluate the use of HNO{sub 2} as the reductant for tetravalent plutonium during reductive stripping operations. Secondary objectives were to determine the solvent extraction behavior of feed solutions prepared by dissolving fuel from a boiling water reactor (BWR) and to improve the solvent extraction feed clarification
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