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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. Sat . "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 = {Sat Nov 01 00:00:00 EST 1997},
month = {Sat Nov 01 00:00:00 EST 1997}
}

Conference:
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