Determination of oxygen-to-metal atomic ratio in mixed oxide fuel by non-dispersive infrared spectrophotometry after fusion in an inert gas atmosphere

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Abstract

A new method of analysis for the determination of the oxygen-to-metal atomic ratio (O/M) in a uranium-plutonium mixed oxide (MOX) fuel was developed. The sample and the nickel metal were fused in a graphite crucible in a resistance heating furnace under helium flowing through the system. The oxygen in the MOX fuel reacted quantitatively with the crucible graphite producing carbon monoxide, which was determined using non-dispersive infrared spectrophotometry (NDIR). The oxygen content in the MOX fuel was calculated from the analysis results of the carbon monoxide. The O/M ratios determined by the present method were in good agreement with those of the thermogravimetric method. The relative standard deviation was less than 0.20% for sintered MOX fuel. Only 30mg of sample was required, and the analysis time takes about 10min. No specific skills for glove-box work are necessary. The present method is applicable to sintered MOX fuels over a wide range of plutonium contents. Copyright (C) 1999 Elsevier Science B.V.

Original languageEnglish
Pages (from-to)297-302
Number of pages6
JournalAnalytica Chimica Acta
Volume402
Issue number1-2
DOIs
Publication statusPublished - Dec 3 1999

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Infrared Spectrophotometry
Mixed oxide fuels
Noble Gases
Spectrophotometry
spectrophotometry
Atmosphere
Oxides
Fusion reactions
Metals
oxide
Oxygen
Infrared radiation
oxygen
atmosphere
metal
Plutonium
gas
Graphite
Crucibles
plutonium

All Science Journal Classification (ASJC) codes

  • Analytical Chemistry
  • Biochemistry
  • Environmental Chemistry
  • Spectroscopy

Cite this

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title = "Determination of oxygen-to-metal atomic ratio in mixed oxide fuel by non-dispersive infrared spectrophotometry after fusion in an inert gas atmosphere",
abstract = "A new method of analysis for the determination of the oxygen-to-metal atomic ratio (O/M) in a uranium-plutonium mixed oxide (MOX) fuel was developed. The sample and the nickel metal were fused in a graphite crucible in a resistance heating furnace under helium flowing through the system. The oxygen in the MOX fuel reacted quantitatively with the crucible graphite producing carbon monoxide, which was determined using non-dispersive infrared spectrophotometry (NDIR). The oxygen content in the MOX fuel was calculated from the analysis results of the carbon monoxide. The O/M ratios determined by the present method were in good agreement with those of the thermogravimetric method. The relative standard deviation was less than 0.20{\%} for sintered MOX fuel. Only 30mg of sample was required, and the analysis time takes about 10min. No specific skills for glove-box work are necessary. The present method is applicable to sintered MOX fuels over a wide range of plutonium contents. Copyright (C) 1999 Elsevier Science B.V.",
author = "Toshiaki Hiyama",
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T1 - Determination of oxygen-to-metal atomic ratio in mixed oxide fuel by non-dispersive infrared spectrophotometry after fusion in an inert gas atmosphere

AU - Hiyama, Toshiaki

PY - 1999/12/3

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N2 - A new method of analysis for the determination of the oxygen-to-metal atomic ratio (O/M) in a uranium-plutonium mixed oxide (MOX) fuel was developed. The sample and the nickel metal were fused in a graphite crucible in a resistance heating furnace under helium flowing through the system. The oxygen in the MOX fuel reacted quantitatively with the crucible graphite producing carbon monoxide, which was determined using non-dispersive infrared spectrophotometry (NDIR). The oxygen content in the MOX fuel was calculated from the analysis results of the carbon monoxide. The O/M ratios determined by the present method were in good agreement with those of the thermogravimetric method. The relative standard deviation was less than 0.20% for sintered MOX fuel. Only 30mg of sample was required, and the analysis time takes about 10min. No specific skills for glove-box work are necessary. The present method is applicable to sintered MOX fuels over a wide range of plutonium contents. Copyright (C) 1999 Elsevier Science B.V.

AB - A new method of analysis for the determination of the oxygen-to-metal atomic ratio (O/M) in a uranium-plutonium mixed oxide (MOX) fuel was developed. The sample and the nickel metal were fused in a graphite crucible in a resistance heating furnace under helium flowing through the system. The oxygen in the MOX fuel reacted quantitatively with the crucible graphite producing carbon monoxide, which was determined using non-dispersive infrared spectrophotometry (NDIR). The oxygen content in the MOX fuel was calculated from the analysis results of the carbon monoxide. The O/M ratios determined by the present method were in good agreement with those of the thermogravimetric method. The relative standard deviation was less than 0.20% for sintered MOX fuel. Only 30mg of sample was required, and the analysis time takes about 10min. No specific skills for glove-box work are necessary. The present method is applicable to sintered MOX fuels over a wide range of plutonium contents. Copyright (C) 1999 Elsevier Science B.V.

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