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Title: Simultaneous measurements of plutonium and uranium in spent-fuel dissolver solutions

Abstract

The authors have studied the isotope dilution gamma-ray spectrometry (IDGS) technique for simultaneous measurements of elemental concentrations and isotopic compositions for both plutonium and uranium in input spent-fuel dissolver solutions at a reprocessing plant. The technique under development includes both sample preparation and analysis methods. For simultaneous measurements of both plutonium and uranium, a critical issue is to develop a new method to keep both plutonium and uranium in the sample after they are separated from fission products. Furthermore, it is equally important to improve the analysis method so that the precision and accuracy of the plutonium analysis remain unaffected while uranium is retained in the sample. To keep both plutonium and uranium in the sample for simultaneous measurements, extraction chromatography is being studied and shows promise to achieve the goal of cosegregation of the plutonium and uranium. 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 subsequent measuring using high-resolution gamma-ray spectrometry. Owing to the fact that the U/Pu ratio is altered during the fission product separation phase, it is necessary to develop a method which could accurately correct for this effect. Such a method wasmore » developed using the unique decay properties of {sup 241}Pu to {sup 237}U and shows considerable promise in allowing for accurate determination of the {sup 235}U concentrations before the chemical extraction.« less

Authors:
 [1]; ; ; ; ;  [2]
  1. Los Alamos National Lab., NM (United States)
  2. Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan)
Publication Date:
Research Org.:
Los Alamos National Lab., NM (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
548660
Report Number(s):
LA-UR-97-2715; CONF-970744-
ON: DE98001030; TRN: 98:001071
DOE Contract Number:
W-7405-ENG-36
Resource Type:
Conference
Resource Relation:
Conference: 38. annual meeting of the Institute of Nuclear Materials management, Phoenix, AZ (United States), 20-24 Jul 1997; Other Information: PBD: [1997]
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; 40 CHEMISTRY; PLUTONIUM; URANIUM; GAMMA SPECTROSCOPY; EXTRACTION CHROMATOGRAPHY; SPENT FUELS; REPROCESSING; PROCESS SOLUTIONS; DISSOLUTION; CONCENTRATION RATIO

Citation Formats

Li, T.K., Kuno, T., Kitagawa, O., Sato, S., Kurosawa, A., and Kuno, Y.. Simultaneous measurements of plutonium and uranium in spent-fuel dissolver solutions. United States: N. p., 1997. Web.
Li, T.K., Kuno, T., Kitagawa, O., Sato, S., Kurosawa, A., & Kuno, Y.. Simultaneous measurements of plutonium and uranium in spent-fuel dissolver solutions. United States.
Li, T.K., Kuno, T., Kitagawa, O., Sato, S., Kurosawa, A., and Kuno, Y.. 1997. "Simultaneous measurements of plutonium and uranium in spent-fuel dissolver solutions". United States. doi:. https://www.osti.gov/servlets/purl/548660.
@article{osti_548660,
title = {Simultaneous measurements of plutonium and uranium in spent-fuel dissolver solutions},
author = {Li, T.K. and Kuno, T. and Kitagawa, O. and Sato, S. and Kurosawa, A. and Kuno, Y.},
abstractNote = {The authors have studied the isotope dilution gamma-ray spectrometry (IDGS) technique for simultaneous measurements of elemental concentrations and isotopic compositions for both plutonium and uranium in input spent-fuel dissolver solutions at a reprocessing plant. The technique under development includes both sample preparation and analysis methods. For simultaneous measurements of both plutonium and uranium, a critical issue is to develop a new method to keep both plutonium and uranium in the sample after they are separated from fission products. Furthermore, it is equally important to improve the analysis method so that the precision and accuracy of the plutonium analysis remain unaffected while uranium is retained in the sample. To keep both plutonium and uranium in the sample for simultaneous measurements, extraction chromatography is being studied and shows promise to achieve the goal of cosegregation of the plutonium and uranium. 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 subsequent measuring using high-resolution gamma-ray spectrometry. Owing to the fact that the U/Pu ratio is altered during the fission product separation phase, it is necessary to develop a method which could accurately correct for this effect. Such a method was developed using the unique decay properties of {sup 241}Pu to {sup 237}U and shows considerable promise in allowing for accurate determination of the {sup 235}U concentrations before the chemical extraction.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1997,
month =
}

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  • We have studied the improvement in simultaneous measurements of concentrations and isotopic compositions for plutonium in input spent-fuel dissolver solutions at a reprocessing plant by isotope dilution gamma-ray spectrometry (IDGS) technique. The IDGS technique uses the high-resolution low-energy gamma-ray spectrometry and isotope dilution method. The dissolver solutions are subsequently measured using high-resolution gamma-ray spectrometry following the fission product separations by extraction chromatography using U/TEVA{center_dot}Spec resins. The improved method can simplify the separation procedure and save more than 2 hours in sample preparation time. The results of plutonium concentrations and isotopic compositions of dissolver solutions analyzed by IDGS agree very wellmore » with those obtained by traditional isotope dilution mass spectrometry. The rapid and accurate IDGS technique with the improved separation method could provide a timely, less expensive, and simpler on-site verification method for the input accountability measurements.« less
  • We have developed a novel technique, isotope dilution gamma-ray spectroscopy (IDGS), for simultaneously determining the plutonium concentration and the isotopic composition of irradiated spent-fuel dissolver solutions, such as the input accountability solutions to a chemical reprocessing plant. The plutonium isotopic analysis is based on high-resolution, low-energy gamma-ray spectrometry. To measure the plutonium concentration in the dissolver solution, a spike is added to the unknown dissolver solution. We then determine the concentration from the measured isotopic differences among the spike, the dissolver solution, and the spiked dissolver solution. Resin bead techniques have been developed to rapidly separate fission products and recovermore » plutonium from dissolver solutions for measurements by high-resolution gamma-ray spectrometry. Both plutonium concentrations and isotopic compositions of dissolver solutions analyzed by IDGS agree very well with those obtained by traditional isotope dilution mass spectrometry. The rapid and accurate IDGS technique can provide a timely, less expensive, and simpler on-site verification method of the plutonium in the input accountability samples.« less
  • An experiment conducted jointly by the International Atomic Energy Agency, the COGEMA reprocessing facility at LaHague, France, the French Center for Nuclear Studies at Saclay, and ORNL is nearing completion. The aim of this experiment is to evaluate the use of internal standards when applied under field conditions to spent fuel dissolver solutions. Samples were taken at LaHague and shipped to Saclay, the IAEA in Vienna, and ORNL. Both resin beads and dried residues were shipped. ORNL has analyzed plutonium and uranium from these samples with good results: external precisions for uranium concentrations were +-0.06% and for plutonium +-0.2%. Copiesmore » of our report sheets are given in the appendices. 17 refs., 10 tabs.« less