Separation of Plutonium from Irradiated Fuels and Targets
Author(s) -
L. Gray,
Kiel Holliday,
Alice Murray,
M.C. Thompson,
D.T. Thorp,
S.L. Yarbro,
Theodore Venetz
Publication year - 2015
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/1240057
Subject(s) - plutonium , spent nuclear fuel , transuranium element , fission products , plutonium 240 , nuclear reprocessing , actinide , uranium , waste management , radioactive waste , nuclear fuel cycle , purex , radiochemistry , environmental science , high level waste , fissile material , nuclear power , plutonium 239 , nuclear engineering , fission , chemistry , nuclear chemistry , materials science , neutron , nuclear physics , engineering , metallurgy , physics , extraction (chemistry) , solvent extraction , chromatography
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