Feasibility study of plutonium and uranium measurements in input dissolver solutions

Conference · Sun Oct 01 04:00:00 EDT 1995

OSTI ID:114651

Li, T K ^[1]; Kitagawa, O; Kuno, Y; Kurosawa, A ^[2]

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1. Los Alamos National Lab., NM (United States)
2. Power Reactor & Nuclear Fuel Development Corp., Ibaraki-Ken (Japan)

We are studying the isotope dilution gamma-ray spectrometry (IDGS) technique for the simultaneous measurements of concentrations and isotopic compositions for both plutonium and uranium in spent-fuel dissolver solutions at a reprocessing plant. Previous experiments have demonstrated that the IDGS technique can determine the elemental concentrations and isotopic compositions of plutonium in dissolver solutions. The chemical separation and recovery methods for just plutonium were ion-exchange techniques using anion exchange resin beads and filter papers. To keep both plutonium and uranium in the sample for simultaneous measurements, a new sample preparation method is being studied and developed: extraction chromatography. The technique uses U/TEVA{center_dot}Spec resin to separate fission products and recover both uranium and plutonium in the resin from dissolver solutions for measurements by high-resolution gamma-ray spectrometry.

• Research Organization: Los Alamos National Lab., NM (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 114651
• Report Number(s): LA-UR--95-3380; CONF-950923--11; ON: DE96001374
• Country of Publication: United States
• Language: English

Related Subjects

40 CHEMISTRY
CONCENTRATION RATIO
EXTRACTION CHROMATOGRAPHY
GAMMA SPECTRA
GAMMA SPECTROSCOPY
PLUTONIUM
PLUTONIUM 238
PLUTONIUM 239
PLUTONIUM 240
PLUTONIUM 241
PLUTONIUM 242
RESINS
SOLUTIONS
SPENT FUELS
URANIUM