Analysis of Minor Actinides in Mixed Oxide Fuel Irradiated in Fast Reactor(1)Determination of Neptunium-237

DOI Web Site 被引用文献3件 参考文献13件
  • KOYAMA Shin-ichi
    Alpha Gamma Section, O-arai Engineering Center,Power Reactor and Nuclear Fuel Development Corporation
  • OTSUKA Yuko
    Alpha Gamma Section, O-arai Engineering Center,Power Reactor and Nuclear Fuel Development Corporation
  • OSAKA Masahiko
    Alpha Gamma Section, O-arai Engineering Center,Power Reactor and Nuclear Fuel Development Corporation
  • MOROZUMI Katsufumi
    Alpha Gamma Section, O-arai Engineering Center,Power Reactor and Nuclear Fuel Development Corporation
  • KONNO Koichi
    Alpha Gamma Section, O-arai Engineering Center,Power Reactor and Nuclear Fuel Development Corporation
  • KAJITANI Mikio
    Nuclear Fuel Cycle Development Section, Head Office,Power Reactor and Nuclear Fuel Development Corporation
  • MITSUGASHIRA Toshiaki
    Nuclear Fuel Cycle Development Section, Head Office,Power Reactor and Nuclear Fuel Development Corporation The Oarai Branch, Institute for Materials Research, Tohoku University

書誌事項

タイトル別名
  • Analysis of Minor Actinides in Mixed Oxide Fuel Irradiated in Fast Reactor, (I). Determination of Neptunium-237.
  • Analysis of Minor Actinides in Mixed Ox
  • Determination of Neptunium-237

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The MOX (mixed oxide) fuels, 29.97 wt% (analytical value is 28.08 wt%) plutonium in 8.3 or 12.1 wt% enriched uranium were irradiated up to 120 GWd/t in the MARK-II core of JOYO. The irradiated MOX fuels were dissolved in 8M nitric acid solution. Anion exchange chromatographic procedures were developed for the isolation of neptunium contained in these MOX solutions. Neptunium-237 was separated from the other actinides by using the developed chromatographic technique and the content of 237Np was determined by α spectrometry.<BR>It was found that the content of 237Np slightly increased with increasing burnup. The content did not exceed 0.08 wt% in the 30 wt% MOX fuels irradiated up to about 120 GWd/t. Model calculation by ORIGEN-2 reproduces well the observed content of 237Np.

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