Open AccessTheoretical analysis of sodium removal from Fast Flux Test Facility fuel subassemblies.
Author(s) -
R.R. Borisch
Publication year - 1972
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4550161
Subject(s) - purex , plutonium , raffinate , uranium , chemistry , nuclear reprocessing , transuranium element , radiochemistry , nuclear engineering , spent nuclear fuel , burnup , nuclear fuel cycle , mox fuel , environmental science , solvent extraction , nuclear chemistry , radioactive waste , materials science , metallurgy , extraction (chemistry) , engineering , chromatography
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