Open AccessISPO Task A-126: Application of Mixed Internal Standards to the Mass Spectrometric Analysis of Plutonium and Uranium in Spent Fuel Dissolver Solutions: ORNL Results
Author(s) -
D. H. Smith,
R.L. Walker,
J. A. Carter
Publication year - 1985
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/12162149
Subject(s) - plutonium , uranium , enriched uranium , spent nuclear fuel , nuclear engineering , mox fuel , transuranium element , plutonium 239 , plutonium 240 , environmental science , radiochemistry , isotopes of uranium , nuclear reprocessing , nuclear fuel , waste management , nuclear physics , chemistry , engineering , physics , fission , neutron
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