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

• 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

Bibliographic Information

Other Title

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

Abstract

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.

Journal

• Journal of Nuclear Science and Technology

  Journal of Nuclear Science and Technology 35 (6), 406-410, 1998

  Atomic Energy Society of Japan

Keywords

• minor actinide
• neptunium 237
• mixed oxide fuels
• fast reactors
• ion exchange
• isotope analysis
• alpha spectrometry

Details

• CRID: 1390001204094615168
• NII Article ID: 10002079525
• NII Book ID: AA00703720
• DOI: 10.3327/jnst.35.406
• COI: 1:CAS:528:DyaK1cXltVSjs7k%3D
• ISSN: 18811248
• ISSN: 00223131
• NDL BIB ID: 4503987
• Web Site: https://ndlsearch.ndl.go.jp/books/R000000004-I4503987
• Text Lang: en
• Data Source:
  • JaLC
  • NDL
  • Crossref
  • CiNii Articles
• Abstract License Flag: Disallowed