TY - JOUR
T1 - Determination of nitrogen in uranium-plutonium mixed oxide fuel by gas chromatography after fusion in an inert gas atmosphere
AU - Hiyama, Toshiaki
AU - Takahashi, Toshio
AU - Kamimura, Katsuichiro
PY - 1997/6/20
Y1 - 1997/6/20
N2 - A gas chromatographic technique has been developed for the determination of nitrogen in uranium-plutonium mixed oxide fuel after fusion in an inert gas atmosphere. When the sample and pure iron powder in a graphite crucible were heated to approximately 2500°C by a resistance heating furnace, a large amount of carbon monoxide was evolved with a small amount of nitrogen and hydrogen. A gas chromatograph equipped with a pre-cut system was used for the separation of nitrogen from the carbon monoxide. Nitrogen separated by the gas chromatograph was determined by means of a thermal conductivity detector. Only 100 mg of the sample was used, and the analysis requires about 10 min. No specific skills for glove-box work are necessary. The relative standard deviation and detection limit (3σ-criterion)were less than 5% and 9μg g-1, respectively. The present method is not only applicable to the analysis of research samples but also to the quality control of uranium-plutonium mixed oxide fuel production lines.
AB - A gas chromatographic technique has been developed for the determination of nitrogen in uranium-plutonium mixed oxide fuel after fusion in an inert gas atmosphere. When the sample and pure iron powder in a graphite crucible were heated to approximately 2500°C by a resistance heating furnace, a large amount of carbon monoxide was evolved with a small amount of nitrogen and hydrogen. A gas chromatograph equipped with a pre-cut system was used for the separation of nitrogen from the carbon monoxide. Nitrogen separated by the gas chromatograph was determined by means of a thermal conductivity detector. Only 100 mg of the sample was used, and the analysis requires about 10 min. No specific skills for glove-box work are necessary. The relative standard deviation and detection limit (3σ-criterion)were less than 5% and 9μg g-1, respectively. The present method is not only applicable to the analysis of research samples but also to the quality control of uranium-plutonium mixed oxide fuel production lines.
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U2 - 10.1016/S0003-2670(97)00109-8
DO - 10.1016/S0003-2670(97)00109-8
M3 - Article
AN - SCOPUS:0030997790
SN - 0003-2670
VL - 345
SP - 131
EP - 137
JO - Analytica Chimica Acta
JF - Analytica Chimica Acta
IS - 1-3
ER -