Determination of trace amounts of plutonium in low-active liquid wastes from spent nuclear-fuel reprocessing plants by flow injection-based solid-phase extraction/electrochemical detection system

Shigeo Taguchi, Masahiko Yamamoto, Naoki Surugaya, Akira Kurosawa, Toshiaki Hiyama, Tatsuhiko Tanaka

研究成果: ジャーナルへの寄稿記事

5 引用 (Scopus)

抄録

A flow injection-based electrochemical detection system coupled to a solid-phase extraction column was developed for the determination of trace amounts of plutonium in low-active liquid wastes from spent nuclear-fuel reprocessing plants. The oxidation state of plutonium in a sample solution was adjusted to Pu(VI) by the addition of silver(II) oxide. A sample solution was made up in 3 mol L-1 HNO3 and loaded onto a column packed with UTEVA® with 3 mol L-1 HNO3 as the carrier. Plutonium(VI) was adsorbed onto the resin, and interfering elements were removed by rinsing the column with 3 mol L-1 HNO3. Subsequently, the adsorbed Pu(VI) was eluted with 0.01 mol L-1 HNO3, and then introduced directly into the flow-through electrolysis cell with boron-doped diamond electrode. The eluted Pu(VI) was detected by an electrochemical amperometric method at a working potential of 0.1 V (vs. Ag/AgCl). The current produced on reduction of Pu(VI) was continuously monitored and recorded. The plutonium concentration was calculated from the relationship between the peak area and concentration of plutonium. The relative standard deviation of ten analyses was 1.1% for a plutonium solution of 25 μg L -1 containing 50 ng of Pu. The detection limit calculated from three-times the standard deviation was 0.82 μg L-1 (1.6 ng of Pu).

元の言語英語
ページ(範囲)435-441
ページ数7
ジャーナルJournal of Radioanalytical and Nuclear Chemistry
288
発行部数2
DOI
出版物ステータス出版済み - 5 1 2011

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Radioactive Waste
Plutonium
Nuclear fuel reprocessing
Spent fuels
Solid Phase Extraction
Injections
Liquids
Silver oxides
Electrolysis
Diamond
Boron
Limit of Detection
Diamonds
Electrodes
Resins
Oxidation

All Science Journal Classification (ASJC) codes

  • Analytical Chemistry
  • Nuclear Energy and Engineering
  • Radiology Nuclear Medicine and imaging
  • Pollution
  • Spectroscopy
  • Public Health, Environmental and Occupational Health
  • Health, Toxicology and Mutagenesis

これを引用

Determination of trace amounts of plutonium in low-active liquid wastes from spent nuclear-fuel reprocessing plants by flow injection-based solid-phase extraction/electrochemical detection system. / Taguchi, Shigeo; Yamamoto, Masahiko; Surugaya, Naoki; Kurosawa, Akira; Hiyama, Toshiaki; Tanaka, Tatsuhiko.

:: Journal of Radioanalytical and Nuclear Chemistry, 巻 288, 番号 2, 01.05.2011, p. 435-441.

研究成果: ジャーナルへの寄稿記事

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abstract = "A flow injection-based electrochemical detection system coupled to a solid-phase extraction column was developed for the determination of trace amounts of plutonium in low-active liquid wastes from spent nuclear-fuel reprocessing plants. The oxidation state of plutonium in a sample solution was adjusted to Pu(VI) by the addition of silver(II) oxide. A sample solution was made up in 3 mol L-1 HNO3 and loaded onto a column packed with UTEVA{\circledR} with 3 mol L-1 HNO3 as the carrier. Plutonium(VI) was adsorbed onto the resin, and interfering elements were removed by rinsing the column with 3 mol L-1 HNO3. Subsequently, the adsorbed Pu(VI) was eluted with 0.01 mol L-1 HNO3, and then introduced directly into the flow-through electrolysis cell with boron-doped diamond electrode. The eluted Pu(VI) was detected by an electrochemical amperometric method at a working potential of 0.1 V (vs. Ag/AgCl). The current produced on reduction of Pu(VI) was continuously monitored and recorded. The plutonium concentration was calculated from the relationship between the peak area and concentration of plutonium. The relative standard deviation of ten analyses was 1.1{\%} for a plutonium solution of 25 μg L -1 containing 50 ng of Pu. The detection limit calculated from three-times the standard deviation was 0.82 μg L-1 (1.6 ng of Pu).",
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